Text

Inservice Testing Program for Pumps & Valves - Manual Update, Detailed Description of Changes - Section 4.1
	ML030290082
Person / Time
Site:	Catawba
Issue date:	01/21/2003
From:	Gordon Peterson; Duke Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML030290082 (152)
	v • d • e

DETAILED DESCRIPTION OF CHANGES Catawba Nuclear Station Unit 1 and Unit 2 Changes for Catawba Unit I and Unit 2 are listed on pages 1 through 3. Detailed description of changes is listed on pages 4 through 9. The new revision number (26) applies to both units. The effective date for the changes as provided by this submittal is October 31, 2002.

ABBREVIATION CHANGES

- All codes have been reviewed to align with recommendations in publication "Guidelines for Inservice Testing at Nuclear Power Plants, NUREG 1482" IN-SERVICE TESTING PROGRAM DOCUMENT - Revision 3 added TABLE OF ABBREVIATIONS - Added the following Frequency code:

CM Condition Monitoring JUSTIFICATION FOR DEFERRAL - REVISIONS JFD Number Valve Number(s)

CN-CA-03 ICA0008,1CA0010,ICA0I2 2CA0008,2CA0010,2CA0012 CN-CA-04 1(2)CA0173 CN-CA-06 1(2)CA0291,1 (2)CA0292 CN-CF-02 ICF0031 ICF0040, ICF0049, 1CF0058 2CF003 I,2CF0040,2CF0049,2CF0058 CN-FW-01 1(2)FW0028,1(2)FW0056 CN-NI-04 INI0060, 1NI0071,1 NI0082, INI0094 2NI0060,2NI0071,2NI0082,2NI0094 CN-NI-06 1 N10059, 1N10070, 1N1008 1,1 N1093 2NI0059,2NI0070,2NI0081,2NI0093 CN-NI-14 INI0175,IN01176,1N10180,INO1181 2NI0175,2NIO176,2NOI 180,2NIO181 CN-NS-01 INS0004,1NS002 1,1 NS0098,1 NS0099 2NS0004,2NS0021,2NS0098,2NS0099 CN-NI-25 NI0125,1NI0129 2NIO125,2NI0129 CN-NV-12 INVOOOIA,INVO002A 2NVOOOIA,2NVO002A CN-SM-01 ISMOOOI,1SM0003,ISM0005, ISM0007 2SMOOO,2SM0003,2SM0005,2SM0007 Change Revised - Included in Condition Monitoring Program Revised - Included in Condition Monitoring Program Revised - Included in Condition Monitoring Program Revised - Included in Condition Monitoring Program Revised - Included in Condition Monitoring Program Revised - Included in Condition Monitoring Program Revised - Included in Condition Monitoring Program Revised - Included in Condition Monitoring Program Revised - Included in Condition Monitoring Program Deleted - Moved open stroke to Supplemental Program Deleted - Moved closed stroke to Supplemental Program Revised - Test Alternative modified JUSTIFICATION FOR DEFERRAL - NEW JFD Number CN-NI-25 Valves INI0054A, 1NI0065B, 1N10076A, INI0088B 2NI0054A,2NI0065B,2NI0076A,2NI0088B VALVE GENERIC RELIEF REQUEST - NEW CN-GRV-04 Appendix II Check Valve Condition Monitoring Page 1 of 9 10/31/02

DETAILED DESCRIPTION OF CHANGES Catawba Nuclear Station Unit 1 and Unit 2 VALVE SPECIFIC RELIEF REQUEST - NEW CN-SRV-VG-02 DIG Solenoid and Check Valve Testing VALVES REMOVED FROM CATAWBA INSERVICE TESTING System Valves NW 1 (2)NW0193,1(2)NW0194,1(2)NW0235,1(2)NW0236 VALVES ADDED TO THE CATAWBA INSERVICE TESTING PROGRAM System Valves NV 1(2)NV0046,1(2)NV0057,1(2)NV0068,1(2)NV0079 VALVE CHANGES TO INSERVICE TESTING PROGRAM Valve 1(2)LD0017 1(2)LD0018 1(2)LD0047 1(2)LD0048 1(2)NI0054A 1(2)NI0065B 1(2)NI0076A 1(2)NI0088B 1(2)NIO121A 1(2)NI0125 1(2)NI0129 1(2)NI0136B 1(2)NI0152B I(2)NV0001A 1(2)NVO002A Change Added closed stroke Added closed stroke Added closed stroke Added closed stroke Added closed stroke Added closed stroke Added closed stroke Added closed stroke Removed NW test Changed open function to supplemental program Changed open function to supplemental program Deleted closed stroke Removed NW test Changed closed function to Supplemental Program Changed closed function to Supplemental Program ADDITIONAL VALVE TESTING INCLUDED IN CATAWBA SUPPLEMENTAL TESTING System Valves CA 1(2)CAK360,1(2)CAK361,1 (2)CAK400,1(2)CAK401,1 (2)CAK440, 1(2)CAK441, 1 (2)CAK480,1(2)CAK481,1(2)CAK520,1(2)CAK521,1 (2)CAK560,1 (2)CAK561, 1(2)CAK600,1(2)CAK601,1(2)CAK640,1(2)CAK641 (these are all check valves and should be shown as 'CACK', however due to program limitations they are shown as 'CAK")

KC I(2)KC0313,1(2)KC0330.(2)KC0355,1(2)KC0361,1(2)KC0374,1(2)KC0380,1(2)KC0386, 1(2)KC0392,1(2)KC0404,1(2)KC0410,1(2)KC0814 NB 1(2)NV0331 NF 1(2)NF0895 NI 1(2)NI0125,1(2)NI0129,1(2)NI0481 NV 1 (2)NV0001 A, 1 (2)NV0002A RN 1 (2)RN0499,1(2)RN0807,1 (2)RN0815,1(2)RN0823,1 (2)RN0861,1(2)RN0863 WL 1(2)WL0462, l(2)WL0826,1(2)WLA033 Page 2 of 9 10/31/02

DETAILED DESCRIPTION OF CHANGES Catawba Nuclear Station Unit 1 and Unit 2 VALVES INCLUDED IN APPENDIX II CHECK VALVE CONDITION MONITORING PROGRAM All valves assigned Relief Request Number CN-GRV-04 1 (2)CA0008 1(2)NI0081 1 (2(CA0010 1(2)NI0082 1 (2)CA0012 1(2)NI0093 1(2)CA0173 1(2)NI0094 1(2)CA0291 1(2)NIO175 1(2)CA0292 1(2)NIO176 1(2)CF0031 1(2)NIO180 1(2)CF0040 1(2)NI0181 1(2)CF0049 1(2)NS0004 1(2)CF0055 1(2)NS0021 1(2)FW0028 1(2)NS0098 1(2)FW0056 1(2)NS0099 1(2)NI0059 1(2)NI0060 1(2)NI0070 1(2)NI0071 CHANGES TO THE PROGRAM DOCUMENT Added section 4.3.8 for Condition Monitoring Revised section 4.6 to add discussion of 10CFR50 Appendix J, Option B which has been adopted Revised Enclosure 9.10 - Valve Stroke Time Data Evaluation Flow Chart Revised Enclosure 9.13 - Cold Shutdown Valve Testing Priority list due to Condition Monitoring and valves moving to the Supplemental Program Page 3 of 9 10/31/02

DETAILED DESCRIPTION OF CHANGES Catawba Nuclear Station Unit 1 and Unit 2 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

1(2)CA0291 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

1(2)CA0292 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

Valve added to the Supplemental Test Program. NSMs CN-11391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

1(2)CAK361 Valve added to the Supplemental Test Program. NSMs CN-1 1391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

Valve added to the Supplemental Test Program. NSMs CN-1 1391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

Valve added to the Supplemental Test Program. NSMs CN-l 1391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

Valve added to the Supplemental Test Program. NSMs CN-I 1391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

1(2)CAK441 Valve added to the Supplemental Test Program. NSMs CN-1 1391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

Valve added to the Supplemental Test Program. NSMs CN-1 1391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

1(2)CAK481 Valve added to the Supplemental Test Program. NSMs CN-1 1391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

Valve added to the Supplemental Test Program. NSMs CN-11391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

Page 4 of 9 10/31/02 I(2)CA0008 1(2)CA0010 1(2)CA0012 1(2)CA0173 1(2)CAK360 1(2)CAK400 1(2)CAK401 1(2)CAK440 1(2)CAK480 I(2)CAK520

DETAILED DESCRIPTION OF CHANGES Catawba Nuclear Station Unit I and Unit 2 1 (2)CAK521 1(2)CAK560 Valve added to the Supplemental Test Program. NSMs CN-11391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

Valve added to the Supplemental Test Program. NSMs CN-1 1391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

1(2)CAK561 Valve added to the Supplemental Test Program. NSMs CN-11391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

1(2)CAK600 Valve added to the Supplemental Test Program. NSMs CN-11391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

1(2)CAK601 Valve added to the Supplemental Test Program. NSMs CN-1 1391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

I(2)CAK640 1(2)CAK641 Valve added to the Supplemental Test Program. NSMs CN-11391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

Valve added to the Supplemental Test Program. NSMs CN-11391 and CN-21391 added these check valves to prevent depressurization of accumulator upon loss of Instrument Air. These accumulators insure auxiliary feedwater control valves operation for Steam Generator Overfill event.

1(2)CF0031 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

1(2)CF0040 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

1(2)CF0049 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

1(2)CF0058 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

1(2)FW0028 1(2)FW0056 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

1(2)KC0313 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)KC0330 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)KC0355 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

Page 5 of 9 10/31/02

DETAILED DESCRIPTION OF CHANGES Catawba Nuclear Station Unit I and Unit 2 1(2)KC0361 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)KC0374 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)KC0380 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)KC0386 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)KC0392 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)KC0404 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)KC0814 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)LD0017 Revised the program to include the Open to Closed stroke. Operating Experience (OE) suggested these valves could affect Diesel Generator performance if not closed.

1(2)LD0018 Revised the program to include the Open to Closed stroke. Operating Experience (OE) suggested these valves could affect Diesel Generator performance if not closed.

1(2)LD0047 Revised the program to include the Open to Closed stroke. Operating Experience (OE) suggested these valves could affect Diesel Generator performance if not closed.

1(2)LD0048 Revised the program to include the Open to Closed stroke. Operating Experience (OE) suggested these valves could affect Diesel Generator performance if not closed.

1(2)NB0331 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)NF0895 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)NI0054A Added closed stroke per Minor Modification CNCE-70537.

1(2)NI0059 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

1(2)NI0060 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

l(2)NI0065B Added closed stroke per Minor Modification CNCE-70537.

1(2)NI0070 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

1(2)NI0071 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

I(2)NIO076A Added closed stroke per Minor Modification CNCE-70537.

Page 6 of 9 10/31/02

1(2)NI0081 1(2)NI0082 1(2)NI0088B 1(2)NI0093 1(2)NI0094 1(2)NIO121A 1(2)NI0125 1(2)NI0129 1(2)NIO136B 1(2)NIO152B 1(2)NI0175 1(2)NI0176 1(2)NI0180 1(2)NI0181 1(2)NI0481 1(2)NS0004 1 (2)NS0021 1(2)NS0098 1(2)NS0099 DETAILED DESCRIPTION OF CHANGES Catawba Nuclear Station Unit I and Unit 2 Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

Added closed stroke per Minor Modification CNCE-70537.

Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

Removed Containment Valve Injection (NW) water from this valve. Modifications CN-1 1385 and CN 21386 evaluated the removal and determined adequate sealing was provided by normal system pressure.

Revised test direction from Both to Open to Closed. Closed to Open function was moved to the Supplemental Program.

Revised test direction from Both to Closed to Open as identified by PIP C01-1043.

Removed Containment Valve Injection (NW) water from this valve. Modifications CN-1 1385 and CN 21386 evaluated the removal and determined adequate sealing was provided by normal system pressure.

Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

Revised to include Relief Request CN-GRV-04 for inclusion in the Check Valve Condition Monitoring Program.

Page 7 of 9 10/31/02

DETAILED DESCRIPTION OF CHANGES Catawba Nuclear Station Unit I and Unit 2 1(2)NV0001A Closed function moved to the Supplemental Program by modification CNCE-71172.

1(2)NVO002A Closed function moved to the Supplemental Program by modification CNCE-71172.

1(2)RN0499 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)RN0807 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)RN0815 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)RN0823 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)RN0861 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)RN0863 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

l(2)SM0001 Revised Test Alternative & Frequency to remove the partial stroke requirement. The Improved Tech Spec recommends against partial stroke testing due to the possibility of spurious closure.

1(2)SM0003 Revised Test Alternative & Frequency to remove the partial stroke requirement. The Improved Tech Spec recommends against partial stroke testing due to the possibility of spurious closure.

1(2)SM0005 Revised Test Alternative & Frequency to remove the partial stroke requirement. The Improved Tech Spec recommends against partial stroke testing due to the possibility of spurious closure.

1(2)SM0007 Revised Test Alternative & Frequency to remove the partial stroke requirement. The Improved Tech Spec recommends against partial stroke testing due to the possibility of spurious closure.

1(2)WL0462 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)WL0826 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

1(2)WLA033 Relief valve added to the supplemental testing program. Evaluation performed via calculation determined supplemental testing was appropriate for these valves.

Justification For Deferral CN-CA-03 has been revised to note the Condition Monitoring frequency for valves 1(2)CA0008, I(2)CA0010, 1(2)CA0012.

Justification For Deferral CN-CA-03 has been revised to note the Condition Monitoring frequency for valves 1(2)CA0173.

Justification For Deferral CN-CA-03 has been revised to note the Condition Monitoring frequency for valves 1(2)CA0291, 1 (2)CA0292.

Justification For Deferral CN-CF-02 has been revised to note the Condition Monitoring frequency for valves 1(2)CF003 1, 1(2)CF0040, 1(2)CF0049,1(2)CF0055.

Justification For Deferral CN-FW-01 has been revised to note the Condition Monitoring frequency for valves 1(2)FW0028, 1(2)FW0056.

Page 8 of 9 10/31/02

DETAILED DESCRIPTION OF CHANGES Catawba Nuclear Station Unit I and Unit 2 Justification For Deferral CN-NI-04 has been revised to note the Condition Monitoring frequency for valves 1(2)NI0060, 1(2)NI0071, 1(2)NI0082, 1(2)NI0094.

Justification For Deferral CN-NI-06 has been revised to note the Condition Monitoring frequency for valves 1(2)NI0059, 1(2)NI0070, 1(2)NI0081, 1(2)NI0093.

Justification For Deferral CN-NI-14 has been revised to note the Condition Monitoring frequency for valves 1(2)NI0175, 1(2)NIO 176, 1 (2)NIO0180, 1(2)NIO181.

Justification For Deferral CN-NI-25 was revised to delete the Open test for valves 1(2)NI0125 and 1(2)NI0129 which was moved to the Supplemental Program. The JFD number was reused for valves 1(2)NI0054A, 1(2)NI0065B, 1(2)NI0076A, and 1(2)NI0088B for documenting the Closed test for these valves which is performed during refueling.

Justification For Deferral CN-SM-01 has been revised to delete the partial stroke requirement. Improved Tech Spec (ITS) recommends against a partial stroke at power due to the potential for spurious closure.

Page 9 of 9 10/31/02

DUKE POWER CATAWBA NUCLEAR STATION ASME INSERVICE TESTING PROGRAM REVISION 26 October 2002 Prepared by:

Reviewed by:

Approved by:

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TABLE OF CONTENTS SECTION PAGES 1.0 Catawba Nuclear Station Program Document 1 - 38 2.0 Table of Abbreviations 1-3 3.0 PUMP INSERVICE TESTING PROGRAM 3.1 Pump Inservice Testing General Data - Unit I and Unit 2 1 - 8 4.0 VALVE INSERVICE TESTING PROGRAM 4.1 Valve Inservice Testing General Data - Unit I and Unit 2 Page Number Steam Generator Blowdown Recycle System BB 1 -7 Auxiliary Feedwater System CA 1-15 Feedwater System CF 1-8 Diesel Generator Fuel Oil System FD 1-2 Refueling Water System FW 1-5 Instrument Air Lock System IA 1-6 Component Cooling System KC 1-14 Diesel Generator Engine Cooling Water System KD 1 - 1 Spent Fuel Cooling System KF 1 -1 Diesel Gen. Lube Oil System LD 1-4 Radiation System MI 1-6 Boron Recycle System NB 1 -1 Reactor Coolant System NC 1-7 Residual Heat Removal System ND 1-7 Ice Condenser Refrigeration System NF 1-3 Safety Injection System NI 1 -37 Nuclear Sampling System NM 1-14 Containment Spray System NS 1-8 Chemical & Volume Control System NV 1-19 Containment Penetration Valve Injection Water System NW 1 -35 Fire Protection System RF 1-3 Nuclear Service Water System RN 1-13 Page 1 of 2 Rev. 26 10/31/02

TABLE OF CONTENTS 4.0 VALVE INSERVICE TESTING PROGRAM - Continued 4.1 Valve Inservice Testing General Data - Unit I and Unit 2 Main Steam To Aux Equipment SA 1-2 Main Steam System SM 1-4 Main Steam to Atmosphere System SV 1-9 Breathing Air System VB 1 -1 Diesel Generator Engine Starting Air System VG 1 - 12 Instrument Air System VI 1-4 Containment Purge Ventilation System VP 1-9 Containment Air Release & Addition System VQ 1 -2 Station Air System VS 1 -1 Cont. Air Ret. & Hydrogen Skimmer System VX 1 - 1 Cont. Hydrogen Sample & Purge System VY 1 -2 Decontamination System WE 1 -1 Liquid Waste Recycle System WL 1-7 Control Area Chilled Water System YC 1 -1 Makeup Demineralizer Water System YM 1 -1 5.0 RELIEF REQUEST PAGES 5.1 Pumps - Generic Relief Request I -I 5.2 Pumps - Specific Relief Request 1 - 1 5.3 Valves - Generic Relief Request I - 1 5.4 Valves - Specific Relief Request I - 1 6.0 JUSTIFICATION FOR DEFERRAL 6.1 Valves -Justification for Deferral I - 1 7.0 SUPPLEMENTAL TEST PROGRAM 7.1 Supplemental Test Program - Valves 1-12 8.0 CORRESPONDENCE Page 2 of 2 Rev. 26 10/31/02

CATAWBA NUCLEAR STATION ASME Section XI In-Service Testing Program Document October 31,2002 Revision 03 Prepared by:

Reviewed by:

Approved by:

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TABLE OF CONTENTS 1.0 Scope of Document 2.0 References 3.0 Definitions and Terms 4.0 Valve Program 4.1 Valve IST Program Scope 4.2 Exemption and Position Statements 4.3 Check Valve Testing 4.4 Relief Valve Testing 4.5 Thermal Expansion Check Valves 4.6 Leak Rate Testing 4.7 Remote Position Indication and Testing from Remote Locations 4.8 Post Maintenance and Modification Testing (Retest) 4.9 Fail-Safe Testing 4.10 Skid-Mounted Valves 4.11 Valve Test Acceptance Criteria 5.0 Pump Program 5.1 Pump IST Program Scope 5.2 Exemption and Position Statements 5.3 Mini-flow and Full Flow Testing 5.4 Vibration Monitoring 5.5 Post Maintenance and Modification Testing (Retest) 5.6 Skid-Mounted Pumps 5.7 Test Acceptance Criteria 6.0 Relief Request 6.1 Implementation of Relief Request 6.2 Interim Relief Request 7.0 Justification for Deferrals 7.1 Testing Deferral Justifications (Practicality Determinations) 8.0 Appendices Appendix A:

IST Program Responsibilities Appendix B:

Appendix B Supplemental Testing Program Appendix C:

Notification of Program Changes 9.0 Enclosures.1:

Revising the Program.2:

Program Bases Philosophy.3:

Valve Data Sheet.4:

Pump Data Sheet CNS ASME In-service Testing Program Rev. 03 Page 2 of 38 CNSSCOPE.DOC 10/31/02

.5:.6:.7:.8:.9:.10:.11:.12:.13:

Generic Relief Request Form Justification for Deferral Form Specific Relief Request Form System Piping Classification Correlation Summary of CNS IST Program Submittal Changes Valve IST Stroke Time Data Evaluation Flow Chart NC PORV Stroke Requirement Position Statement SA-1 & SA-4 Position Statement Cold Shutdown List CNS ASME In-service Testing Program Rev. 03 Page 3 of 38 CNSSCOPE.DOC 10/31/02

1.0 SCOPE OF DOCUMENT Technical Specification requires performance of pump and valve testing in accordance with ASME Section XI. Failure to meet the requirements of this program is a violation of Technical Specifications and 10CFR 50.55a.

