L-2004-043, Submittal of Fourth 10-year Testing Interval IST Program, Revision 0, Beginning February 22, 2004 for Turkey Point Unit 3 and April 15, 2004 for Turkey Point Unit 4

Submittal of Fourth 10-year Testing Interval IST Program, Revision 0, Beginning February 22, 2004 for Turkey Point Unit 3 and April 15, 2004 for Turkey Point Unit 4

ML040790074
Person / Time
Site:	Turkey Point
Issue date:	03