The purpose of this program document is to specify the Catawba Nuclear Station (or hereafter referred to as "licensee" or "CNS") In-Service Testing Program for performing valve and pump testing. This document will also outline the process for additions, changes, and deletions of pumps and valves from the CNS IST Program.

1.1 Program Period:

Second Ten-Year Interval (120-month period beginning August 19, 1995);

Unit(s) 1 and 2 Concurrently 1.2 Applicable ASME Code(s) and Addenda:

ASME/ANSI OM-1 987 Edition; PART 6 including OMb-1989 ANSI/ASME OM-1-1987 ASME/ANSI OM-1987 Edition; PART 10 including OMa-1988 ASME OM Code - 1995 (OMa - 1996 Addenda); Subsections ISTC and Appendix II 1.3 Program Changes:

The NRC and the ANII will be notified of IST Program changes. However, component additions and deletions will be submitted and testing implemented or deleted without prior NRC approval.

In the instance where a component has been added to the IST Program, testing and the appropriate program changes will take place within 90 days of revising the program source documents unless determined to be impractical. If a hardship is identified, notification will be submitted to the NRC and an interim extension from testing implementation obtained.

The content of this program document is for non-mandatory compliance to recommendations stated in NUREG-1482 and is intended for the purpose of maintaining program continuity and documenting additional discussions and positions relative to code interpretations. Therefore, changes to this program document will not require prior NRC review and/or approval unless the licensee determines a need to do so.

CNS ASME In-service Testing Program Rev. 03 Page 4 of 38 CNSSCOPE.DOC 10/31/02

2.0 REFERENCES

The following documents were used as references in the development of this document:

Generic Letter 89-04 Generic Letter 89-10 10 CFR 50, Appendix B 10 CFR 50.55a ASME Section XI (1989)

ASME OM-6 (OMb-1 989), OM-10 (OMa-1 988), and OM-1 (1987)

Technical Specifications Final Safety Analysis Report (FSAR)

Nuclear System Directive: 408 Testing Reg. Guide 1.26 NRC Inspection Procedure 73756 Non-Mandatory

References:

NUREG/CP-0123, Proceedings of the NRC/ASME Symposiums on Pump and Valve Testing NUREG-1482, Guidelines for In-service Testing at Nuclear Power Plants, April 1995 ANSI OM-1, 1981 Req. for In-service Testing of Nuclear Power Plant Pressure Relief Devices.

OM-1 3, "Standard for Assessing the Operational Readiness for Power Operated Relief Valves."

OM-22, "Standard for Assessing the Operational Readiness for Check Valves."

ASME OMc Code - 1994 ASME OM Code - 1995 NRC Information Notice 97-90 NRC Information Notice 97-16 CNS ASME In-service Testing Program Rev. 03 Page 5 of 38 CNSSCOPE.DOC 10/31/02

3.0 DEFINITIONS and TERMS Generic Letter 89 the NRC letter providing additional requirements in testing MOVs to design basis conditions.

Generic Letter 89 the NRC letter providing supplemental guidance on developing and enhancing plant IST programs.

ASME Section XI -

the section of ASME Codes and Standards Manual that determines how to perform in service testing of light water reactor nuclear plant components.

ASME OM-10 Code -

the part of ASME Section XI codes dealing with the in-service testing of valves.

ASME OM-6 Code -

the part of ASME Section XI codes dealing with the in-service testing of pumps.

Frequencies -

the interval of time between in-service testing of the components. These intervals are defined in CNS Technical Specifications:

1)

Quarterly (3 months) - 115 days maximum

2)

Cold Shutdown (CSD) - Average Coolant Temperature (Tavg) <_ 200OF

3)

Refueling (RF) - Unit at shutdown for the purpose of replacing or rearranging all or a portion of the fuel assemblies or control rods.

IST Component -

components (valves and pumps) that are required to be tested per ASME Section XI.

Sections 4.1 and 5.1 of this document define the criteria to be included in the IST Program.

"=App. B Component" "UApp. J Component" Active Component Passive Component System Resistance Trending Set Point Leak Test Stroke-Time Limiting Stroke-Time Relief Requests Justif. For Deferrals -

components (valves and pumps) tested under of 10CFR50, Appendix B.

components leak tested for containment integrity under 10CFR50, Appendix J.

a component that must perform a mechanical motion during the course of accomplishing a system safety function.

a component that does not perform a mechanical motion during the course of accomplishing a system safety function.

the hydraulic resistance to flow in a system.

a comparison of current data to previous data obtained under similar conditions for the same equipment.

the value for which relief valves are set to relieve pressure.

testing of valves to verify seat leakage is limited to a specified maximum.

the time interval from valve actuation to the limit switch indication light at the end of the actuating cycle.

the maximum time allowed for a valve to stroke before becoming immediately inoperable.

A request submitted to the NRC requesting relief from the requirements of the Code for testing a particular component or a generic group of components.

A documented explanation of why a valve can only be tested at a cold shutdown or refueling outage frequency as opposed to quarterly.

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4.0 VALVE PROGRAM 4.1 In-Service Testing (IST) Program As required by 10CFR50.55a, valves that are classified in accordance of NRC Regulatory Guide 1.26 as ISI Class A, B, or C, which corresponds to ASME Class 1, 2, or 3 respectively, are included in the CNS IST Program. The following defines the criteria for inclusion of equipment in the IST Program:

a)

All Category A valves that fall within the Duke ISI Class A, B, or C boundaries.

b)

All Category B and C valves that fall within the Duke ISI Class A, B, or C boundaries and are active in the mitigation of the Design Basis Accidents (Design Basis Accidents are defined as those described in Chapter 15 of the FSAR).

c)

Valves in systems specifically required by Technical Specifications to be tested per ASME Section XI.

Valves' that are active in certain non-Design Basis Events, are cold shutdown valves not associated with an FSAR Chapter 15 event, are significant to plant safety, or are of economic importance that are beyond the scope of 10CFR50.55a. Such valves will be tested in the supplemental, 10CFR50 Appendix B Program, or the IST Program. See Appendix B of this document for a discussion of the 10CFR50 Appendix B Program.

The scope of the OM Standards and Code has not been expanded to include all safety-related pumps and valves in the IST Program.

Until the scope of 10CFR50.55a is changed, the scope of the IST Program will continue to be limited to only those components within the applicable ASME Code class1, 2, or 3 systems unless otherwise determined by the licensee (reference NUREG-1 482).

4.2 Valve Testing Program Exemptions and Position Statements Valves tested under jurisdiction of this program will be tested per requirements of OM-10 (OMa-1988), at the specified frequencies unless it has been determined to be impractical. This section of the program document provides CNS positions on interpretations, guidance, and other options regarding testing alternatives.

4.2.1 Category A and NC valves (containment and pressure isolation valves) will be leak tested in accordance with OM-i 0 section 4.2.2.

4.2.2 Valve stroke times will be recorded to at least the nearest second, except for valves, which have stroke times of less than one second. For these valves, a time of one second will be recorded.

Valves that stroke in less than 2 seconds may be exempted from reference ranges and the maximum limiting stroke time shall be 2 seconds as specified by OM-10 section 4.2.1.8 (e).

Additionally, documented stroke times will be to the nearest full second.

4.2.3 Stopwatches used to measure stroke times will be calibrated annually.

4.2.4 OM-10, section 6.3 (h) requires the signature of the person or persons responsible for conducting and analyzing the test. The dated initials of the person or persons responsible for conducting and analyzing the test may be used in place of a signature in the record of the tests.

4.2.5 It is the licensee's position that valve testing will be deferred if the normal code required test frequency or plant conditions would result in increased personnel risk or damage to plant equipment. Practicality of such deferral shall be determined by the licensee and documented in the "Justification for Deferral" section of the IST Program manual. In such cases, the licensee will not perform any type of destructive testing to determine the period of time at which damage to the equipment or risk to personnel would occur. Exercising valves on a cold shutdown or refueling outage frequency is not a deviation from the code (reference NUREG-1482, Section 2.4.5).

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4.2 Valve Testing Program Exemptions and Position Statements (continued)

NOTE: For cold shutdowns less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , valve testing does not have to be performed.

However, for cold shutdowns expected to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , valve testing will commence as soon as possible, but no later than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after reaching cold shutdown. Valve testing will proceed in a normal manner until all testing is complete or the plant is ready to return to power.

A completion of all valve testing is not a prerequisite to return to power.

Any testing not completed by the end of one cold shutdown will be performed during subsequent cold shutdowns, starting from the last test performed at the previous cold shutdown.

4.2.6 Manual valves that meet the scope requirements of OM-10 or are taken credit for in the safety analysis as capable of being repositioned to shut down the plant, to maintain the plant in a safe shutdown condition, or to mitigate the consequences of an accident will be included in the IST Program.

However, testing of such valves will be solely based on exercising requirements established by the licensee.

4.2.7 Valves that are not categorized as ISI Class A, B, or C need not be included in the IST Program.

However, according to GL 89-04, Position 11, "The intent of 10 CFR 50 Appendix A, GDC-1, and Appendix B, Criterion XI, is that all components, such as pumps and valves, necessary for safe operation are to be tested to demonstrate that they will perform satisfactorily in service."

The licensee reserves the right to include valves which do not meet these criteria in the IST Program. These valves are typically tested In the Supplemental Program. In such cases, the licensee will specify how the component is tested or if a deviation from the Code guidelines is allowable. CNS will not submit Relief Requests or Justification for Deferrals for "Non-Code" Class valves.

4.2.8 Thermal Relief Valves that meet the scope requirements of OM-1 0 or are taken credit for in the safety analysis for being capable of relieving pressure in code class 1, 2 and 3 piping systems by maintaining the plant in a safe shutdown condition, or in mitigating the consequences of an accident will be included in the IST Program. However, testing of such valves will be based on exercising frequencies established by the guidance given in OM PART 1, 1987 sections 1.3.3 and 1.3.4.

4.2.9 Containment Purge Valves (VPs), which are passive in the closed direction, will be leak tested per 10 CFR 50, Appendix J but not stroke-timed for IST purposes. Containment Purge valves are "passive" in Modes 1-4. During a postulated fuel handling accident inside the containment, no credit for containment isolation or mixing in the containment is taken. System design assures a safe release path from the containment with the VP system in operation. The radiological consequences of a postulated fuel handling accident are within the exposure guideline values of 10CFR 100.

4.2.10 Containment Hydrogen Purge Valves (VY), which are passive in the closed direction, will be leak tested per 10 CFR 50, Appendix J but not stroke-timed for IST purposes. These valves are "passive" in Modes 1-4.

CNS Technical Specifications requires exercising these valves.

However, power is removed and these valves are placed under administrative control as to not permit re-positioning after they have been leak-tested per Appendix J.

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4.3 Check Valve Testing Check valves tested under the jurisdiction of this program will be tested per Code requirements at the specified frequencies unless it has been determined to be impractical. This section of the program document is to provide the CNS positions concerning interpretations, guidance, and other options and testing alternatives for check valves.

4.3.1 For check valves in series where one of two valves is credited in the safety analysis, the verification that the pair of valves is capable of closing will be done on the basis of testing one of the check valves.

4.3.2 Category A and NC valves (containment and pressure isolation check valves) will be leak tested in accordance with OM-1 0 (OMa-1 988) section 4.2.2.

4.3.3 Full stroke testing of check valves will not necessarily constitute the obturator contacting the back-stop. Where possible, sufficient flow will be passed through the valve to verify design basis accident flow. If full flow is not possible, then the licensee will perform correlation testing, partial stroking, or other alternatives as provided by OM-10 section 4.3.3.3. Additionally, the code allows use of indirect evidence (such as system pressure, flow, temperature, or level) or other positive means to verify flow or pressure requirements. These indirect methods will not be subject to the range and accuracy requirements of the code. (ref. NUREG-1 482, section 4.1.2).

4.3.4 Check valve exercising to verify the closed position will not require demonstration that the valve was open prior to closure.

4.3.5 Seismic boundary check valves will be included in the program.

4.3.6 Check valves included in the Sample Disassembly portion of the IST Program will be disassembled and inspected under the provisions and guidelines given in GL 89-04 and per OM 10 (OMa-1 988), section 4.3.2.4 (c).

4.3.7 Where applicable to the CNS IST Program, back flow testing of check valves will be performed in accordance with GL 89-04 guidance. Examples of methods that may be used to verify valve closure are as follows:

Pump discharge check valves - verified closed by meeting a parallel pump's acceptance criteria while cross-connected; Appendix J testing;

"* Measure back flow through the valve using an open vent on the backside of the valve or ultrasonic flow measurement techniques;

"* Pressure drop across a pump;

"* Pump wind-milling;

"* Observation of external indication on valve stem.

4.3.8 As an alternative to the testing and/or examination requirements of OM-10, sections 4.2.1 and 4.3.2, the licensee has developed a check valve conditioning monitoring program in accordance with ASME OM 1995 (OMa-1996), Appendix II (Check Valve Condition Monitoring Program),

and the additional stipulations imposed in 10 CFR 50.55a. The licensee may implement this program on a valve or group of similar valves. A "Relief Request" has been submitted and approved and is included in the 'Valve - Generic Relief Request' section of the program manual.

Specific check valve testing requirements can be found at \\\\cnslf3\\mse-lib\\CM DATA\\Archive Database and opening Catawba CM Program Database in 2000.mdb and select 'Full Report'.

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4.3.9 The licensee recognizes the NRC's acceptance of non-intrusive techniques (N.I.T.) for testing check valves and will randomly apply N.I.T. to the check valve program. However, the industry's use of N.I.T. equipment is continuing to evolve and in many cases is not supplied from the vendor under the elements of the Q.A. program as with other types of test equipment utilized for testing safety related components (e.g. software qualifications, calculation validity, engineering correlation, etc).

Because of this, validation of such equipment is the responsibility of the licensee. Therefore, N.I.T. remains a voluntary option and will be evaluated on an individual application basis.

4.4 Relief Valve Testing Relief valves tested under the jurisdiction of this program will be tested per code requirements of OM-1, 1987, unless it has been determined to be impractical. This section of the program document is to provide the site's positions concerning interpretations, guidance, and testing alternatives for relief valves. Relief valves shall be considered for inclusion in the program if they provide overpressure protection for portions of systems that perform a specific function in shutting down a reactor or in mitigating the consequences of an accident.

4.4.1 Relief valves that are not credited for assisting in -mitigating the consequences of an accident and are only installed for over-pressure protection are considered passive.

4.4.2 Generic Relief Requests CN-GRV-01, CN-GRV-02, and CN-GRV-03 may not apply to all safety or relief valves. Actual valve testing requirements and/or test procedures should be reviewed to determine if these Relief Requests apply.

4.5 Thermal Expansion Check Valves A review of piping configurations inside containment, which could result in thermal expansion over pressurization, was conducted to insure protection had been provided, if necessary. Thermal expansion results when an incompressible fluid trapped between two closed valves inside containment is heated to post accident containment temperatures and expands. Pressure relief is required to prevent failure of the piping between the valves. Relief is accomplished by the slight movement in the open direction of an existing check valve or a check valve placed there for that purpose. Relief for containment penetrations is accomplished by the opening of the inside containment isolation check valve or a bypass check valve around a motor operated inside containment isolation valve. Containment penetrations equipped with Thermal Expansion Check Valves relieve this pressure back to containment.

The amount of opening required to relieve possible over pressurization is small enough such that there is not a credible failure of the check valve in the open direction, which would prevent this. These valves will not be tested in the open direction, unless there are other requirements to do so. All Thermal Expansion Check valves do have a safety function to open and therefore will be categorized as Active.

4.5.1 The following valves are designated as thermal expansion check valves, which protect containment penetrations. The open function on these valves may be tested, however this is not for thermal relief capability. These thermal expansion check valves are part of the containment penetration boundary and as such do receive Type C test and are listed in Table 6-77 of the UFSAR.

o 1 (2)FW0005 o

1 (2)KC0047, 1 (2)KC0279, 1(2)KC0340 o

1(2)NB0262 o

1(2)NC0057 o

1(2)NF0229, 1(2)NF0235 o

1(2)NI0471, 1(2)NI0485 o

1(2)NM0424, 1(2)NM0425 o

1(2)NV0090, 1(2)NV0874 o

1(2)RF0392, 1(2)RF0448 o

1 (2)RN0405, 1 (2)RN0438, 1(2)RN0485 o

1 (2)WL0321, 1 (2)WL0806, 1 (2)WL0868, 1 (2)WLA022 o

1(2)YM0121 CNS ASME In-service Testing Program Rev. 03 Page 10 of 38 CNSSCOPE.DOC 10/31/02

4.5.2 The following valves are designated as thermal expansion check valves and are listed in Table 6-77 of the UFSAR, however these valves are not Type C tested. These valves are classified as Pressure Isolation Valves (PIVs) and do have leakage requirements per Technical Specification.

The open function on these valves may be tested, however this is not for thermal relief capability.

o 1(2)NI124, 1(2)NI125, 1(2)NI128, 1(2)NI129, 1(2)NI156, 1(2)NI159, 1(2)NI165, 1(2)NI167, 1(2)NI169, 1(2)NI171, 1(2)NI175, 1(2)NI176, 1(2)NI180, 1(2)NI181 4.5 Thermal Expansion Check Valves - Continued 4.5.3 The following valves are designated as thermal expansion check valves and are listed in Table 6-77 of the UFSAR, however these valves are not Type C tested. The open function on these valves is tested by disassembly.

o 1 (2)NS0013, 1 (2)NS0016, 1 (2)NS0030, 1 (2)NS0033, 1 (2)NS0041, 1 (2)NS0046 4.5.4 The following valves are designated as thermal expansion check valves, however these valves are not Type C tested nor is the open function tested. There are no testable requirements, however these valves will be listed in Section 4.1 of this manual with a note to refer back to Section 4.5 for more information. These valves are listed in Table 6-77 of the UFSAR.

o 1 (2)BB0052, 1(2)BB0053, 1 (2)BB0054, 1 (2)BB0055 o

1 (2)KC0280, 1 (2)KC0322 o

1(2)NM0426, 1(2)NM0427, 1(2)NM0428, 1(2)NM0429 o

1 (2)NV0022, 1 (2)NV0046, 1 (2)NV0057, 1 (2)NV0068, 1(2)NV0079, 1 (2)NV00861 o

1 (2)NW0037, 1(2)NW001 07 4.5.5 The following valves are designated as thermal expansion check valves, however these valves are not Type C tested. These valves are classified as Pressure Isolation Valves (PIVs) and do have leakage requirements per Technical Specification.

The open function may be tested, however this is not for thermal relief capability. The valves are not listed in Table 6-77 of the UFSAR.

o 1(2)NI0060, 1(2)NI0071, 1(2)NI0082, 1(2)NI0094, 1(2)NIO126, 1(2)NIO134, 1(2)NIO157, 1 (2)NIO160 4.5.6 The following valves are designated as thermal expansion check valves, however these valves are not Type C tested nor is the open function tested. There are no testable requirements, however these valves will be listed in Section 4.1 of this manual with a note to refer back to Section 4.5 for more information. These valves are not listed in Table 6-77 of the UFSAR.

o 1(2)ND0116, 1(2)ND0117 o

1 (2)NV0033, 1 (2)NV0034, 1 (2)NV0049, 1 (2)NV0060, 1 (2)NVO071, 1 (2)NVO082, 1 (2)NV0492, 1 (2)NV0493, 1 (2)NV0494, 1 (2)NV0495, 1 (2)NV0878, 1 (2)NV0879, 1 (2)NVO880, 1 (2)NV0881 4.6 Leak Rate Testing All category A valves will be tested per OM-10, section 4.2.2, except those valves which function in the course of plant operation in a manner that demonstrates adequate seat leak-tightness need not be leakage tested. In such cases, proper administrative controls will be implemented and the valves leak tested during refueling outages.

4.6.1 Category A containment isolation valves shall be tested per 10CFR50, Appendix J. 10CFR50, Appendix J (Option B) has been adopted and allows testing interval extension beyond the nominal 30 months for those CIVs with acceptable performance. A frequency of RF (refueling)

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has been specified in Section 4.0 - Valve Inservice Testing Program for those valves which have an Appendix J leakrate test. The actual testing interval can be determined from the recently developed Leakrate Program. Refueling is the minimum testing interval for the bulk of the Appendix J valves, except for systems such as VP, VQ and VY.

Where a valve is identified as a containment isolation valve in the Technical Specification or FSAR and if it is determined to be an "active" valve with respect to this function, it will be exercised to the closed position when there is an associated requirement for leak testing.

4.7 Testing from Remote Location Section 4.1 of OM-10 requires valves with remote position indication to be tested at least once every 2 years to verify that the valve operation is accurately indicated. Valves that have remote operating switches and/or power supplies shall also be tested and verified for proper indication from the remote location. Other valve operating parameters (such as timing) may not be performed from the remote location during this testing.

4.8 Post Maintenance and Modification Testing (Retest)

(Reference Nuclear System Directive 408 Testing, Sections 408.9 and 408.10) 4.9 Fall-Safe Testing of Valves All Fail-Safe valves shall be tested in accordance with OM-10, section 4.2.1.6. Control valves are typically excluded from testing in the IST Program. However, if a control valve must change position to support a safety related function and it has a fail-safe position, then it will be included in the program and tested to verify the ability to perform that function with power and/or air removed (or simulated power and/or air removal).

4.10 Skid-Mounted Valves As recognized in 1995 ASME OM Codes (OMb-1997), skid mounted valves will be excluded form the scope of OM-10 test requirements provided they are adequately tested as part of the 'major' component. The licensee however, may opt to include certain components contained on these skids in the IST program for testing and trending purposes. In such cases, any program changes, exceptions, exemptions, or deferrals will not be submitted to the NRC for prior approval, but simply documented in the program plan.

4.11 Valve Test Acceptance Criteria All valve test acceptance criteria (IST-TAC) will be developed in accordance with the provisions specified in OM

10. The applicable acceptance criteria will be developed when the valve is known to be performing in a satisfactory manner. Where IST-TAC other than that required by code is established for a given valve (e.g.,

additional N.I.T. diagnostics), the documentation of that criteria will be at the discretion of the licensee and not required to be part of the test record. Trending of valve IST-TAC will be performed by the licensee on a periodic basis. Leakage criteria for valves (other than those tested in accordance to 10CFR50, Appendix J) will be determined based on leakage rates specified by the licensee or using the guidance specified in 4.2.2. Relief valve IST-TAC will be established per OM-1, 1987.

Such IST-TAC should not be confused with the acceptance criteria specified in DBDs, DBD associated TAC Sheets, Technical Specifications, or any FSAR. Such acceptance criteria are the most limiting values and can not be exceeded. IST-TAC are set to verify operational readiness of the valves and to identify valve degradation before the 'most limiting' acceptance criteria is exceeded. IST-TAC are based upon stroke times measured when the valve is know to be in good working order and are controlled within the test procedures. Alternately, DBD-TAC are specific criteria associated with a valve's design basis.

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4.11 Valve Test Acceptance Criteria (continued) 4.11.1 Valve Stroke-Time Acceptance Criteria:

The following cases present the options available for determining valve operability based on stroke time:

CASE 1 The valve strokes within its acceptable stroke time. The valve is considered operable.

CASE 2:

The valve does not move at all on the first try or exceeds the LIMITING VALUE. OM-10 immediately refers to this valve as being inoperable. An engineering evaluation needs to be done to determine the cause of the valve failure and system operability.

CASE 3:

The valve fails to meet the acceptance stroke time, but strokes in less than the LIMITING-VALUE.

Per OM-10, the valve shall be immediately stroked again to achieve an acceptable stroke time. Per the Catawba Valve Testing Program:

a.

If the valve successfully strokes on the second stroke, the valve is considered operable. The cause of the initial deviation shall be analyzed and the results documented in the test procedure. A third valve stroke may be performed to demonstrate consistent valve operation.

b.

If the valve does not fall within the acceptable range on the second stroke, then the valve will be analyzed within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months OR declared inoperable (if applicable).

An evaluation must be performed to determine the root cause of the failed test. The evaluation may determine that either corrective maintenance must be performed on the valve or the new stroke data is acceptable and new baselines must be established. Such results must be either documented in the test procedure or per the site Problem Identification Process (PIP).

c.

In the event the initial stroke and the second test results are inconsistent, but the engineering evaluation shows the new stoke time is acceptable, a third test may be performed to verify consistent behavior. Documentation of the third test will be optional if it shows no deviation from the second stroke.

4.11.2 Valve Stroke-Time Measurements and Methods:

Valve stroke-times are measured with a stopwatch to the nearest second. The stopwatch is started when the valve is actuated and it is stopped when an indication light is received indicating that the valve has completed its full stroke.

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4.11.3 Limiting-Value Stroke-Time Acceptance Criteria:

Limiting-Values for stroke-times will be established in accordance with guidance given in Generic Letter 89-04, Position 5. It is the position of the licensee that these values will be determined as follows (with the limitations of Tech. Specs. and Safety Analysis limits being the most limiting):

Valve Type Limitinq Value Calculation EMO (> 10secs.)

1.3R (to the nearest 0 or 5sec.)

EMO (_5 10secs.)

1.5R (to the nearest 0 or 5sec.)

POV (> 1Osecs.)

2.0R (to the nearest 0 or 5sec.)

POV (5 1 Osecs.)

2.25R (to the nearest 0 or 5sec.)

Note: Where 'R' represents the valve reference value at acceptable operation.

4.11.4 Engineering Evaluations: (Discussion to be completed for CNS in later revision)

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5.0 PUMP PROGRAM 5.1 In-Service Testing (iST) Program As required by 10CFR50.55a certain pumps that are classified in accordance of NRC Regulatory Guide 1.26 as ISI Class A, B, or C, which corresponds to ASME Class 1, 2, or 3 respectively are included in the IST Program. The following defines the criteria for inclusion of equipment in the IST Program:

a)

Pumps in systems specifically required by Technical Specifications to be tested per ASME Section XI.

b)

All pumps that fall within the Duke ISI Class A, B, or C boundaries that are provided with an emergency power source and are also active in mitigating the consequences of the Design Basis Accidents (Design Basis Accidents are defined as those described in FSAR Chapter 15).

Currently Catawba Nuclear Station is under the requirements of the ASME Code and Standards, OM PART 6, 1987 Edition, including OMb-1 989 (which is OMa-1 988 plus Errata Addenda to correct Table 3).

5.2 Pump Testing Program Exemptions and Position Statements Pumps tested under the jurisdiction of this program will be tested per code requirements of OM-6 at the specified frequencies unless it has been determined to be impractical.

The purpose of this section of the program document is to provide CNS positions on interpretations, guidance, and other options regarding testing alternatives.

5.2.1 Section 7.3 of the OM-6 code requires the signature of the person or persons responsible for conducting and analyzing the test. The dated initials of the person or persons responsible for conducting and analyzing the test may be used in place of a signature in the record of the tests.

5.2.2 Developed head acceptance (criteria and data) should be rounded to the nearest 0.5 psi, if possible. In most cases the suction gauges used will allow this type of accuracy.

5.2.3 Vibration acceptance (criteria and data) should be truncated to 2 decimal places for operability determinations. The full four-digit display number should still be recorded.

5.2.5 Pumps whose only safety function is predicated on plant shutdown and recovery from a fire per commitments made as a result of 10CFR50, Appendix R are not required to be included in the IST Program. The licensee will test these in accordance with Appendix R requirements.

5.2.6 Pumps that are not provided with an emergency source of power will not be required to meet IST requirements. The licensee however, may elect to include these pumps in the IST Program for testing purpose only.

5.2.7 Pumps, which can only be tested during plant operation, will be tested within 1 week following plant startup to comply with section 5.4 guidance.

If the testing schedule is not maintained during plant shutdowns, the affected pump(s) must be tested before entering an operational mode, which requires the pump(s) to be operable. The licensee however, may elect to delay repairs and/or retest of pumps not required to be operable for plant startup or other operational modes.

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5.3 Mini-flow and Full Flow Pump Testing (Discussion to be completed at a later date.)

5.4 Vibration Monitoring Pump vibrations monitored under the jurisdiction of this program will be performed per code requirements at the specified frequencies unless it has been determined to be impractical or a specific deviation from code is needed. This purpose of this section of the program document is to provide the site's positions concerning interpretations, guidance, and other options of vibration monitoring and analysis. Specific positions to certain sections to follow are currently being developed by the In Service Testing Working Group Team (ISTWG) and will be submitted in future revisions.

5.4.1 Pump drivers. (Discussion to be completed in future revision) 5.4.2 Smooth Running Pumps. (Discussion to be completed in future revision) 5.4.6 Vibration points for pumps. (Discussion to be completed in future revision) 5.5 Post Maintenance and Modification Testing (Retest)

(Reference Nuclear System Directive: 408 Testing, sections 408.9 and 408.10) 5.6 Skid-Mounted Pumps As recognized in 1995 ASME OM Codes (OMb-1997), skid mounted pumps will be excluded form the scope of OM-10 test requirements provided they are adequately tested as part of the 'major' component. The licensee however, may opt to include certain components contained on these skids in the IST program for testing and trending purposes.

In such cases, any program changes, exceptions, exemptions, or deferrals will not be submitted to the NRC for prior approval, but simply documented in the program plan.

5.7 Pump Test Acceptance Criteria All pump test acceptance criteria (IST-TAC) will be developed in accordance with the provisions specified in OM

6.

The applicable acceptance criteria will be developed when the pump is known to be performing in a satisfactory manner. Where IST-TAC other than that required by code is established for a given pump (i.e.,

pump curves), the documentation of that criteria will be at the discretion of the licensee and may not be part of the test record.

'IST-TAC' may not be the same acceptance criteria specified in DBDs, DBD associated TAC Sheets, Technical Specifications, or any FSAR. IST-TAC are set to verify operational readiness of the pumps and to identify pump degradation before the 'most limiting' acceptance criteria are exceeded. Pump IST-TAC will be evaluated to verify that other acceptance criteria specified (DBDs, DBD TAC sheets, Tech. Specs., or UFSAR) will not be exceeded.

5.7.1 Pump Hydraulic Acceptance Criteria: (Discussion to be included in future revision)

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6.0 Relief Requests The purpose of a Relief Request is to exclude components from testing requirements of the Code that cannot be followed. Therefore, if the testing on the component can not be performed due to plant configuration, plant safety, equipment limitations, type, or hazards to personnel, relief from the code will be requested.

Submitted relief requests will:

1) give an alternative method that ensures an acceptable level of quality and safety,

2) explain the hardship with meeting the code requirement,

3) provide a schedule or alternative test frequency (or duration for interim Relief Request).

At the end of each Ten Year Interval', all Relief Requests will be reviewed for next interval applicability. In cases where a 'Specific Relief' was previously submitted to the NRC and approval granted, but the conditions and provisions do not change (i.e. no code change or modification to equipment or system) to eliminate the relief, the relief will continue to be applicable the next interval. Relief Requests will not be written for any non-Code Class components that are included in the IST Program at the licensee's discretion..

6.1 Implementing Relief Requests:

When a Relief Request is submitted for those requirements which have been determined to be clearly impractical, the licensee reserves the right to implement the proposed alternative testing while the NRC is reviewing the Relief Request, providing the licensee has assured the alternative does not compromise the level of safety provided by the code testing requirement. This position is referenced from NUREG-1 482, section 2.5.

6.2 Interim Relief Requests:

When a Relief Request is required on an interim basis, the licensee will submit the relief for review, but as with section 6.1, may implement the relief while the NRC is reviewing the request. Updates to schedules or impacts to modification implementation of the component with interim relief will be communicated to the NRC as the program is updated. Interim Relief Requests shall be withdrawn when the licensee no longer requires them.

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7.0 Justifications for Deferrals:

Justification for Deferrals (JFDs) will be written when a component can not be tested at the specified frequency.

This could be due to an impracticality of testing the component at power or due to plant safety concerns introduced by the testing configuration. The basis for determining the impracticality of testing at power and expanding the component's testing frequency to a Cold Shutdown or Refueling Outage frequency is documented in the Justification for Deferral.

In-Service Testing to be performed at Cold Shutdown shall:

a) be performed during each cold shutdown when the planned length is of sufficient duration to establish the necessary test conditions and to perform the test, and b) be performed as to not impact the timely completion of the shutdown related activities and subsequent return to operation. For outages when the planned length is not of sufficient duration to complete all tests, testing will start within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of reaching cold shutdown conditions. This is supported by the position stated in OM-10, section 4.3.2.2, OMa-1 988 Addenda.

c) be performed at the next available cold shutdown consistent with the above criteria if an opportunity to test the valve is not available (Completion of the IST is not a prerequisite to return to operation).

Any testing required to be performed during a refueling outage shall be completed prior to plant operation.

Components tested during start-up will not delay start-up if the site Technical Specifications allow start-up with the component out of service or inoperable.

Retest and corrective actions shall be performed at the first available opportunity.

7.1 Testing Deferral Justifications:

7.1.1 Purpose

The purpose of the testing Justification for Deferral form is to document the reason that a pump or valve can only be tested at cold shutdown or at refueling outage.

Valid reasons could be plant configuration for testing which would jeopardize the safety of plant operation, access to the component which would be against ALARA, access to the component due to the environmental conditions endangering personnel safety, or that plant configuration for testing would require the plant to be in a mode not suitable for power production. Removing one train for testing or entering a Limiting Condition of Operation (LCO) is not sufficient basis for not performing the required tests, unless the testing renders systems inoperable for extended periods of time. It is not the intent of IST to cause unwarranted plant shutdowns or to unnecessarily challenge other safety systems. Other factors such as the effect on plant safety and the difficulty of the test should be considered. As stated earlier, testing should not interfere with power production.

Note:

The Justification of Deferral Form is found in Enclosure 9.6.

CNS ASME In-service Testing Program Rev.03 Page 18 of 38 CNSSCOPE.DOC 10/31/02

8.0 APPENDICES Appendix A: IST PROGRAM Responsibilities 1.0 Site IST Engineer:

The IST Engineer position will be filled by a qualified individual knowledgeable of plant system operation. He/she ensures the site is in compliance by its performance testing and trending methods. The IST Engineer will accomplish this by maintaining consistency among the System Engineers and overall program management.

The IST Engineer may publish an overall summary (as an annual summary), on the current status of the site performance monitoring of the valves and pumps tested under the requirements of the IST or 10CFR50, Appendix B Program.

The IST Engineer will be responsible for notifying Regulatory Compliance of any changes to the Valve and Pump Testing Program described in this document, including changes to the data sheet information.

The IST Engineer will be responsible for updating and maintaining the IST Database.

The IST Engineer will be responsible for coordinating and implementing the program update and renewal per 10CFR50 every 10 years.

2.0 GO IST Coordinator:

The General Office (GO) IST Coordinator will be an individual responsible for overall corporate IST Program management. He/she ensures Duke Powers corporate strategies for the IST Program align with industry and regulatory standards. This individual is knowledgeable of each site's IST programs including program administration and will be responsible for ensuring each site is in compliance with the applicable ASME Codes and IST guidelines (OM-6, OM-10, GL 89-04, NUREG-1482 etc.).

The GO IST Coordinator will be the technical consultant on any Code-related issues that require interpretation or involve Operability determinations (at the discretion of the IST Engineer and site management). The GO IST Coordinator will provide support for internal and external IST Program audits.

The GO IST Coordinator will be the Single Point of Contact on any issues that involve site-site interaction. The GO IST Coordinator will be responsible for ensuring consistency where practical.

The GO IST Coordinator will represent Duke Powers interest for Code development.

The GO IST Coordinator will be responsible for assisting with review and updating the IST Program per 10CFR50 each 10 year interval. He/she will also assist the sites in preparing, submitting, and reviewing interim revisions to the IST Program. Also, the IST Coordinator will assist the site IST Engineer in developing position statements, Relief Requests, and Justification for Deferrals.

He/she will also perform periodic reviews of site Relief Requests and/or Justification for Deferrals for consistency and compliance.

CNS ASME In-service Testing Program Rev. 03 Page 19 of 38 CNSSCOPE.DOC 10/31/02

Appendix A: IST PROGRAM Responsibilities (Continued) 2.0 GO IST Coordinator (continued):

The GO IST Coordinator will see that progress addressing technical issues will be made by the IST Working Group (ISTWG).

This includes defining appropriate tasks, tracking action items, conducting periodic meetings, interface with the appropriate BEST contacts, and maintaining overall group focus.

3.0 Mechanical Systems and Equipment Engineering (MSE)

MSE Systems is responsible for the following:

"* ensuring the accuracy of IST dataset information,

"* defining test acceptance criteria (TAC),

"* ensuring code testing requirements-are met,

"* documenting reasons for scope or code deviation,

"* providing tech. assistance for developing test procedures,

"* complete valve and pump data sheets for program revisions MSE Equipment is responsible for the following:

"* Notifying the IST Engineer of maintenance that could affect the baseline data for any IST component,

"* Overall administration of the relief valve testing program (OM-1),

"* Administrating the check valve sample disassembly program,

"* Provide input when evaluating specific component issues (why failed test, baseline changed, etc.,)

Each Mechanical System Engineer is responsible for the components within their systems, which are in the program. If the status of component changes, the MSE is responsible for initiating the required changes to the program (see Appendix C).

4.0 Civil/Electrical and Nuclear Engineering (CEN)

CEN is responsible for the following:

"* notifying the IST Engineer of maintenance that could affect the baseline data for any IST component,

"* provide input when evaluating specific component issues (why failed test, baseline changed, etc.,)

5.0 Operations Performance Test Group (OTG)

This group is responsible for the following:

"* input data into procedure and IST database,

"* performing tests,

"* accurately recording and notifying MSE of any testing problems,

"* initiating a PIP when a test is failed or a problem is encountered,

"* documenting test discrepancies on the procedure.

6.0 Operations Procedure Group This group is responsible for the following:

"* updating and maintaining all IST procedures,

"* verifying all technical changes with the IST Engineer.

CNS ASME In-service Testing Program Rev. 03 Page 20 of 38 CNSSCOPE.DOC 10/31/02

10CFR50, Appendix B Program (Supplemental Testing Program)

The scope of the Catawba Pump and Valve Testing Program includes:

(1) all components that are active in mitigating the consequences of Design and non-Design Basis Events, or required for cold shutdown, (2) provide a containment isolation function, (3) or are designated by station Technical Specifications to be included in testing programs.

This scope is further divided into IST testing and 10CFR50, Appendix B testing. (Reference Duke Power Company's Oconee Nuclear Station's 11/1/90 Generic Letter 89-04 response - M. S.

Tuckman to NRC)

Selected components tested under guidelines of 10CFR50, Appendix B portion of the Catawba Pump and Valve testing program provide a function important to the safety of nuclear power plant operation, but are not explicitly under the scope of ASME OM Codes and Standards or considered beyond the scope of 1 OCFR50.55a. Specifically, the 1 OCFR50, Appendix B Program includes:

(1) pumps and valves not included in the IST Program, which are active in certain non Design Basis Events, (2) are cold shutdown valves not associated with a FSAR Chapter 15 event, (3) are significant to plant safety, (4) or are of economic importance.

The CNS 10CFR50, Appendix B Program will be administered using the ASME IST Code as guidance for testing and trending.

The acceptance criteria and testing intervals used to test Appendix B components should be specified by the IST Engineer. Relief Requests and Justification for Deferrals will not be submitted for Appendix B components. If the requirements of the ASME Code cannot be followed for components in the Appendix B Program, deviations from Code

'guidelines' will be documented in the section "SUPPLEMENTAL PROGRAM POSITIONS."

The 10CFR50, Appendix B components will be tested using approved Duke Power "A" procedures and requirements of 10CFR50, Appendix B. Deviations from standard test practices will be allowed only if substantiated in writing per the methods outlined in this document.

APPENDIX B: SUPPLEMENTAL PROGRAM POSITIONS:

B.1 Per Catawba's GL 89-04 response, 10 CFR 50, Appendix B manual valves are only stroked at a refueling frequency.

CNS ASME In-service Testing Program Rev. 03 Page 21 of 38 CNSSCOPE.DOC 10/31/02 Appendix 13:

Appendix C: Notification of Program Changes The System Engineer shall initiate program changes as changes are made to the respective system, DBDs, or active/passive valve calculations. Notification of external customers (e.g. Regulatory Compliance Group) of such changes to the program will occur by issuing the appropriate administrative mechanism (i.e. PIP, Minor Modification Request, etc.).

To ensure Code compliance for the CNS Pump and Valve Testing Program, the IST Engineer should be notified of any of the following changes:

"* changing the active/passive status of a component,

"* changing the leakage requirements of the component,

"* changing the piping classification of the component (Duke Class and ISI Class),

"* something changes with how the component may be tested,

"* a commitment is made or changed for testing or operation of a component,

"* taking credit for a new function, flow path, etc.,

"* a modification to the component is planned which can/will significantly affect the components baseline Test Acceptance Criteria (TAC).

CNS ASME In-service Testing Program Rev. 03 Page 22 of 38 CNSSCOPE.DOC 10/31/02

9.0 ENCLOSURES

.1 - REVISING THE PROGRAM

1.

Process for Revisinq the IST Program Mechanical Systems Engineering Management Procedure MSE 1.16, "Administration and Control of the Catawba Inservice Testing Program", defines the process to be followed when changes to the IST Program should be made, how changes to the IST Program are made, and when changes should be forwarded for NRC review.

2.

Inclusion of Flow Diagrams (reference NUREG-1 482, Section 2.4.3)

The staff recommends that flow diagrams be included in the program submittal to assist in finding the pumps and valves included in the program.- This information will assist the staff in reviewing relief requests or proposed alternatives.

A partial submittal of the program containing relief requests should include applicable drawings to support the relief requests or to supersede previous IST flow diagrams.

IST flow diagrams need not be updated regularly, but if drawings change because of modifications, or if relief requests are affected, the staff recommends drawings be revised and submitted to the NRC in the next periodic submittal of revisions to the IST Program. The staff also recommends licensees include applicable drawings with relief requests that are very detailed and are submitted to supplement the IST Program.

CNS ASME In-service Testing Program Rev. 03 Page 23 of 38 CNSSCOPE.DOC 10/31/02

.2 (RESERVED FOR "PROGRAM BASES PHILOSOPHLY')

CNS ASME In-service Testing Program Rev. 03 Page 24 of 38 CNSSCOPE.DOC 10/31/02

.3 Valve Data Sheet Deletion Reason for change Valve Number Description Valve Type BA BF CK DI EX GB GT PG PR RV SC ST SV VB Valve Size Actuator Type AO HO MA ML MO MR PA SA SO Flow Diagram Coordinate System Engineer PROFS ID Containment Isolation Valve Yes No Active Valve Yes No Auxiliary Safe Guard Valve Yes No Vent/Drain Yes No Valve Category ASME Class Required Accident Position Cold Shutdown Position Alternate Feedwater Path DBD Time OPEN TS Time OPEN FSAR Time OPEN Valve Test Type Test Direction Test Frequency Test Procedure A

B A

B Open Open Yes No C

C Closed Closed Generic Letter 89-10 Valve ESF Valve Skid Mounted Valve D

(See OM-10 section 1.4)

N (non code class)

Throttled Throttled DBD Time CLOSED TS Time CLOSED FSAR Time CLOSED FS PS ST U

OC CO BOTH a

CSD RF LT CNS ASME In-service Testing Program Rev. 03 Page 25 of 38 CNSSCOPE.DOC 10/31/02 Revision Addition Yes No Yes No Yes No

.4 Pump Data Sheet Pump(s):

Revision Addition Reason for Change Deletion Pump Information ISl Class Duke Class Pump Manufacturer Pump Type Pump BEP (Design Pt.)

Driver Manufacturer Driver Size OFD ES Actuation Channels Procedure No(s).:

Accident Pump Flow Delta P Required Full Flow Requirement TAC Sheets Procedure No(s):

Test frequency A

B C

A B

C D

F G

)gpm psi Coor.

1 2

3 4

5 6

a CSD RF CNS ASME In-service Testing Program Rev. 03 Page 26 of 38 CNSSCOPE.DOC 10/31/02

.5 Catawba Units I and 2 Generic Relief Request Item Number:

Component Number (s):

Flow Diagram (s):

Function (s):

ISI Class/Duke Class:

Code Category:

Test Requirement (s):

Basis for Relief:

Code Alternative:

CNS ASME In-service Testing Program Rev. 03 Page 27 of 38 CNSSCOPE.DOC 10/31/02

.6 Catawba Units 1 and 2 Justification for Deferral Item Number:

Component Number (s):

Flow Diagram (s):

Code Category.

ASME Class:

Function (s):

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

CNS ASME In-service Testing Program Rev. 03 Page 28 of 38 CNSSCOPE.DOC 10/31/02

.7 Catawba Units I and 2 Specific Relief Request Item Number:

Component Number (s):

Flow Diagram (s):

Function:

ASME Class:

Code Category:

Test Requirement:

Basis for Relief:

Alternate Testing:

CNS ASME In-service Testing Program Rev. 03 Page 29 of 38 CNSSCOPE.DOC 10/31/02

.8 System Piping Classification Correlation (1)

Safety Related YES YES YES NRC Quality Group A

B C

NO D(3)

ANSI Duke QA Safety Condition Class 1

1 1

Code Des. Criteria (6) 1 Class 1, ASME Sect. III 2

Class 2, ASME Sect. III 3

Class 3, ASME Sect. III 2(4)

NNS(2)

ANSI B31.1.0 No D

4 NNS(2)

ANSI B31.1.0 NO H

NO H (HVAC)

YES

-(4)

-(6)

ANSI B31.1.0 Duke Power Spec.

Duke Power Spec Seismic Pressure Boundary Intearity Normally Contains Seismic Radioactiv Cateaorv e Material YES SC-I YES SC-I YES SC-I NO N/A YES SC-I1(7)

NO N/A NO N/A YES SC-I (1)

Safety Related as used herein is in accordance with 10CFR50 Appendix A General Design Criteria for Nuclear Power Plants and is applicable to function only; i.e., structures, systems, and components required to function such that the facility can be operated without undue risk to the health and safety of the public are safety related.

(2)

NNS = Non-Nuclear Safety (3)

Class E piping is equivalent to NRC Quality Group D; i.e., the system is designed to normally carry a radioactive fluid; however, is considered NNS as a component failure would not result in a calculated potential exposure in excess of the limits established by 10 CFR PART 20.

(4)

Class E, G, and H piping systems may also be assigned QA Condition 3 and/or 4 to denote additional requirements for fire protection of safety related components and/ or seismic structural integrity (except pressure boundary) to preclude adverse interactions with safety related structures, systems and components, respectively; refer to Duke Nuclear Guide 1.29.

(5)

Code and Standards Applicability: Duke Power Company establishes an "effective code date" in accordance with 10CFR50, par. 50.55a for Catawba Nuclear Station. Due to the numerous code and standards references applicable to each station, no attempt is made to specifically identify these references as they are amended, superseded, or substituted. Duke reviews and complies with all or portions of the latest versions of the above Codes and Standards unless materials and/ or design commitments have progressed to a stage that it is not practical to make a change.

When only portions of addenda to Codes and Standards are utilized, the appropriate engineering review of the entire agenda assures that the overall intent of the Code Standard is still maintained.

(6)

HVAC Duct Systems may be constructed of either sheet metal or piping materials depending upon the design function and requirements.

Non-Safety Related HVAC may be assigned QA Condition 4. SC-It Support Restraints to preclude adverse interactions with safety related structures, systems, and components. Refer to Duke Nuclear Guide 1.29.

(7)

Class F for piping systems is used when pressure boundary protection is required.

Seismic Category II hangers may be use on Class E, G, or H piping systems when pressure boundary integrity is not required. See Duke Guide 1.29.

CNS ASME In-service Testing Program Rev. 03 Page 30 of 38 CNSSCOPE.DOC 10/31/02 Duke System Piping Classification A

B C

E F

G YES YES YES YES NO NO NO NO NOTES:

.9 Summary of IST Program Submittal Changes (Will be composed and distributed to all recipients of changes/revisions).

CNS ASME In-service Testing Program Rev. 03 Page 31 of 38 CNSSCOPE.DOC 10/31/02

.10 VALVE STROKE TIME DATA EVALUATION FLOW CHART CNS ASME In-service Testing Program Rev. 03 Page 32 of 38 CNSSCOPE.DOC 10/31/02

LTOP (Tcold <

285 F)

After 4 1/2 sq In vent path established (preferred)

Cb Cooldown/Shutdown

-V NOTE: PORVs ai condition. Valve, N2 stroke required (TS 3.4.9.3, [ITS 3.4.12],

3.4.4[ITS 3.4.11])

VI stroke (optional) - can be used to satisfy cold shutdown stroke if no maintenance is scheduled (see JFD CN-NC-02)

(TS 3.4.4,ITS 3.4.11])

MODE 2 MODE 3 or 4 MODE 5 NC temp > 200 F Prior to loss of 4 1/2 sq in vent path VI cold shutdown stroke required if not performed prior to mode 4 down; (can be deferred to startup if maintenance is scheduled, see JFD CN-NC-02).11 NC PORV Stroke Requirement Position Statement VI stroke - required if maintenance was done or if TSS 4.4.4.1 [ITS 3.4.11.2] was not performed with NC> 200 F during plant shutdown (Note - can satisfy cold shutdown stroke)

Prefer to do VI stroke after LTOP is exited - Tcold > 285 F

'A VI cold shutdown stroke (allowed but not preferred)

N2 stroke - required if maintenance was performed (TS 3.4.9.3[ITS 3.4.12])

VI stroke cold shutdown required if not performed during shutdown (see JFD CN-NC

02) - can satisfy post maintenance test requirement, required if maintenance was performed (can be deferred to modes 3 or 4)

(TS 3.4.4[ITS 3.4.11], TS 3.4.11[UFSAR Chap 16])

m 0

t

(_0 Heatup/Startup re Cold Shutdown valves and are required to be tested EACH time the plant is in the Cold Shutdown

, can be exempted from cold shutdown testing if testing was performed within the previous 92 days.

-1

.12 CATAWBA NUCLEAR STATION MECHANICAL SYSTEMS ENGINEERING SA-1 & SA-4 POSITION STATEMENT

Subject:

SA-1 & SA-4 Exclusion from the Inservice Testing Program

Purpose:

The purpose of this letter is to document Engineering's position for not including valves SA-1 & SA-4 in the IST Program.

Position Statement:

Valves SA-1 (Main Steam B to CAPT Maintenance Isolation) and SA-4 (Main Steam C to CAPT Maintenance Isolation) are manual gate valves located in the Interior Doghouse immediately downstream of the respective SM piping.

SA-1 and SA-4 are currently listed in Catawba Technical Specification, as Containment Isolation Valves.

The valves are locked open and capable of local manual operation only. These valves are required to be open to supply steam to the CAPT from the respective SM piping for Engineered Safety Features (ESF) operation of the CAPT. However, CAPT operation can continue with one of these valves closed providing that steam is available from the opposite SM piping.

T/S 3.6.3 and Table 3.6-2 are applicable to valves that are required to close on an ESF signal to ensure penetrations passing through containment are isolated during an accident.

Those systems and penetrations essential for reactor core protection are not automatically isolated during such events. SA-1 and SA-4 are listed as Containment Isolation Valves in T/S 3.6.3 Table 3.6-2, but are not closed on an ESF signal.

Valves SA-3 (S/G B Main Steam to CAPT Stop Check) and SA-6 (S/G C Main Steam to CAPT Stop Check) are stop check valves located in the Aux. Building Elevation 543' Mechanical Penetration Room, downstream (CAPT side) of valves SA-1 and SA-4 respectively, before the SA piping joins together to supply the CAPT. The piping and supports for SA-3 and SA-6 are procured and maintained within the constraints of ASME Class II (Duke Class B) standards; and are therefore, of acceptable construction to extend the penetration beyond the identified Containment Isolation Valves (SA-1 and SA-4). These valves are required to be open for CAPT operation when supplying steam to the CAPT from the respective SM piping. However, CAPT operation can continue with one of these valves closed provided steam is available from the opposite SM piping.

Catawba FSAR Table 6.2.4.1, Containment Isolation System Design Basis (10CFR50, Appendix A, Criterion 57, Closed System Isolation Valves) originally listed valves SA-1 and SA-4 as Containment Isolation Valves. However, these valves have since been replaced in the FSAR table by valves SA-3 and SA-6, following a Design Study performed as a result of PIP 1-C-90 0008. The Design Study concluded that these valves and associated piping are of a sufficient design and construction for use as Containment Isolation Valves (as discussed previously) due to accessibility concerns with SA-1 and SA-4 for certain scenarios requiring the isolation of one steam supply to the CAPT. For the Main Steam Line break, environmental conditions in the Doghouse may prevent Operator access to these valves.

CNS ASME In-service Testing Program Rev. 03 Page 34 of 38 CNSSCOPE.DOC 10/31/02

.12 (continued)

CATAWBA NUCLEAR STATION MECHANICAL SYSTEMS ENGINEERING SA-1 & SA-4 POSITION STATEMENT The following two accident scenarios require the isolation of one steam supply to the CAPT due to current dose assessment limitations and CA System operation requirements:

1)

Steam Generator Tube Rupture (SGTR) and

2)

Main Steam Line Break.

The dose calculations for Main Steam Line Break and SGTR scenarios assume limited release of main steam to the atmosphere. Operator action is taken as directed within current Emergency Operating Procedures (EP's) and/or Abnormal Operating Procedures (AP's) to manually close SA-3 and/or SA-6 as applicable in these scenarios.

These valves are used in the EP's and AP's as opposed to SA-1 and SA-4 due to more assured accessibility as discussed previously - SA-1 and SA-4 are located in the Interior Doghouse and would not be accessible in the event of a high energy line break (i.e. Main Steam Line Break) in this Doghouse.

However, SA-1 and SA-4 are the closest isolation valves to containment.

If accessible, SA-1 and SA-4 can also be closed in a shorter time frame than SA-3 and SA-6.

During a SGTR, the time required to manually close stop check valves SA-3 and SA-6 may increase due to "dress-out" requirements and increased radiation monitoring prior to entering the area due to contamination and increased dose in the mechanical penetration room.

Therefore, if accessible, closing SA-1 and SA-4 would be preferable over SA-3 and SA

6. In each of these accident scenarios, the time required for an Operator to close the applicable valve has been estimated and factored into the Accident Analyses and resultant dose calculations. Calculated off-site doses are within allowable values for these scenarios.

For the SGTR scenario, failure to isolate steam to the CAPT from the S/G with the tube rupture would allow indefinite release of main steam to the atmosphere via the CAPT exhaust, which would consequently exceed the current dose calculations.

Assuming no high energy line break in the Interior Doghouse during a SGTR accident, closing SA-1 and SA-4 would be preferable over SA-3 and SA-6. For the Main Steam Line Break scenario, SA-3 or SA-6 (depending on the break scenario) would automatically close (stop check valves) to prevent the diversion of steam from an intact steam line to the faulted piping and then to the atmosphere or into containment (depending on the location of the break) effectively depressurizing a second S/G, rendering the CAPT inoperable due to the loss of all steam supply, and also affecting the operation / flow balance of the Motor Driven CA pumps.

The applicable SA line is isolated as a precaution in case of the check valve fails to close and isolate the faulted steam line. Unless the steam line break is located in the Interior Doghouse, closing SA-1 and SA-4 would be preferable over SA-3 and SA-6.

CNS ASME In-service Testing Program Rev. 03 Page 35 of 38 CNSSCOPE.DOC 10/31/02

.12 (continued)

CATAWBA NUCLEAR STATION MECHANICAL SYSTEMS ENGINEERING SA-1 & SA-4 POSITION STATEMENT As a result of a Containment Integrity Review concluded in January of 1996, SA-1 and SA-4 were identified as the preferred valves for containment isolation purposes.

FSAR Table 6-77 was revised to list SA-1 and SA-4 as the Containment Isolation Valves for penetrations M261 and M363. T/S Table 3.6-2 listed SA-1 and SA-4 as Containment Isolation Valves and did not require revision. Applicable Operations EP's and AP's would be revised to use SA-1 and SA-4 as the first response with the option for using SA-3 and SA-6.

This recommendation recognizes the design acceptability of closing SA-3 and SA-6, if attempts to close SA-1 and SA-4 are unsuccessful.

Section X of the Containment Integrity Review can be consulted if further information is required concerning these recommendations.

CNS ASME In-service Testing Program Rev. 03 Page 36 of 38 CNSSCOPE.DOC 10/31(02

.13 CATAWBA NUCLEAR STATION MECHANICAL SYSTEMS ENGINEERING Priority for Cold Shutdown Valve Testing During Unplanned Entry into Mode 5 The following table provides guidance relative to the order in which cold shutdown testing should occur. The order, or priority, is based on possible system conditions during Mode 5, placing of jumpers and sliding of links, etc. Valves should be tested in the order listed (if possible) so that the valves tested in the unit's preceding cold shutdown will be the last ones tested during the unit's next cold shutdown. Should a valve be unavailable for testing and subsequently passed over during any given forced entry into Mode 5, that valve should be one of the first tested during the unit's cold shutdown outage. Following a refueling outage, the testing sequence re-starts at item one.

Valve Valve Valve Valve 1

1(2)NCO032B 25 1(2)ND0002A 49 1(2)NV0188A 73 1(2)CF0048 2

1(2)NCO034A 26 1(2)ND0036B 50 1(2)NV0189B 74 1(2)CF0055 3

1(2)NCO036B 27 1(2)ND0037A 51 1(2)NVO202B 75 1(2)CF0057 4

1(2)NIO100B 28 1(2)NI0173A 52 1(2)NVO203A 76 1(2)NVO089A 5

1(2)NIO103A 29 1(2)NI0178B 53 1(2)NVO312A 77 1(2)NVO091B 6

1(2)NI0144A 30 1(2)NV0252A 54 1(2)NV0314B 78 1(2)KC0338B 7

1(2)NI0147B 31 1(2)NV0253B 55 1(2)NVO010A 79 1(2)KC0424B 8

1(2)NI0162A 32 1(2)SM0001 56 1(2)NVO011A 80 1(2)KC0425A 9

1(2)NIO121A 33 1(2)SM0003 57 1(2)NVO013A 81 1(2)RN0437B 10 1(2)NI0152B 34 1(2)SM0005 58 1(2)VI0077B 82 1(2)RN0484A 11 1(2)NI0332A 35 1(2)SM0007 59 1(2)ND0010 83 1(2)RN0487B 12 1(2)NI0333B 36 2CA0149 60 1(2)ND0044 84 13 1(2)NI0334B 37 2CA0150 61 1(2)NI0342*

85 14 1(2)KC0320A 38 2CA0151 62 1(2)NV0813*

86 15 1(2)KC0332B 39 2CA0152 63 1(2)NV0254*

87 16 1(2)KC0333A 40 1(2)CF0033 64 1(2)NIO009A 88 17 1(2)NCO250A 41 1(2)CF0042 65 1(2)NIO010B 89 18 1(2)NCO251B 42 1(2)CF0051 66 1(2)NI0184B 90 19 1(2)NC0252B 43 1(2)CF0060 67 1(2)NI0185A 91 20 1(2)NC0253A 44 1(2)NS0038B 68 1(2)CF0028 92 21 1(2)NVO015B 45 1(2)NS0043A 69 1(2)CF0030 93 22 1(2)ND0032A 46 1(2)ND0028A 70 1(2)CF0037 94 23 1(2)ND0065B 47 1(2)NI0136B 71 1(2)CF0039 95 24 1(2)ND0001B 48 1(2)NI0183B 72 1(2)CF0046 I

I

Denotes partial stroke CNS ASME In-service Testing Program Rev. 03 Page 37 of 38 CNSSCOPE.DOC 10/31/02

.13 (continued)

CATAWBA NUCLEAR STATION MECHANICAL SYSTEMS ENGINEERING Priority for Cold Shutdown Valve Testing During Unplanned Entry into Mode 5 Special Notes:

1. Valves 1(2)KC0338B, 1(2)KC0424B, 1(2)KC0425A, 1(2)RN0437B, 1(2)RN0484A, 1(2)RN0487B, 1(2)NVO089A and 1(2)NVO091B are considered Cold Shutdown valves; however, exercising these valves while the reactor coolant pumps are in operation could result in pump damage.

OM Part 10 allows the test interval for these valves to be extended to refueling outages when the tests cannot be practically performed during power operations or cold shutdown outages (reference NUREG 1482, section 3.1.1.4).

2. The following valves are considered to be Cold Shutdown valves although they are actually tested in Mode 3 following each cold shutdown of greater than 30 days:

1(2)CA0037, 1(2)CA0041, 1(2)CA0045, 1(2)CA0049, 1(2)CA0053, 1(2)CA0057, 1(2)CA0061, 1(2)CA0065.

In addition, the following valves are also considered Cold Shutdown valves although the movement to close test is actually performed in Mode 4 during Pressure Boundary Valve testing:

1(2)NI0124, 1(2)NI0125, 1(2)NI0126, 1(2)NI0128, 1(2)NI0129, 1(2)NI0134, 1(2)NIO156, 1(2)NI0157, 1(2)NI0159, 1(2)NI0160, 1(2)NFI165, 1(2)NI0167, 1(2)NI0169, 1(2)NI0171, 1(2)NI0175, 1(2)NI0176, 1(2)NI0180 1(2)NI0181.

Testing of these valves during Modes 3 and 4 as described above is allowed per NUREG 1482, section 3.1.1.2.

3. The PORVs, valves 1(2)NCO032B, 1(2)NCO034A, 1(2)NCO036B are considered Cold Shutdown and are stroked EACH time the Unit enters Cold Shutdown. See Enclosure 9.11 in the IST Program Document for further guidance for testing valves 1(2)NCO032B, 1(2)NCO034A, and 1(2)NCO036B.

CNS ASME In-service Testing Program Rev. 03 Page 38 of 38 CNSSCOPE.DOC 10/31/02

Catawba Unit 1 Catawba Unit 2 TABLE OF ABBREVIATIONS Duke System Valve Class A

B C

E F

G H

Code Design Criteria Class 1, ASME Section 111, 1971 Class 2, ASME Section 111, 1971 Class 3, ASME Section 111, 1971 ANSI B31.1.0 (1967)

ANSI B31.1.0 (1967)

Duke Power Company Specification Designed for Seismic Loading Yes Yes Yes No Yes ANS Safety Class 1

2 3

NNS NNS No No NNS = Non-Nuclear Safety Numbering Sequence for Relief Request and Justification For Deferral Examples:

RELIEF REQUEST JUSTIFICATION FOR DEFEI CN-SRP-VG-01 CN-VG-01 SEQUENCE SEQI SYSTEM (N/A if Generic)

SYSTEM (SPECIFIC or GENERIC)

RELIEF for (PUMP or VALVE)

RRAL JENCE STATION STATION SECTION 2.0 Page 1 of 3 10/31/02 Rev.26

Catawba Unit 1 Catawba Unit 2 TABLE OF ABBREVIATIONS VALVE TYPE BA BF CK CT DI EX GB GT KT ND PG PR RV SC ST SV TW VB FREQUENCY 2RF 2Y 6M CM CS CSDRF ILRT M

NA Notel Note2 Note3 NPT NT Q

QCS QRF RF RR RV SD UNK VV W

Y Description Ball Butterfly Check Control Diagram Explosive Glove Gate Kerotest Needle Plug Pressure Regulating Relief Stop Check Stop Solenoid Three Way Vacuum Breaker Description Every Other Refueling Outage Testing Once Every Two Years Tested Every 6 Months Condition Monitoring Tested At Cold Shutdown Tested Each Cold S/D And Each RFO Tested Every ILRT Outage Tested Once Monthly No Specified Test Frequency See Technical Specification 6 Month, See Technical Specification CSD, Hot Tested Prior To LTOP No Periodic Test Required No Test Required Tested Once Quarterly Tested Quarterly And Each Cold Shut Down Tested Quarterly And Each Refueling Outage Tested Every Refueling Outage Per Relief Request Test Relief Valve Per Om-1 Schedule Disassemble One Valve Per Group Each Refueling Outage Unknown Visual Verification Frequency Tested Once Weekly Tested Once Yearly SECTION 2.0 Page 2 of 3 10/31/02 Rev.26

Catawba Unit 1 Catawba Unit 2 TEST TYPE AM ASGC BT CAL CSE CVE CVED EX FS FT IS u

LT LTNW LTTS MFVT MV NTS NT PF PI PIS PS PSTT PV RV RVPR SD SFB SFT SI, ST TTB UNK US Description Acoustic Monitoring Aux Safeguards Circuitry Test New Baseline Test Calibration Contact System Engineering Contact Valve Engineering Contact Valve Engineering for DP Test Requirements Explosive Valve Test Full Stroke Exercise Valve To Safety Position(s)

Failed To Safe Position Instrumented Electrical Stroke Leak Rate Test Valve To App J Requirements(s)

Leak Rate Test Valve To Section XI Requirements(s)

Qualified Seal System Leak Rate Test (CNS only)

Leak Test Per Tech Spec Requirements Miniflow Verification Test MOVATS/Votes - MOV's See Program Document - Section 4.5 No Test Required Piping Flush Verify The Valve Remote Position Indication Pre And Post Maintenance Instrumented Electrical Stroke Partial Stroke Exercise Valve Pump Source Transfer Test MOVATS/Votes - POV's Safety And Relief Valve Test Safety And Relief Valve Test - Pressure Regulator Sample Disassembly System Flow Balance Failed to Safe Position and Timed Special Test For Particular Component Or Situation Measure Full Stroke Time Of Valve Torque Test Bench Unknown Functional (Uninstrumented) Stroke Only OM-10 VALVE CATEGORIES Category A Leakage is Critical Category B Leakage is NOT Critical Category C Self Actuating (Checks, Reliefs, Etc.,)

SECTION 2.0 Page 3 of 3 10/31/02 Rev.26

DUKE POWER CATAWBA NUCLEAR STATION PUMP INSERVICE TESTING PROGRAM Section 3.0

Equipment ID Description Flow Diagram Pump ASME Test Type Frequency Relief Request Class CA - Auxiliary Feedwater System ICAPUOOO1 Motor Driven Auxiliary Feedwater Pump IA ICAPU0002 Motor Driven Auxiliary Feedwater Pump I B ICAPU0003 Turbine Driven Auxiliary Feedwater Pump #1 2CAPUOOOI Motor Driven Auxiliary Feedwater Pump 2A 2CAPU0002 Motor Driven Auxiliary Feedwater Pump 2B 2CAPU0003 Turbine Driven Auxiliary Feedwater Pump #2 CN-1592-1.0 Centrifugal CN-1592-1.0 Centrifugal CN-1592-1.0 Centrifugal CN-2592-1.0 Centritugal CN-2592-1.0 Centrifugal CN-2592-1.0 Centrifugal 3

Vibration Test Tested once quarterly System Flow Balance Test Tested once Quarterlv Differential Pressure Performance Tesfiested once quarterlv 3

Vibration Test Tested once qiuarterlv System Flow Balance Test Tested once quarterlv DitTerential Pressure Performance Tesff'ested once quarterlv 3

Vibration Test Tested once quarterly System Flow Balance Test Tested once quarterly Differential Pressure Performance Tesifested once quarterlv 3

Vibration Test Tested once quarterly System Flow Balance Test Tested once quarterly Differential Pressure Performance Tesfrested once quarterly 3

Vibration Test Tested once quarterlv System Flow Balance Test Tested once quarterly Differential Pressure Performance Tesffested once quarterly Catawba Nuclear Station lnserviceTesting Program Submittal - Pumps fniorln-a ?. Revi*'onp ?A (10.11102)

CA - Auxiliary Feedwvater System None None CN-SRP-CA-01 None None CN-SRP-CA-0 I None None None None None CN-SRP-CA-01 None None CN-SRP-CA-01 None None None Section 3.1 Paae I

Equipment ID Description Flow Diagram Pump ASME Test Type Frequency Relief Request Class KC - Component Cooling System I KCPUOOO Component Cooling Water Pump I A I IKCPU0002 Component Cooling Water Pump IA2 I KCPU0003 Component Cooling Water Pump I1B I IKCPU0004 Component Cooling Water Pump IB2 2KCPUOOOI Component Cooling Water Pump 2AI 2KCPU0002 Component Cooling Water Pump 2BI 2KCPU0003 Component Cooling Water Pump 2A2 2KCPU0004 Component Cooling Water Pump 2B2 CN-1573-1.0 Centrifugal CN-1573-1.0 Centrifugal CN-1573-1.0 Centrifugal CN-1573-1.0 Centrifugal CN-2573-1.0 Centrifugal CN-2573-1.0 Centrifugal CN-2573-1.0 Centrifugal CN-2573-1.0 Centrifugal 3

Vibration Test Tested once quarterlv Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesfrested once quarterlv 3

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesffested once quarterly 3

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesffested once quarterlv 3

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesfrested once quarterly 3

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesrrested once quarterly 3

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesifested once quarterly 3

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesirested once quarterly 3

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance TestI'ested once quarterly Catawba Nuclear Station Inservice Testing Program Submittal -Pumps Interval 2. Revision 26 (10/31I02)

KC - Component Cooli/m System None None None None None None None None None None None None None None None None None None None None None None None None Section 3.1 Page 2

Equipment ID Description Flow Diagram Pump ASME Test Type Frequency Relief Request Class ND - Residual Heat Removal System INDPUOOOI Residual Heat Removal Pump IA CN-1561-1.0 VLS Centrifugal INDPU0002 Residual Heat Removal Pump I B CN-1561-1.1 VLS Centrifugal 2NDPUOOOI Residual Heat Removal Pump 2A CN-2561-1.0 VLS Centrifugal 2NDPU0002 Residual Heat Removal Pump 2B CN-2561-1.1I VLS Centrifugal 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesffested once quarterly 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance TesiTested once quarterly 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesflested once quarterly 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Testfested once quarterly Catawba NuclearStation Inservice Testing Program Submittal - Pumps Internal 2. Revision 26 (10/31/02)

None None None None None None None None None None None None ND - Residual Heat Removal System Section 3.1 Page 3

Equipment ID Description Flow Diagram Pump ASME Test Type Frequency Relief Request Class NI - Safety Iniection System iNIPU0009 Safety Injection Pump IA INIPUOIO Safety Injection Pump IB 2NIPU0009 Safety Injection Pump 2A 2NIPUOOIO Safety Injection Pump 2B CN-1562-1.2 Centrifiugal CN-1562-1.2 Centrifugal CN-2562-1.2 Centrifugal CN-2562-1.2 Centrifugal 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance TesfFested once quarterly 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesfrested once quarterly 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesffested once quarterly 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesffested once quarterly Catawba Nuclear Station Inservice Testing Program Submittal - Pumps Internal 2. Revision 26 (10/31/02)

NI - Safety Injection Svstem None None None None None None None None None None None None Section 3.1 Page 4

Equipment ID Description Flow Diagram Pump ASME Test Type Frequency Relief Request Class NS - Containment Spray System INSPUOOI Containment Spray Pump IA INSPU002 Containment Spray Pump IB 2NSPUO0I Containment Spray Punmpl 2A 2NSPU002 Containment Spray Pump 2B CN-1563-1.0 VLS Centrifugal CN-1563-L.0 VLS Centrifugal CN-2563-1.0(

VIS Centrirugal CN-2563-1.0 VLS Centrifugal 2

Vibration Test Tested once quarterly Differential Pressure Performance Tesfrested once quarterly 2

Vibration Test Tested once quarterly Differential Pressure Performance Tesffested once quarterly 2

Vibration lest Tested once quarterly Differential Pressure Performance Tesffested once quarterly 2

Vibration Test Tested once quarterly Differential Pressure Performance Tesffested once quarterly Catawvba Nuclear Station Inscricec lcsling Program Submittal - Pumps Interval 2. Revision 26 (10/31/02)

NS - Containment Spray System None None None None None None None None Section 3.1 Page 5

Equipment ID Description Flow Diagram Pump ASME Test Type Frequency Relief Request Class NV - Chemical & Volume Control System INVPUOOOIC Standby Makeup Pump CN-1554-1.8 INVPU0015 Centrifugal Charging Pump IA INVPU0016 Centrifugal Charging Pump lB 2NVPUOOOIC Standby Makeup Pump 2NVPUOO5 Centrifugal Charging Pump 2A 2NVPUOO6 Centrifugal Charging Pump 2B Gear Positive Displacement CN-1554-1.7 Centrifugal CN-1554-1.7 Centrifugal CN-2554-1.8 Gear Positive Displacement CN-2554-2.0 Centrifugal CN-2554-1.7 Centrifugal 0

Vibration Test Tested once quarterly Differential Pressure Performance Tesffested once quarterly 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesfrested once quarterly 2

Vibration Test Tested once quarterly Pump Head Curve Test No specified test frequency Differential Pressure Performance Tesffested once quarterly o

Vibration Test Tested once Quarterlv Differential Pressure Performance Tesffested once quarterly 2

Vibration Test Tested once quarterlv Pump Head Curve Test No specified test frequencv Differential Pressure Performance Tesfrested once quarterlv 2

Vibration Test Tested once qjuarteriv Pump Head Curve Test No specified test frequencv Differential Pressure Performance Tesffested once quarterlv Catawba Nuclear Station Inservice Testing Program Submittal -Pumps Intnrval 2. Revinin 26 (10/31/02)

NV - Chemical & Volume Control System None None None None None None None None None None None None None None None None Section 3.1 Pauee6

Equipment ID Description Flow Diagram Pump ASME Test Type Frequency Relief Request Class RN - Nuclear Service Water System IRNPU0002 Nuclear Service Water Pump IA CN-1574-1.0 VLS Centrifugal IRNPU0004 Nuclear Service Water Pump IlB CN-1574-1.2 VLS Centrifugal 2RNPU0002 Nuclear Service Water Pump 2A CN-2574-1.0 VLS Centrifugal 2RNPU0004 Nuclear Service Water Pump 2B CN-2574-1.2 VLS Centrifugal 3

Vibration Test Tested once quarterlv System Flow Balance Test Tested once quarterlv Differential Pressure Performance Tesifested once quarterlv 3

Vibration Test Tested once Quarterlv System Flow Balance Test Tested once quarterlv Differential Pressure Performance Tesffested once Quarterlv 3

Vibration Test Tested once quarterly System Flow Balance Test Tested once quarterlv Differential Pressure Performance Testfested once Qjuarterlv 3

Vibration Test Tested once quarterlv System Flow Balance Test Tested once quarterly Differential Pressure Performance Tesffested once quarterly Catawba Nuclear Station Inservice Tesling Program Submittal - Pumps Interval 2. Revision 26 (10/31/02)

None None None None None None None None None None None None RN - Nuclear Service Water System Section 3.1 Page 7

Equipment ID Description Flow Diagram Pump ASME Test Type Frequency Relief Request Class YC - Control Area Chilled Water System OYCPUDOOI Control Area Chilled Water Pump Train A CN-1578-2.0 OYCPU0002 Control Area Chilled Water Pump Train B Centrifugal CN-1578-2.0 Centrifugal 3

Vibration Test Tested once quarterly Difterential Pressure Performance Tesffested once quarterly 3

Vibration Test Tested once quarterly Differential Pressure Performance Testrested once quarterly Catawba Nuclear Station lnservice'rTsting Program Submittal - Pumps Inrertal 2. Revision 26 (10/31/02)

None None None None Section 3.1 Pa~e 8 YC - Control Area Chilled Wafer System

DUKE POWER CATAWBA NUCLEAR STATION VALVE INSERVICE TESTING PROGRAM Section 4.0

Valve Flow ASNIE Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest RB B

Steam Generator Blowdown Recycle System I BB0008A CN-1580-1.0 K05 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0008A CN-2580-1.0 J05 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage IBB0010B CN-1580-l1. 0 K07 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0010B CN-2580-1.0 J06 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage Catawba NMclear Station - ISTSubnnual for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 BB-Steam Generator Blowdown Recycle System Page I of 7

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I BB0019A CN-1580-1.0 C05 2

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

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0019A CN-2580-1.0 DO5 2

B Yes Gate Rotork N\\one Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST' Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I BB0021B CN-1580-1.0 C07 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2 BB0021 B CN,-2580-1 0 D06 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I BB0052 C,\\"-1580-1.0 K05 2

C Yes Check Self Actuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required 2BB0052 CN-2580-1.0 J05 2

Y es Check Self Actuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required Catawba Nuclear Station -IST Submitual for Valves Interval 2. Revision 26 Section 4.1 BB-Steam Generator Blowdown Recycle System Page 2 of 7 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD P1 Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IBB0053 CV-1580-1.0 105 2

C Yes Check SelfActuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required 2BB0053 CN-2580-1.0 H05 2

C Yes Check SelfActuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required 1BB0054 CX-)1580-1.0 F05 2

C Yes Check Self Actualed None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required 2BB0054 CN-2580-1.0 F05 2

C Yes Check Self Actuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required IBB0055 CV-)1580-1.0 DO5 2

C Yes Check SelfActuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required 2BB0055 CN-2580-1.0 DO5 2

C Yes Check Self Actuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required IBB0056A CN-)1580-1.0 H05 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0056A CA'-2580-10 1105 2

B Yes Noie Yes SI Measure Full-Stroke Open to Closed Time of Valve ST Measure Full-Stroke Open to Closed Time of Valve 0

Tested once None quarterly RIF Tested at None refueling outage Catarba Nuclear Station - 1STSubmittal for I'alves Interval 2. Revision 26 Section 4.1 BB-Steam Generator Blowdown Recycle System Page 3 of 7 (10/31/02)

Gate Rotork

Valve Flow ASNIE Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest 1 BB0057B CN-1580-1.0 H07 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0057B CN-2580-.0 H06 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I BB0060A CN-1580-1.o0 F05 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0060A CV-2580-1.0 F05 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage Catavba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 BB-Steam Generator Blowdown Recycle System Page 4 of 7

Valve Flow ASNIE Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I BB0061B CN-1580-1.0 F07 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0061 B CN-2580-1I. 0 F06 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage IBB0147B CN-1580-1.o K07 2

B Yes Globe Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0147B CN'-2580-. 0 K06 2

B Yes Globe Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage Catawba Nuclear Station - IST Submittal for Valv'es Interval 2. Revision 26 (10/31/02)

Section 4.J1 BB-Steam Generator Blowdown Recycle System Page 5 of 7

Valve Flow ASNIE Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IBB0148B CA-1580-1.0 1"H07 2

B Yes Globe Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0148B CN-2580-1.0 106 2

B Yes Globe Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST' Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage IBB0149B CN-1580-o.0 F07 2

B Yes Globe Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2BB0149B CY-2580-1.0 G06 2

B Yes Globe Rolork NoneI

'Yes ST Measure Full-Stroke Time of Valve ST Measure Full-Stroke Time of Valve Open to Closed 0

Open to Closed RF Tested once None quarterly Tested at None refueling outage Catawba Nuclear Station - ISTSiubmittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.!

BB-Steam Generator Blowdown Recycle System Page 6 of 7

Valve Flow ASNIE Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IBB0150B CA-'-1580-1/0 C07 2

B Yes Globe Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage ST Measure Full-Stroke Open to Closed Time of Valve ST Measure Full-Stroke Open to Closed Time of Valve 0

Tested once None quarterly RF Tested at None refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 BB-Steam Generator Blowdown Recycle System Page 7 of 7 2BB0150B CN-2580-1.0 E06 2

B Yes Globe Rotork None Yes

Valve Flow ASNIE Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest CA

- Auaxiliary Feedwater System ICAOOO8 CN-1592.l.0 D09 3

C Yes Check SelfActuated CN-CA-03 No FS Full-Stroke Exercise Both (Stroke Test)

CM Valve to Safety Position(s)

Condition CN-GRV-04 Monitoring 2CA0008 CN-2592-1.0 D09 3

C Yes Check Self Actuated CN-CA-03 No FS Full-Stroke Exercise Both (Stroke Test)

CM Valve to Safety Position(s)

Condition CN-GRV-04 Monitoring ICAO010 CN-1592-l.O DO5 3

2CAOOIO CN-2592-1.0 DO5 3

C Yes C

Yes Check Self Actuated CN-CA-03 No Check SelfActuated CN-CA-03 No FS Full-Stroke Exercise Both (Stroke Test)

CM Valve to Safety Position(s)

FS Full-Stroke Exercise Both (Stroke Test)

CM Valve to Safety Position(s)

Condition CN-GRV-04 Monitoring Condition CN-GRV-04 Monitoring ICA0012 CN-1592-l.0 DOI 3

C Yes Check Self Actuated CN-CA-03 No FS Full-Stroke Exercise Both (Stroke Test)

CM Valve to Safety Position(s)

Condition CN-GRV-04 Monitoring 2CA0012 CV-2592-1.0 DOI 3

C Yes Check SelfActuated CN-CA -03 No FS Full-Stroke Exercise Both (Stroke Test)

CM Valve to Safety Position(s)

Condition CN-GRV-04 Monitoring Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 CA-Auxiliary Feedwater System Page)I of 15

Valve Flow ASME Valve Active Valve Actuator JOD P1 Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction FrequencyIDescription Reqest ICA0015A CN-1392-l.0 D02 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly 2CA0015A CN-2592-1.0 D02 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly ICA0018B CN-1592-I.O D06 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly 2CA0018B CN-2592-l.O D06 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly ICA0020 CN-1592-1.0 Ill/

3 C

Yes Three Way Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2CA0020 CN-2592-1.0 111i 3

C Yes Three Way Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s)

ICA0023 CN-1592-1.0 J10 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2CA0023 CN-2592-1.0 3lO 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Valve to Safety Position(s)

Closed to Open 0

Tested once None quarterly Catmvba Nuclear Station - IST'Submintal for Valves Interval 2 Revision 26 Section 4. 1 CA-Auxiliary Feedwater System Page 2 of 15 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0027 CN-1592-1.0 104 3

C Yes Three Way SelfActuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2CA0027 CN-2392-1.0 104 3

C Yes Three Way Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s)

ICA0028 CN-l592-l.0 J03 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2CA0028 CN-2592-l.0 J03 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s)

ICA0032 CN-1592-1.0 108 3

C Yes Three Way Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2CA0032 CN-2592-1.0 108 3

C Yes Three Way Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s)

Catawba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 (10/31/02)

Section 4.1 CA-Auxiliary Feedwater System Page 3 of 15

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0033 CN-1592-1.0 J07 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2CA0033 CN-2592-1.0 J07 3

C Yes Check SelfActuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 1CA0036 CN-1592-1.l C12 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2CA0036 CN-2592-L.l C12 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly I CA0037 CN-1592-1.1 G12 2

C Yes Check Self Actuated CN-CA -01 No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage 2CA0037 CN-2592-1.l G12 2

C Yes Check SelfActuated CN-CA,-01 No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage ICA0038A CN-1592-1. I H12 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly ST Measure Full-Stroke Time of Valve Both (Stroke Test) 0 Tested once None quarterly Catavba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 Section 4.1 CA-Auxiliary Feedwaler System Page 4 of 15 (10/31/02) 2CA0038A CN-2592-l.1. I1112 B

Yes Gate Rotork None Yes

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0040 CN-1592-1.1 J12 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2CA0040 CN-2592-1. I J12 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly ICA0041 CN-1592-1.1 112 2

C Yes Check Self Actuated CN-CA-0)

No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage 2CA0041 CN-2592-l.I 112 2

C Yes Check Self Actuated CN-CA-0!

No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage ICA0042B CN-1592-1.1 112 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2CA0042B CN-2592-1. I 112 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly ICA0044 CN-1592-1.I J09 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2CA0044 CN-2592-1.1 J09 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 Section 4.1 CA-Auxiliary Feedwater System Page 5 of 15 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I CA0045 CN-1592-1. I J109 2

C Yes Check Self Actuated CN-CA -0)

No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage 2CA0045 CN-?592-l. 1 109 2

C Yes Clheck Self Actuated CN-CA-Ol No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage ICA0046B CN-1592-J.l 109 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2CA0046B CN-2592-l. 1 109 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 1CA0048 CN-1592-1.l C09 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2CA0048 CN-2592-1. I C09 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly ICA0049 CN-l1592-1.1 GO9 2

C Yes Check Self Actuated CN-cA-OI No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage 2CA0049 CN-2592-l. /

(W9 2

C" Yes

('heck Self Actuated (WN-cAI-0 No CFS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage Catawvba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 Section 4. 1 CA-Auxiliary Feedwater System Page 6 of 15 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0050A CN-1592-. I 1H09 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2CA0050A CN-2592-l. 1 H09 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly ICA0052 CN-1592-1.1 C06 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2CA0052 CN-2592-i.l C06 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly ICA0053 CN-1592-1.1 G06 2

C Yes Check Self Actuated CN-CA-O0 No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage 2CA0053 CN-2592-1. I G09 2

C Yes Check Self Actuated CN-CA-01 No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage 1CA0054B CN-1592-l.1 H06 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2CA0054B CN-2592-1. I Ht06 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Time of Valve Both (Stroke Test) 0 Tested once None quarterly Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (101/311o 2)

Section 4.1 CA-Auxiliary Feedwater System Page 7 of 15

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Rcqest ICA0056 CN-1592-1.1 J06 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2CA0056 CN-2592-1.

,J06 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 1CA0057 CN-1592-1.1

,J06 2

C Yes Check Self Actuated CN-CA-0I No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage 2CA0057 CN-2592-1. 1 106 2

C Yes Check SelfActuated CN-CA -01 No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage ICA0058A CN-1592-1.1 106 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2CA0058A CN-2592-1.1 106 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly ICAO060 CN-1592-1.1 J03 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2CA0060 (N-2592-l.1 J03 3

1B

)es Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly Catawba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 Section 4.1 CA-Auxiliary Feedwater System Page 8 of I5 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0061 CN-1592-1. 1 103 2

C Yes Check Self Actuated CN-CA-01 No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage 2CA0061 CN-2592-1.1 103 2

C Yes Check Self Actuated CN-CA-0)

No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage ICA0062A CN-1592-1. /

103 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time or Valve quarterly 2CA0062A CN-2592-1. I 103 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly ICA0064 CN-1592-1.1 C03 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2CA0064 CN-2592-1.1 C03 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly ICA0065 CN-1592-1.1 G03 2

C Yes Check Self Actuated CN-CA,-01 No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage 2CA0065 CN-2592-1. I G03 2

C Yes Check Self Act ated CN-CA-0l No FS Full-Stroke Exercise Closed to Open RF Tested at None Valve to Safety refueling Position(s) outage Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 Section 4.)1 CA-Auxiliary Feedwater System Page 9 of 15 (10/31102)

Valve Flow ASME Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0066B CN-1592-1.1 H03 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2CA0066B CN-2592-1. 1 H03 2

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

Q Tested once None Time of Valve quarterly ICA0085B CN-1592-1.0 D07 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly 2CA0085B

('N-2592-1.0 D07 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly ICAOI 16A CN-1592-1.0 D08 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly 2CA0116A CN-2592-1.0 D08 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly ICA0149 CN-1592-1.1 i01 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CA0149 CN-2592-1.

1/01 2

B Yes Gale Air CN-CA-05 Yes SF1' Failed to Safe Position and Timed SFT Failed to Safe Position and Timed Open to Closed Open to Closed CS Tested at cold None shutdown RF Tested at None refueling outage Catawba Nuclear Station - ISTSubmittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 CA-Auxiliary Feedwater System Page 10 of 15

Valve Flow ASNIE Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0150 CN-1592-1.J 1035 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CA0150 CN-2592-1.l lO/

2 B

Yes Gate Air CN-CA-05 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFr Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage ICA0151 CN-1592-1.1 108 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SF1' Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CA0151 CN-2592.1.1 108 B

Yes Gate Air CN-CA-05 Yes SFr Failed to Safe Position Open to Closed and Timed SFT Failed to Safe Position Open to Closed and Timed CS Tested at cold None shutdown RF Tested at None refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 Section 4. 1 CA-Auxiliary Feedwater System Page 11 of 15 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0152 CN-1592-1.1 1//

2 B

Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CA0152 CN-2592-1.

/it 2

B Yes Gate Air CN-CA-05 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage ICA0173 CANI592-1.0 E08 3

C Yes Check Self'Actuated CN-CA-04 No FS Full-Stroke Exercise Both (Stroke Test)

CM Condition CN-GRV-04 Valve to Safety Monitoring Position(s) 2CA0173 CN-2592-l.0 E08 3

C Yes Check Self Actuated CN-CA-04 No FS Full-Stroke Exercise Both (Stroke Test)

CM Condition CN-GRV-04 Valve to Safety Monitoring Position(s)

ICA0185 CN-1592-1.1 EOI 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CA0185 CN-2592-1.1 EOI 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage Catawba Nuclear Station - 1ST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 CA-Auxiliary Feedwater System Page 12 of 15

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0186 CN-1592-1.1 E05 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CA0186 CN-2592-1.1 E05 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 1CA0187 CN-1592-1.1 E08 2

B Yes Gate Air None Yes SF1' Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CA0187 CN-2592-1.1 E08 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 Section 4.1 CA-Auxiliary Feedwater System Page 13 of 15 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction FrequencyDescription Reqest 1CA0188 CAN-1592-1.1 Ell 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CA0188 CN-2592-1.1 Elli 2

B Yes Gate Air None Yes SFI" Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage ICA0255 CN-1592-1.0 El 3

C No Relief Self Actuated None Yes RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV-Ol,02,03 Test valve per Om-I schedule 2CA0255 CN-2592-I.O F2 ICA0256 CN-1592-1.O F4 2CA0256 CN-2392-1.0 15 C

No 3

C No C

No Relief SelfActuated Relief Self Actuated Relief Self Actuated None Yes None Yes None Yes RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV-01,02.03 Test valve per OM-1 schedule RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV-01,02,03 Test valve per OM-1 schedule RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV-01,02,03 Test valve per OM-i schedule Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 Section 4.1 CA-Auxiliary Feedwater System Page 14 of 15 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICA0257 CN-1592-1.0 F8 2CA0257 CN-2592-1.0 F9 3

C No 3

C No Relief SelfActuated Relief Self Actuated None Yes None Yes RV Safety and Relief Valve Closed to Open Test RV Safety and Relief Valve Closed to Open Test RV Test relief CN-GRV-01,02,03 valve per OM-I schedule RV Test relief CN-GRV-01.02.03 valve per OM-I schedule ICA0291 CN-1592-l.0 D7 2CA0291 CN-2592-1.0 D7 ICA0292 CN-1592-l.0 D7 2CA0292 CN-2592-1.0 D7 3

C Yes 3

C Yes Check Self Actuated CN-CA-06 Yes Check Self Actuated CN-CA-06 Yes Check SelfActuated CN-CA-06 Yes Check Self Actuated CN-CA-06 Yes FS Full-Stroke Exercise Valve to Safety Position(s)

FS Full-Stroke Exercise Valve to Safety Position(s)

Both (Stroke Test)

CM Both (Stroke Test)

CM Condition CN-GRV-04 Monitoring Condition CN-GRV-04 Monitoring Condition CN-GRV-04 Monitoring Condition CN-GRV-04 Monitoring Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 CA-Auxiliary Feedwater System Page 15 of 15

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest CF " Feedwater System ICF0028 CN-1591-1.1 J13 3

B Yes Gate Air CN-CF-04 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0028 CN-259 1-1. I J13 3

B Yes Gate Air CN-CF-04 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage ICFO030 CN-1591-I.I JII NCA B

Yes Gate Air CN-CF-OS Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0030 CN-2591-I.J JI I NA4 B

Yes Gate Air CN-CF-O5 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 Section 4.1 CF-Feedwater System Page I of 8 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICF0031 CN-1591-1.1 G13 2

C Yes Check Self Actuated CN-CF-02 No FS Full-Stroke Exercise Open to Closed CM Condition CN-GRV-04 Valve to Safety Monitoring Position(s) 2CF0031 CN-2591-1.1 G13 2

C Yes Check Self Actuated CN-CF-02 No FS Full-Stroke Exercise Open to Closed CM Condition CN-GRV-04 Valve to Safety Monitoring Position(s)

I CF0033 CN-1591-1. /

F13 2

B Yes Gate Hydraulic CN-CF-01 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0033 CAN-2591-. I F13 2

B Yes Gate Hydraulic CN-CF-O0 Yes SFT' Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 1CF0037 CN.1591-1.1 J9 3

B Yes Gate Air CN-CF-04 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0037 C'N-2591-1. I J9 3

Ii Yes Gate Air (N-(.'C-04 Yes SF1' Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SIFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage Catmvba Nuclear Station - ISTSubmittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 CF-Feedwater System Page 2 of 8

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction FrequencylDescription Reqest ICF0039 CN-l591-l.l JlO?

NA B

Yes Gate Air CN-CF-05 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0039 CN-2591-l.l ilO)

?M B

Yes Gate Air CN-CF-05 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage ICF0040 CN-1591-1.1 G09 2

C Yes 2CF0040 CN-2591-1.l G09 2

C Yes Check Self Actuated CN-CF-02 No Check Self Actuated CN-CF-02 No FS Full-Stroke Exercise Valve to Safety Position(s)

FS Full-Stroke Exercise Valve to Safety Position(s)

Open to Closed CM Condition CN-GRV-04 Monitoring Open to Closed CM Condition CN-GRV-04 Monitoring 1CF0042

('N-159l-l.l 1F09 2

B Yes Gate Hydraulic CN-CF-Ol Yes SF1T Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0042 CN-259l-l.l F09 Yes Gate Hydraulic CN-CF-O1 Yes SFT Failed to Safe Position and Timed SFT Failed to Safe Position and Timed Open to Closed Open to Closed CS Tested at cold None shutdown RF Tested at None refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 Section 4.1 CF-Feedwater System Page 3 of 8 (10/31/02)

ASME Valve Active Valve Class Catg.

Type Actuator Type JOD pi Test Test Type Type Description Test Test Frequency Relief Direction Frequency Description Reqest ICF0046 CN-1.91-.I-J6 2CF0046 CN-2591-t.t A6 1CF0048 CN-1591-I.I 15 2CF0048 CN-2591-l.1 ii B B Yes B

Yes NA B

Yes Gate Gate Gate Gate Air CN-CF-04 Yes Air CN-CF-04 Yes Air CN-CF-05 Yes Air CN-CF-05 Yes SFT Failed to Safe Position Open to Closed and Timed SFr Failed to Safe Position Open to Closed and Timed SFT Failed to Safe Position Open to Closed and Timed SFTr Failed to Safe Position Open to Closed and Timed SFF Failed to Safe Position Open to Closed and Timed SFT Failed to Safe Position Open to Closed and Timed SFT Failed to Safe Position Open to Closed and Timed SFT Failed to Safe Position Open to Closed and Timed CS Tested at cold None shutdown RIF Tested at None refueling CS Tested at cold None shutdown RF Tested at None refueling outage CS Tested at cold None shutdown RIF Tested at None refueling CS Tested at cold None shutdown RF Tested at None refueling outage ICF0049 CN-1591-1.1 G06 2

C Yes Check Self Actuated CN-CF-02 No FS Full-Stroke Exercise Open to Closed CM Condition CN-GRV-04 Valve to Safety Monitoring Position(s) 2CF0049 CN-2591-1.l G06 2

C Yes Check Self Actuated CN-CF-02 No FS Full-Stroke Exercise Valve to Safety Open to Closed CM Condition CN-GRV-04 Monitoring Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 Section 4.1 CF-Feedwater System Page 4 of 8 (10/31/02)

Valve Flow Diagram outage outage Position(s)

Valve Flow ASME Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICF0051 CN-1S91-1.1 F06 2

B Yes Gate Hydraulic CN-CF-1I Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0051 CN-2591-l. 1F06 2

B Yes Gate Hydraulic CN-CF-0I Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 1CF0055 CN-1591-1.1 J2 3

B Yes Gate Air CN-CF-04 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0055 CN-2591-1.1 J2 3

B Yes Gate Air CN-CF-04 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 Section 4.1 CF-Feedwater System Page 5 of 8 (10/31/02)

Valve Flow ASNIE Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest 1CF0057 CN-1591-1.l J4 NA B

Yes Gate Air CN-CF-05 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0057 CN-2591-1. 1 J4 NA B

Yes Gate Air CN-CF-05 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage ICF0058 CN-1591-1.1 G03 2

C Yes 2CF0058 CN-2591-.1I G03 2

C Yes Check SelfActuated CN-CF-02 No Check Self Actuated CN-CF-02 No FS Full-Stroke Exercise Valve to Safety Position(s)

FS Full-Stroke Exercise Valve to Safety Position(s)

Open to Closed CM Condition CN-GRV-04 Monitoring Open to Closed CM Condition CN-GRV-04 Monitoring ICF0060 CN-1591-1.1 F03 2

B Yes Gate Hydraudic CN-CF-OJ Yes SF1' Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage 2CF0060 CN-2591-1.1 F03 2

B Yes Gate Hydraulic CN-CF-O0 Yes SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 Section 4.1 CF-Feedwater System Page 6 of 8 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICF0087 CN-1591.1.1 F02 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SF1' Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown 2CF0087 CN-2591-1I.

F02 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown ICF0088 CN-1591-1.1 F06 2

B Yes Gale Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown 2CF0088 CN-2591-1.1 F06 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown ICF0089 CN-1591-1.1 F09 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown 2CF0089 CN-2591-1.I F09 2

B Yes Gate Air None Yes SFFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 Section 4. 1 CF-Feedwater System Page 7 of 8 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ICF0090 CN-1591-1.1 F13 2

B Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SF1 Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown 2CF0090

('N-2591-1. I 1F13 2

B Yes Gate Air None Yes SFf1 Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed CS Tested at cold None and Timed shutdown 2CF0166 CN-2591-1.1 G13 2

C Yes Check Self Actuated CN-CF-03 No FS Full-Stroke Exercise Open to Closed SD Disassem one None Valve to Safety vlv per grp ca.

Position(s)

RFO 2CF0167 CN-2591-1.l G09 2

C Yes Check SelfActuated CN-CF-03 No FS Full-Stroke Exercise Open to Closed SD Disassem one None Valve to Safety vlv per grp ea.

Position(s)

RFO 2CF0168 CN-2591-1.1 G06 2

C Yes Check Self Actuated CN-CF-03 No FS Full-Stroke Exercise Open to Closed SD Disassem one None Valve to Safety vlv per grp ca.

Position(s)

RFO 2CF0169 CN-2591-1.1 G02 2

C Yes Check Self Actuated CN-CF-03 No FS Full-Stroke Exercise Open to Closed SD Disassem one None Valve to Safety vlv per grp ea.

Position(s)

RFO Catawba Nuclear Station - ISTSubmittal for Valves Interval 2, Revision 26 Section 4. 1 CF-Feedwater System Page 8 of 8 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction FrequencyDescription Reqest FD

- Diesel Generator Fuel Oil System I FD0022 CN-1609-3.0 J13 3

B Yes Globe Solenoid None No SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2FD0022 CN-2609-3.0 J13 3

B Yes Globe Solenoid None No SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly I FD0029 CN-1609-3.0 F05 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2FD0029 CN-2609-3.0 F05 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s)

I FD0034 CN-1609-3.0 H13 3

C Yes 2FD0034 CN-2609-3.0 HI3 3

C Yes Relief SelfActuated Relief Self Actuated None No None No RVPR Safety and Relief Valve Closed to Open RV Test - Pressure Regulating RVPR Safety and Relief Valve Closed to Open RV Test - Pressure Regulating Test relief CN-SRV-FD-01 valve per OM-l schedule Test relief CN-SRV-FD-OI valve per OM-I schedule Catawba Nuclear Station - lST7Submittal for IValves Interval 2. Revision 26 (10/31/02)

Section 4. 1 FD-Diesel Generator Fuel Oil System Page I of 2

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I FD0062 CN-1609-3. /

J12 3

B Yes Globe Solenoid None No SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2FD0062 CN-2609-3.l JI2 3

B Yes Globe Solenoid None No SF1T Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly I FD0069 CN-1609-3. I F05 3

C Yes Check SelfActuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2FD0069 CN-2609-3. 1 FO 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s)

I FD0074 CN-1609-3.

H13 3

C Yes 2FD0074 CN-2609-3.1 H13 3

C Yes Relief Self Actuated Relief Self Actuated None No None No RVPR Safety and Relief Valve Closed to Open RV Test - Pressure Regulating RVPR Safety and Relief Valve Closed to Open RV Test -Pressure Regulating Test relief CN-SRV-FD-01 valve per OM-I schedule Test relief CN-SRV-FD-01 valve per OM-I schedule Catawba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 (1o/31102)

Section 4.1 FD-Diesel Generator Fuel Oil System Page 2 of 2

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest FW - Refueling Water System IFWOOOIA CN-1571-1.O J13 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2FW0001A CN-2571-1.0 J13 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 1 FW0004 CN-1571-1.0 L07 2

A No Gate Manual None No LU Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2FW0004 CN-2571-1.0 L07 2

A No Gate Manual None No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I FW0005 CN-1571-JO LOS 2

AC Yes Check SelfActuated CN-FW-02 No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2FW0005 CN-2571-1.0 LOS 2

4C Yes Check Self Actuated CN-FW-02 No LU Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 Section 4.1 FW-Refueling Water System Page I of 5 (10/31/02)

Valve Flow ASNIE Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I FWOOI I CN-1571-1.0 J04 2

A No Plug Manual None No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2FWOOI I CN-2571-1.0 J

J04 2

A No Plug Manual None No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage IFW0013 CN-1571-1.0 105 2

A No Plug Manual None No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2FW0013 CN-2571-l.0 A105 2

A No Plug Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I FW0027A CN-1571-l.0 F03 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested at None Time of Valve refueling outage 2FW0027A CN-2571-1.0 F03 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested at None Time of Valve refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 FW-Refueling Water System Page 2 of 5

Valve Flow ASME Valve Active Valve Actuator JOD P1 Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IFW0028 CN-1571-1.0 F02 2FW0028 CN-25Rl-..O F02 2

C Yes C

Yes Check Self Actuated CN-FW-O1 No Check SelfActuated CN-FW-0I No PS Partial-Stroke Exercise Valve FS Full-Stroke Exercise Valve to Safety Position(s)

PS Partial-Stroke Exercise Valve FS Full-Stroke Exercise Valve to Safety Position(s)

Closed to Open CM Condition CN-GRV-04 Monitoring Open to Closed 0

Tested once None quarterly Closed to Open CM Condition CN-GRV-04 Monitoring Open to Closed 0

Tested once None quarterly I FW0032B CN-1571-10 J13 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2FW0032B CN-2571-10 J13 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage Catawba Nuclear Station - IST Submittal for V'alves Interval 2. Revision 26 Section 4.1 FW-Refueling Water System Page 3 of 5 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I FW0033A CN-1571-1.0 B1!

2 B

Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2FW0033A CN-2571-1.0 B08 2

B Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I FW0049B CN-1571-1.0 B07 2

B Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2FW0049B CN-2571-..0 B08 2

B Yes Globe Limilorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I FW0052 CN-1571-1.0 E1O NA C

Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2FW0052 CN-2571-l.0 E1O NA C

Yes check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s)

Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 Section 4.1 FW-Refueling Water System Page 4 of 5 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD P1 Test Test Type Test Test Frequency Relief Diagram Class Cntg.

Type Type Type Description Direction Frequency Description Reqest I FW0055B CN-1571-.0 1H03 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested at None Time of Valve refueling outage 2FW0055B CN-2571-l.0 H03 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested at None Time of Valve refueling outage I FW0056 CN-1571-1.0 H02 2

C Yes 2FW0056 CN-2571-1.0 H02 2

C Yes Check Self Actuated CIV-FW-O No Check Self Actuated CN-FW-01 No PS Partial-Stroke Exercise Closed to Open Valve FS Full-Stroke Exercise Open to Closed Valve to Safety Position(s)

PS Partial-Stroke Exercise Closed to Open Valve FS Full-Stroke Exercise Open to Closed Valve to Safety Position(s)

CM Condition CN-GRV-04 Monitoring 0

Tested once None quarterly CM Condition CN-GRV-04 Monitoring 0

Tested once None quarterly Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 Section 4.1 FW-Refueling Water System Page5 of 5 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IA

- Instrument Air Lock System 1 IACV5340 CN-1499-1A 1.01 2

AC Yes Check SelfActuated CN-IA-0!

No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 21ACV5340 CN-2499-IAI.01 2

AC Yes Check SelffActuated CN-IA-01 No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage IlACV5350 CN-1499-1AI.01 2

AC Yes Check SelfActuated CN--IA-01 No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 21ACV5350 CN-2499-1AI.01 2

AC Yes Check Self Actuated CN-IA-01 No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage IIACV5360 CN-1499-IA I.01 2

AC Yes Check SelfActuated CN-I, -0!

No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 21ACV5360 CN-2499-1AI.0 2

AC Yes Check Self Actuated CN-IA,-01 No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 Section 4.1 IA-Instrument Air Lock System Page I of 6 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IlACV5370 CN-1499-1AI.01 2

AC Yes Check Self Actuated CN-IA-01 No LU Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 21ACV5370 CN-2499-1AI.A1 2

AC Yes Check Self Actuated CN-IA-01 No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 11ACV5380 CN-1499-1A 1.0!

2 AC Yes Check Self Actuated CN-IA-01 No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 21ACV5380 CN-2499-1AI.01 2

AC Yes Check SelfActuated CN-IA-01 No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 1IACV5390 CN-1499-oAI.A1 2

AC Yes Check SelffActuated CN-IA-01 No I.

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 21ACV5390 CN-2499-IAI.01 2

AC Yes Check SelfActuated CN-IA-0!

No LU Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Cataw'ba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 Section 4. 1 JA-Instrument Air Lock System Page 2 of 6 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I IASV5080 CN-1499-IA1.01 2

A4 Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage Pi Verify the Valve Closed to Open RF Tested at None Remote Position refueling Indication outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 21ASV5080 CN-2499-1OI 2

A Yes Globe Solenoid None Yes SFr Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage PI Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST SubmillaI for Valves Interval 2, Revision 26 Section 4.1 IA-Instrument Air Lock System Page 3 of 6 (10/31/02)

Valve Flow ASME Valve Active Valve Actuator JOD P1 Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Rcqest IIASV5160 CN-1499-IA1.01 2

A Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed O

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage P1 Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 21ASV5160 CN-2499-i.01 2

A Yes Globe Solenoid None Yes SF1 Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage P1 Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Caiawiba Nuclear Station - 1S7 'Submittal for'alvres Interval 2, Revision 26 Section 4. 1 14-Instrument Air Lock System Page 4 of 6 (10/31/02)

Valve Flow ASNIE Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I IASV5400 CN-1499-IA1.01 2

A Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage PI Verify the Valve Open to Closed 2Y Tested once None Remote Position every two Indication years LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 21ASV5400 CN-2499-IAI.0/

2 A

Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage P1 Verify the Valve Open to Closed 2Y Tested once None Remote Position every two Indication years U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 1A-Instrument Air Lock System Page 5 of 6

Valve Flow ASNIE Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IIASV5410 CN-1499-1AI.O 2

A Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage PI Verify the Valve Open to Closed 2Y Tested once None Remote Position every two Indication years LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App.J Requirement(s) refueling outage 21ASV5410 CN-2499-1AI.01 2

A Yes Globe Solenoid None Yes SF1' Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage PI Verify the Valve Open to Closed 2Y Tested once None Remote Position every two Indication years LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 IA-Instrument Air Lock System Page 6 of 6

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest KC Component Cooling System IKC0001A CN-1573-1.o C06 3

B Yes Butterfly Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2KC0001A CN-2573-1.0 C06 3

B Yes Butterfly Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I KC0002B CN-1S73-1.0 C09 3

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

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2KC0002B CN-2573-1.0 C09 3

B Yes Butterfly Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage Cartba Nuclear Station - 1ST Submittal for Valves Interval 2, Revision 26 (10/31/02)

Section 4.1 KC-Component Cooling System Page I of 14

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqcst I KC0003A CN-1573-1.0 C06 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time-of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2KC0003A CN-2573-l.0 C06 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I KC0005 CN-1573-/.0 E04 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2KC0005 CN-2573-1.0 E04 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s)

I KC0008 CN-1573-1.0 E04 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2KC0008 CN-2573-1.0 E04 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s)

Catawba Nuclear Station - IST Submittal for Valves Interval 2 Revision 26 (10/31/02)

Section 4.1 KC-Component Cooling System Page 2 of 14

Valve Flow ASME Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KCOOI I CN-1573-I.0 E10 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2KC001I CN-2573-1.0 Ell 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s)

IKCOO14 CN-1573-1.0 Ell 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2KC0014 CN-2573-1.0 Ell 3

C Yes Check SelfActuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s)

I KC0018B CN-1573-1.0 C09 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2KC0018B CN-2573-1.0 C099 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage Catawiba Nuclear Station - IST Subminttal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 KC-Component Cooling System Page 3 of 14

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0047 CN-1573-1.5 H04 2

AC Yes Check SelfActuated CN-KC-03 No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2KC0047 CN-2573-1.5 H04 2

AC Yes Check Self Actuated CN-KC-03 No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I KC0050A CN-1573-i.)

K07 3

B Yes Butterfly Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2 KC0050A (N-2573-1.0 K07 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I KC0053B CN-1573-1.0 K08 3

B Yes Butterfly Limnitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2KC0053B CN-2573-.

g)K08 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage Catawba Nuclear Station - 1ST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 KC-Component Cooling System Page 4 of 14

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0056A CN-1573-2.o E03 3

B Yes Butterfly Lintiforque None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Closed to Open RF Tested at None Time of Valve refueling outage 2KC0056A CN-2573-2.0 E03 3

B Yes Butterfly Limilorque None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Closed to Open RF Tested at None Time of Valve refueling outage I KC0057A CN-1573-2.0 103 B

Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open and Timed SF1 Failed to Safe Position Closed to Open and Timed 0

Tested once None quarterly RF Tested at None refueling outage 2KC0057A CN-2573-20 J03 3

B Yes Globe Air None Ves SF1' Failed to Safe Position Closed to Open and Timed SFT Failed to Safe Position Closed to Open and Timed 0

Tested once None quarterly RF Tested at None refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 KC-Component Cooling System Page 5 of 14

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0081 B CN-1573-2. i E03 3

B Yes Butterfly Limitorque None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Closed to Open RF Tested at None Time of Valve refueling outage 2 KC0081 B CN-2573-2.l E03 3

B Yes Butterfly Linilorque None Yes ST Measure Full-Stroke Closed to Open 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Closed to Open RF Tested at None Time of Valve refueling outage I KC0082B CN-1573-2. I J03 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open and Timed SFT Failed to Safe Position Closed to Open and Timed 0

Tested once None quarterly RF Tested at None refueling outage 2KC0082B CN-2573-2.1 J03 3

B Yes Globe Air None Yes SFT Failed to Safe Position Closed to Open and Timed SFT Failed to Safe Position Closed to Open and Timed 0

Tested once None quarterly RF Tested at None refueling outage Catawba Nuclear Station -IST Submittal for Valves Interval 2, Revision 26 (10131*/2)

Section 4.1 KC-Component Cooling System Page 6 of 14

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0228B (C-1573-1.0 L08 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2KC0228B CN-2573-l1. 0 K08 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I KC0230A C'N-1573-l0 L07 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2KC0230A CN-2573-1.0 K07 3

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage I KC0279 CN-1573-1.3 K05 2

AC Yes Check SelffActuated CN-KC-03 No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2KC0279 CN-2573-1.3 K05 2

AC Yes Check SelfActuated CN-KC-03 No LU Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - ST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 KC-Component Cooling System Page 7 of 14

Valve Flow ASME Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0280 CA'-1573-1.3 E02 2

C Yes 2 KC0280 CN-2573-1.3 E02 2

C Yes Check Self Actuated Check Self Actuated None No None No NTS See Program Document NA or Fail Safe Pos NT

- Section 4.5 NTS See Program Document NA or Fail Safe Pos NT

- Section 4.5 No Test None Required No Test None Required I KC0281 CN-1573-1.3 K3 2

C Yes Relief Self Actuated None No RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV-Ol.02.03 Test valve per aM-I schedUle 2KC0281 CN-2573-1.3 K3 2

C Yes Relief Self Actuated None No RV Safety and Relief Valve Closed to Open RV Test relief' CN-GRV-01.02.03 Test valve per OM-I schedule I KC0305B CN-1573-1.3 D13 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage 2KC0305B CN-2573-1.3 D13 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage Cataw-ba Nuclear Station - 1ST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 KC-Component Cooling System Page 8 of 14

Valve Flow ASME Valve Active Valve Actuator JOD P1 Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0315B CN-1573-1I.3 L12 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage 2KC0315B CN-2573-1.3 L12 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage I KC0320A CN-1573-1.3 BIO 2

B Yes Gate Rotork CN-KC-O1 Yes ST Measure Full-Stroke Open to Closed CS Tested at cold None Time of Valve shutdown ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage 2KC0320A CN-2573-1.3 BIO 2

B Yes Gate Rotork CN-KC-Ol Yes ST Measure Full-Stroke Open to Closed CS Tested at cold None Time of Valve shutdown ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage Catawba Nuclear Station -IST Submittal for Valves Section 4. /

Interval 2. Revision 26 (10/31/02)

KC-Component Cooling System Page 9 of 14

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0322 CN-1573-1.3 B8 2

C Yes Check SelfActuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required 2KC0322 CN-2573-1.3 B8 2

C Yes Check Self Actuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required I KC0332B CN-1573-1.3 E02 2

B Yes Gate Rotork CN-KC-O1 Yes ST Measure Full-Stroke Open to Closed CS Tested at cold None Time of Valve shutdown ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Salle Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage 2KC0332B CN-2573-1.3 E0t2 2

B Yes Gate Rotork (N-K('-I)l Yes ST Measure Full-Stroke Open to Closed CS Tested at cold None Time of Valve shutdown ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Sale Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/o2)

Section 4. 1 KC-Component Cooling System Page 10 of 14

Valve Flow ASME Valve Active Valve Actuator JOD P1 Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0333A CN-1573-I.3 G02 2

B Yes Gate Roiork CN-KC-OJ Yes ST Measure Full-Stroke Open to Closed CS Tested at cold None Time of Valve shutdown ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage 2KC0333A CN-2573-1.3 GO2 2

B Yes Gate Rotork CN-KC-OI Yes ST Measure Full-Stroke Open to Closed CS Tested at cold None Time of Valve shutdown ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage I KC0338B C'-1573-I.3 DI2 2

Bi Yes Gate Rolork CN-KC-02 Yes ST Measure Full-Stroke Time of Valve ST Measure Full-Stroke Time of Valve Open to Closed Open to Closed LTNW Qualified Seal System NA or Fail Safe Pos Leak Rate Test (CNS Only)

CS Tested at cold None shutdown RF Tested at None refueling RF outage Tested at None refueling outage 2KC0338B CAN-2573-t.3 DI2 2

B Yes Gate Rotork CN-KC-02 Yes ST Measure Full-Stroke Time of Valve ST Measure Full-Stroke Time of Valve Open to Closed Open to Closed LTNW Qualified Seal System NA or Fail Safe Pos Leak Rate Test (CNS Only)

CS Tested at cold None shutdown RF Tested at None refueling outage RF Tested at None refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 KC-Component Cooling System Page 11 of 14

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0340 CN-1573-l.3 El2 2

AC Yes Check SelfActuated CN-KC-03 No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2KC0340 CN-2573-1.3 El2 2

AC Yes Check Self Actuated CN-KC-03 No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I KC0424B CN-1573-1.3 LOS 2

B Yes Gate Roaork CN-KC-02 Yes ST Measure Full-Stroke Open to Closed CS Tested at cold None Time of Valve shutdown ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage 2KC0424B CN-2573-1.3 LOS 2

B Yes Gate Rotork CN-KC-02 Yes ST Measure Full-Stroke Time of Valve ST Measure Full-Strokc Time of Valve Open to Closed Open to Closed LTNW Qualified Seal System NA or Fail Safe Pos Leak Rate Test (CNS Only)

CS Tested at cold None shutdown RF Tested at None refueling outage RF Tested at None refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 (10/31/02)

Section 4.)1 KC-Component Cooling System Page 12 of 14

Valve Flow ASME Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0425A CN-1573-1.3 L06 2

B Yes Gate Rotork CN-KC-02 Yes ST Measure Full-Stroke Open to Closed CS Tested at cold None Time of Valve shutdown ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Sate Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage 2KC0425A CN-2573-1.3 L06 2

B Yes Gate Rotork CN-KC-02 Yes ST Measure Full-Stroke Open to Closed CS Tested at cold None Time of Valve shutdown ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage I KC0429B CA-15 73-1.5 H02 2

A Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2KC0429B CN-2573-1.5 H03 2

A Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LI Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 KC-Component Cooling System Page 13 of 14

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I KC0430A CN-1573-1.5 J03 2

A Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2KC0430A CN-2573-1.5 J03 2

A Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I KCCO37A CNI-1573-l.o C03 3

B Yes Globe Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2KCCO37A CN:-2573-l.o C03 3

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

Q Tested once None Time of Valve quarterly I KCC040B CN-1573-/.(o CI/o 3

B Yes Globe Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2KCC040B CN-2573-1.0 C/O 3

B Yes Globe Rotork None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly Cataiwba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.l1 KC-Component Cooling System Page 14 of 14

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest KD " Diesel Generator Engine Cooling Water System I KD0006 CN-1609-1.0 JlJ/

3 C

Yes Check

&'lfctualed CN-KD-O0 No FS Full-Stroke Exercise Closed to Open NI Tested once None Valve to Safety monthly Position(s)

FS Full-Stroke Exercise Both (Stroke Test)

SD Disassem one None Valve to Safety vlv per grp ca.

Position(s)

RFO 2KD0006 CN-2609-1.0 JI/0 3

C Yes Check Self.Actuated CN-KD-0l No FS Full-Stroke Exercise Closed to Open M

Tested once None Valve to Safety monthly Position(s)

FS Full-Stroke Exercise Both (Stroke Test)

SD Disassem one None Valve to Safety vlv per grp ca.

Position(s)

RFO IKDO021 CN-/609-l/.

ElfO 3

C Yes Check Self Actuated CN-KD-O1 No FS Full-Stroke Exercise Closed to Open NI Tested once None Valve to Safety monthly Position(s)

FS Full-Stroke Exercise Both (Stroke Test)

SID Disassemn one None Valve to Safety vlv per grp, ea.

Position(s)

RFO 2KD0021 C.V-2609-l.0 El0 3

C Yes Check SelfActuated CN-KD-Ol No FS Full-Stroke Exercise Closed to Open M

Tested once None Valve to Safety monthly Position(s)

FS Full-Stroke Exercise Both (Stroke Test)

SD Disassem one None Valve to Safety vlv per grp ea.

Position(s)

RFO Catawba Nuclear Station - 1ST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 KD-Diesel Generator Engine Cooling Water System Page)I of I

Valve Flow ASME Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest KF " Spent Fuel Cooling System IKFOIO B CN-1570-1.0 H13 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2KFOIOIB

'N-2570-l.( 0 1113 2

B Yes Plug Motor-Other None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage IKFO103A C'-1370-l.o.

H12 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage 2KFO103A CN-2570-1.0 H12 2

B Yes Plug Motor-Other None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31M12)

Section 4. 1 KF-Spent Fuel Cooling System Page I of I

Valve Flow ASME Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest LD

- Diesel Gen. Lube Oil System I LD0002 CN-1609-2.0 F09 2LD0002 CN-2609-2O F09 3

C Yes 3

C Yes Relief Self Actuated Relief Self Actuated None No None No RV Safety and Relief Valve Closed to Open Test RV Safety and Relief Valve Closed to Open Test RV Test relief CN-GRV-01,02.03 valve per OM-1 schedule RV Test relief CN-GRV-01,02.03 valve per OM-l schedule I LD0017 CN-1609-2.0 K09 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2LD0017 CN-2609-2.0 K09 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s)

ILD0018 CN-1609-2.0 J06 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2LD0018 CN-2609-2.0

.J06 3

C Yes Check SelfActuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s)

Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (l0/31032)

Section 4. 1 LD-Diesel Gen. Lube Oil System Page I of 4

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I LD0032 CN-1609-22 F09 2LD0032 CN-2609-2.2 F09 3

C Yes C

Yes Relief Self Actuated Relief Self Actuated None No None No RV Safety and Relief Valve Closed to Open Test RV Safety and Relief Valve Closed to Open Test RV Test relief CN-GRV-01,02,03 valve per OM-I schedule RV Test relief CN-GRV-01,02,03 valve per OM-I schedule I LD0047 CN-1609-2.2 K05 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2LD0047 CN-2609-2.2 KO05 3

C Yes Check SelfActuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s)

I LD0048 CN-1609-2.2 J06 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Tested once None Valve to Safety quarterly Position(s) 2LD0048 CN-2609-2.2 J06 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Both (Stroke Test) 0 Valve to Safety Position(s)

Tested once None quarterly Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 LD-Diesel Gen. Lube Oil System Page 2 of 4

Valve Flow ASNIE Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I LD0071 CN-1609-2.0 K06 3

C Yes Check SelfActuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2LD0071 CN-2609-2.0 K06 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s)

I LD0072 CN-1609-2.0 J06 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

lTestcd once None Valve to Safety quarterly Position(s) 2LD0072 CN-2609-2.0 J06 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s)

I LD0078 CN-1609-2.2 K06 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2LD0078 CN-2609-2.2 K06 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s)

Catawiba Nuclear Station - ISTSubmittal for Valves Interval 2. Revision 26 (101/31/2)

Section 4.1 LD-Diesel Gen. Lube Oil System Page 3 of 4

Valve Flow ASME Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I LD0079 CN-1609-2.2 J06 3

C Yes Check Self Actuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s) 2LD0079 CN-2609-2.2 J06 3

C Yes Check Self Aciuated None No FS Full-Stroke Exercise Closed to Open 0

Tested once None Valve to Safety quarterly Position(s)

Catawba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 (10/31/02)

Section 4.1 LD-Diesel Gen. Lube Oil System Page 4 of 4

Valve Flow ASME Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest MI

- Radiation System IMIMV6470 CN-1499.03-09.

KIO 2

A Yes Needle Manual None No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2MIMV6470 CN-1499.03-09.

KIO 2

A Yes Needle Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage IMIMV6471 CN-1499.03-09.

KIO 2

A Yes Needle Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2MIMV6471 CN-1499.03-09.

KIO 2

A Yes Needle Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I MIMV6480 CN-1499.03-09.

KIO 2

A Yes Needle Manual None No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2MIMV6480 CN-1499.03-09.

KIO 2

A Yes Needle Manual None No LJ Leak-Rate Test Valve to Accident Direction RF App J Requirement(s)

Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 MI-Radiation System Page I of 6 None Tested at refueling outage

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IMIMV6481 CN-1499.03-09. KIO 2

A Yes Needle Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2MIMV6481 CN-1499.03-09. KIO 2

A Yes Needle Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I MIMV6490 CN-1499.03-09.

KIO 2

A Yes Needle Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2MIMV6490 CN-1499.03-09. KIO 2

A Yes Needle Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage IMIMV6491 CN-1499.03-09. K IO 2

A Yes Needle Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2MIMV6491 CN-1499.03-09. KIO 2

A Yes Needle Manual None No LU Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2 Revision 26 (10/31/02)

Section 4. 1 Ml-Radiation System Page 2 of 6

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I M ISV5230 CN-1499-MI19 2

A Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage P]

Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2MISV5230 CN-2499-MH19 2

4 Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage PI Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 MI-Radiation System Page 3 of 6

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I MISV5231 CN-1499-MI19 2

A4 Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage PI Verify the Valve Open to Closed RF Tested at None Remote Position refueling indication outage LU Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2M1SV5231 CN-2499-1119 2

4 Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage PI Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage (Ctawba Nuclear Siation -IST Submittal for V'alves Interval 2, Revision 26 (10/31/02)

Section 4.1 MI-Radiation System Page 4 of 6

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I MISV5232 CN-1499-M19 2

A Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage P!

Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2M1SV5232 CA-2499-MII19 2

A Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage Pi Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 (10/31/02)

Section 4.1 MI-Radiation System Page 5 of 6

Valve Flow ASME Valve Active Valve Actuator JOD P1 Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IMISV5233 CN-1499411l9 2

A Yes Globe Solenoid None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage Pl Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2MISV5233 CN-2499-M119 2

A Yes Globe Solenoid None Yes SFr Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage PI Verify the Valve Open to Closed RF Tested at None Remote Position refueling Indication outage U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 MI-Radiation System Page 6 of 6

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest NB

- Boron Recycle System INBO260B CN-1556-2.o G04 2

A Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App)J Requirement(s) refueling outage 2NB0260B CN-2536-2.o G04 2

A Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App)I Requirement(s) refueling outage I NB0262 CN-1556-2.0 G06 2

AC Yes Check Self Actuated CN-NB-OI No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App)J Requirement(s) refueling outage 2NB0262 CN-2556-2.O G06 2

AC Yes Check Self Actuated CN-NB-Ol No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 NB-Boron Recycle System Page I of I

Valve Flow ASME Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction FrequencyIDescription Reqest NC

- Reactor Coolant System INCOOOI CN-1553-l.l K03 I

C Yes Relief Self Actuated None No RV Safety and Relief Valve NA or Fail Safe Pos RV Test relief CN-GRV-0 1,02,03 Test valve per aM-I schedule 2NCOOOI CN-2553-1.I/

K03 I

C Yes Relief Self Actuated None No RV Safety and Relief Valve NA or Fail Safe Pos RV Test relief CN-GRV-0I,02,03 Test valve per OM-I schedule I NCO002 CN-1553-1. I K04 I

C Yes 2NC0002 CN-2553-1.1 K04 I

C Yes INCO003 CN-1553-1. I K06 I

c Yes 2NC0003 CN-2553- /. I K06 I

C Yes Relief Self Actuated Relief Self Actuated Relief Self Actuated Relief Self Actuated None No RV Safety and Relief Valve Closed to Open RV Test relief CN-GJRV-0l.02.03 Test valve per OM-l schedule None No None No None No RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV-01,02,03 Test valve per OM-!

schedule RV Safety and Relief Valve NA or Fail Safe Pos RV Test relief CN-GRV-01.02,03 Test valve per OM-I schedule RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV.01.02,03 Test valve per OM-I schedule Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 NC-Reactor Coolant System Page I of 7

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I NCO031 B CN-1553-1. I F04 I

B Yes Gate Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly 2NC0031 B CN-2533. I. i F04 I

B Yes Gate Liminorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly INCO032B CN-1533-1./

G04 I

B Yes Globe Air CN-NC-02 Yes SFT Failed to Safe Position Both (Stroke Test)

CS Tested at cold None and Timed shutdown 2NC0032B CN-2553-1. I G04 I

B Yes Globe Air CN-NC-02 Yes SFT Failed to Safe Position Both (Stroke Test)

CS Tested at cold None and Timed shutdown I NCO033A CN-1553-1. I F03 B

Yes Gate Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly 2NC0033A CN-2553-l.

F03 I

B Yes Gate Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly I NCO034A CN-1553-i.I G03 B

Yes Globe Air CN-NC-02 Yes SFT Failed to Safe Position Both (Stroke Test)

CS Tested at cold None and Timed shutdown 2NC0034A CN-2?53-/. I G03 I

B Yes Globe Air CN-NC-02 Yes SFT Failed to Safe Position Both (Stroke Test)

CS Tested at cold None and Timed shutdown Catawba Nuclear Station - IST Submittal for Valves Interval 2 Revision 26 (10/31/02)

Section 4.1 NC-Reactor Coolant System Page 2 of 7

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I NCO035B CN-1553-1. /

1F02 I

B Yes Gate Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly 2NC0035B CN-2553-1./

FF02 I

B Yes Gate Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly I NCO036B CN-1553-I.1 G02 I

B Yes Globe Air CN-NC-02 Yes SFT Failed to Safe Position Both (Stroke Test)

CS Tested at cold None and Timed shutdown 2NC0036B CN-2553-l.1 G02 I

B Yes Globe Air CN-NC-02 Yes SFT Failed to Safe Position Both (Stroke Test)

CS Tested at cold None and Timed shutdown INCO053B CN-IJ53-1.i K/I 2

A Yes Globe Limit orque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NC0053B CN-2553-I. I K/I 2

A Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 NC-Reactor Coolant System Page 3 of 7

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I NCO054A CN-1553-1. I K09 2

A4 Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NC0054A CN-2553-1.1 K09 2

A Yes Globe Limitorque None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LI Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I NCO056B CN-1553-1. I 113 2

B Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LTNW Qualified Seal System NA or Fail Safe Pos RF Tested at None Leak Rate Test (CNS refueling Only) outage Catawba Nuclear Station - IST Submittal for Valves Interval 2 Revision 26 (10/31/02)

Section 4.1 NC-Reactor Coolant System Page 4 of 7 2NC0056B CN-2553-1. I 113 2

B Yes Gate Rotork None Yes

Valve Flow ASME Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I NC0057 CN-1553-l. 1 112 2

AC Yes Check SelfActuated CN-NC-OI No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NC0057 CN-2553-1.1 112 2

AC Yes Check Self Actuated CN-NC-Ol No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I NCO141 CN-1553-1.3 J08 2

A No Gate Manual None No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) retleling outage 2NC0141 CN-2553-1.3 J08 2

A No Gate Manual ANone No U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 1NC0142 CN-1553-1.3 K08 2

A No Gate Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NCO142 CN-2553-l.3 K08 2

A No Gate Manual None No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 NC-Reactor Coolant System Page 5 of 7

Valve Flow ASME Valve Active Valve Actuator JOD P1 Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest INCO195B CN-w153-I.3 D07 2

A Yes Gale Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NC0195B CN-2553-1.3 E07 2

A Yes Gale Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage INCO196A CN-1553-i.3 D07 2

A Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LIJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NC0196A CN-2553-1.3 D07 2

A Yes Gate Rotork

Non, Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Cataiwba Nuclear Station.- IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 NC-Reactor Coolant System Page 6 of 7

Valve Flow ASME Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I NC0250A CN-1553-l.i L07 I

B Yes Globe Limitorque CN-NC-03 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown 2NC0250A CN-2553-1. I L07

/

B Yes Globe Limitorque CN-NC-03 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown I NC0251B CN-1553-1.1 L06 8B Yes Globe Limilorque CN-NC-03 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown 2NC0251 B CN-2553-1. I L07 I

B Yes Globe Limitorque CN-NC-03 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown I NC0252B CN-1553-1. 1 K07 B

Yes Globe Limilorque CN-NC-03 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown 2NC0252B CN-2553-/. I K07 B

Yes Globe Limilorque CN-NC-03 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown I NC0253A CN-1553-1. I 1(06 I

B Yes Globe Limilorque CN-NC-03 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown 2NC0253A CN-2553-1.1 K07 I

B Yes Globe Limitorque CN-NC-03 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown

('ulaiba Nuclear Saliot - IST Submittal for V alves Interval 2. Revision 26 (10/31/02)

Section 4.1 NC-Reactor Coolant System Page 7 of 7

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest ND

- Residual Heat Removal System INDOOOIB CN-1561-1.0 L13 I

A Yes Gale Rotork CN-ND-01 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section X1 shutdown Requirement(s) 2ND0001 B CN-2561-1.0 L13 I

A Yes Gale Rotork CN-ND-OI Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section X1 shutdown Requirement(s)

IND0002A CA-1561-I.0 J13 I

A Yes Gate Rotork CN-ND-O0 No ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section X1 shutdown Requirement(s) 2ND0002A CN-2561-1.0 J13 I

A Yes Gate Rotork CN-ND-OI No ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section X1 shutdown Requirement(s)

Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 ND-Residual Heat Removal System Page I of 8

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IND0003 CN-1561-/.0 113 2ND0003 CN-2561-1.0 113 2

C Yes Relief SelfActuated 2

C Yes Relief Self Actuated None No None No RV Safety and Relief Valve Closed to Open Test RV Safety and Relief Valve Closed to Open Test RV Test relief CN-GRV-01,02.03 valve per OM-I schedule RV Test relief CN-GRV-01,02,03 valve per OM-I schedule IND0010 CN-1561-I.O GIO 2

C Yes Check Self Actuated CN-ND-03 No PS Partial-Stroke Exercise Closed to Open 0

Tested once None Valve quarterly FS Full-Stroke Exercise Open to Closed 0

Tested once None Valve to Safety quarterly Position(s)

FS Full-Stroke Exercise Closed to Open CS Tested at cold None Valve to Safety shutdown Position(s) 2ND0010 CN-2561-1.0 GIO 2

C Yes Check Self Actuated CN-ND-03 No PS Partial-Stroke Exercise Closed to Open 0

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

Tested once None Valve to Safety quarterly Position(s)

FS Full-Stroke Exercise Closed to Open CS Tested at cold None Valve to Safety shutdown Position(s)

I ND0025A CN-1561-1.O 1E3 2

B Yes Globe Limitorque None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2ND0025A CN-2561-1.0 E13 2

B Yes Globe Limitorque None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly Catawba Nuclear Station - IST Submittal for Valves hIterval 2. Revision 26 (10/31/02)

Section 4.1 ND-Residual Heat Removal System Page 2 of 8

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I ND0026 CN-1561-1.0 G04 2

B Yes Butterfly Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2ND0026 CN-2561-1.0 G04 2

B Yes Butterfly Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly IND0027 CN-1561-1.0 J06 2

B Yes Butterfly Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly 2ND0027 CN-2561-1.0 J06 2

B Yes Butterfly Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly IND0028A CN-1561-1.0 H04 2

B Yes Gate Rotork CN-ND-05 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown 2ND0028A CN-2561-1.0 104 2

B Yes Gate Rotork CN-ND-05 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown IND0031 CN-lI61-1.O G02 2

C Yes Relief Self Actuated None No RV Safety and Relief Valve Closed to Open Test RV Test relief CN-GRV-01,02.03 valve per OM-l schedule 2ND0031 CN-2361-1.0 G02 2

C Yes Relief SelfActuated None No RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV-01,02.03 Test valve per OM-l schedule Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 ND-Residual Heat Removal System Page 3 of 8

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I ND0032A CN-1361-1.0 F03 2

B Yes Gate Rotork CN-ND-04 Yes ST Measure Full-Stroke Both (Stroke Test)

CS Tested at cold None Time of Valve shutdown 2ND0032A CN-2561-1.0 E03 2

B Yes Gate Rotork CN-ND-04 Yes ST Measure Full-Stroke Both (Stroke Test)

CS Tested at cold None Time of Valve shutdown IND0035 CN-1561-I.O D02 2ND0035 CN-2561-1.0 D02 2

2 C

Yes Relief Self Aciuated C

Yes Relief Self Actuated None No None No RV Safety and Relief Valve Closed to Open Test RV Safety and Relief Valve Closed to Open Test RV Test relief CN-GRV-01.02,03 valve per OM-l schedule RV Test relief CN-GRV-01,02,03 valve per OM-1 schedule IND0036B C'N-1561-l.l LI3 I3A/

Yes Gate Rotork CN-ND-02 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section X1 shutdown Requirement(s) 2ND0036B CN-2561-1.1 L13

/1

.4 Yes Gate Rotork CN-ND-02 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section XI shutdown Requirement(s)

Catawiba Nuclear Station -IST Submittal for Valves Interval 2 Revision 26 (10/31/02)

Section 4.1 ND-Residual Heat Removal System Page 4 of 8

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IND0037A CN-1561-1.

J13 I

A Yes Gate Rotork CN-ND-02 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section Xi shutdown Requirement(s) 2ND0037A CN-2561-1. I J13 I

A Yes Gate Rotork CN-ND-02 Yes ST Measure Full-Stroke Closed to Open CS Tested at cold None Time of Valve shutdown LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section X1 shutdown Requirement(s)

IND0038 CN-161-1.) 113 2

C Yes Relief Self Actuated None No RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV-OI.02,03 Test valve per OM-1 schedule 2ND0038 CN-256/-I.1 113 2

C Yes Relief SelfActuated None No RV Safety and Relief Valve Closed to Open RV Test relief CN-GRV-01,02,03 Test valve per OM-l schedule Catawrba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 ND-Residual Heat Removal System Page5 of 8

Valve Flow ASME Valve Active Valve Actuator JOD P!

Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest 1 ND0044 CN-1561-1.

0GIO 2

C Yes Check Self Actuated CN-ND-03 No PS Partial-Stroke Exercise Closed to Open 0

Tested once None Valve quarterly FS Full-Stroke Exercise Open to Closed 0

Tested once None Valve to Safety quarterly Position(s)

FS Full-Stroke Exercise Closed to Open CS Tested at cold None Valve to Safety shutdown Position(s) 2ND0044 CN-2561-1.1 GIO 2

C Yes Check Self Actuated CN-ND-03 No PS Partial-Stroke Exercise Closed to Open 0

Tested once None Valve quarterly FS Full-Stroke Exercise Open to Closed 0

Tested once None Valve to Safety quarterly Position(s)

FS Full-Stroke Exercise Closed to Open CS Tested at cold None Valve to Safety shutdown Position(s)

IND0059B CN-1561-1.1 E13 2

B Yes Globe Limitorque None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly 2ND0059B CN-2561-1. I E13 2

B Yes Globe Limitorque None Yes ST Measure Full-Stroke Both (Stroke Test) 0 Tested once None Time of Valve quarterly IND0060 CN-1361-1.1 G04 2

B Yes Butterfly Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly 2ND0060 CN-256 1-1.

G04 2

B Yes Butterfly Air None Yes SFT Failed to Safe Position Closed to Open 0

Tested once None and Timed quarterly Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 ND-Residual Heat Removal System Page 6 of 8

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I ND0061 CN-1561-1. I J06 2

B Yes Butterfly Air None Yes SnI Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly 2ND0061 CN-2561-1. I J06 2

B Yes Butterfly Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly IND0064 CN-1561-1.1 H02 2

C Yes 2ND0064 CN-2561-1.1 H02 2

C Yes Relief SelfActuated Relief SelfActuated None No None No RV Safety and Relief Valve Closed to Open Test RV Safety and Relief Valve Closed to Open Test RV Test relief CN-GRV-OI.02,03 valve per OM-I schedule RV Test relief CN-GRV-01.02.03 valve per OM-I schedule IND0065B CN-1561-1.1 E03 2

B Yes Gate Rotork CN-ND-04 Yes ST Measure Full-Stroke Both (Stroke Tcst)

CS Tested at cold None Time of Valve shutdown 2ND0065B CN-2361-1.1 E03 2

B Yes Gate Rotork CN-ND-04 Yes ST Measure Full-Stroke Both (Stroke Test)

CS Tested at cold None Time of Valve shutdown Catawba Nuclear Station - IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4.1 ND-Residual Heat Removal System Page 7 of 8

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest IND0116 CN-1561-1.0 K12 2

C Yes Check Self Actuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section Xi shutdown Requirement(s) 2ND0116 CN-2561-1.0 K12 2

C Yes Check Self Actuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section Xi shutdown Requirement(s)

IND0117 CN-1561-1.1 K12 2

C Yes Check Self Actuated None No NTS See Program Document NA or Fail Safe Pos NT No Test None

- Section 4.5 Required LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section X1 shutdown Requirement(s) 2NDOI17

('W-2561-1.0 K12 2

C Yes Check Se, /fActuated None No NIS See Program Document NA or Fail Salfe Ios NT No Test None

-Section 4.5 Required LT Leak-Rate Test Valve to Accident Direction CS Tested at cold None Section X1 shutdown Requirement(s)

Calmrba Nuclear Station - IST Stubmintal for Valves Interval 2 Revision 26 (10/31/02)

Section 4.1 ND-Residual Heat Removal System Page 8 of 8

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest NF - Ice Condenser Refrigeration System INF0228A CN-1358-2.o H14 2

A Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed retueling outage U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NF0228A CN-2358-2.0 H14 2

A Yes Gate Air None Yes SFT Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF Tested at None and Timed refueling outage LI Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I NF0229 CN-1558-2.0 F14 2

AC Yes Check Self Actuated CN-NF-OI No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NF0229 CN-2558-2.0 Ff4 2

AC Yes Check Self Actuated CN-NF-O0 No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 (10/31/02)

Section 4. 1 NF-Ice Condenser Refrigeration System Page)I of 3

Valve Flow ASME Valve Active Valve Actuator JOD PI Test Test Type Test Test Frequency Relief Diagram Class CaIg.

Type Type Type Description Direction Frequency Description Reqest I NF0233 B CN-1538-2. 0 LI0 2

A Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage UI Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NF0233B CN-2558-2.0 LIO 2

A Yes Gate Rotork None Yes ST Measure Full-Stroke Open to Closed 0

Tested once None Time of Valve quarterly ST Measure Full-Stroke Open to Closed RF Tested at None Time of Valve refueling outage LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage I N F0234A CN-1558-2.0 L12 2

A Yes Gate Air None Yes SFf Failed to Safe Position Open to Closed 0

Tested once None and Timed quarterly SFT Failed to Safe Position Open to Closed RF rested at None and Timed refueling outage U

Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage SFT Failed to Safe Position Open to Closed and Timed SIT Failed to Safe Position Open to Closed and Timed UJ Leak-Rate Test Valve to Accident Direction App J Requirement(s) 0 Tested once None quarterly RF Tested at None refueling outage RF Tested at None refueling outage Catawba Nuclear Station -IST Submittal for Valves Interval 2. Revision 26 (10/311/2)

Section 4. 1 NF-Ice Condenser Refrigeration System Page 2 of 3 2NF0234A CN-2558-2.0 L12 2

A Yes Gate Air None Yes

Valve Flow ASME Valve Active Valve Actuator JOD Pi Test Test Type Test Test Frequency Relief Diagram Class Catg.

Type Type Type Description Direction Frequency Description Reqest I NF0235 CN-1558.2.0 KIO 2

AC Yes Check Self Actuated CN-NF-O0 No IJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage 2NF0235 CN-2558-2.0 KIO 2

AC Yes Check Self Actuated CN-NF-01 No LJ Leak-Rate Test Valve to Accident Direction RF Tested at None App J Requirement(s) refueling outage Catawba Nuclear Station - IST Submittal for Valves Interval 2, Revision 26 (10/31/02)

Section 4. 1 NF-Ice Condenser Refrigeration System Page 3 of 3

ML030290082

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2.0 REFERENCES

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9.0 ENCLOSURES

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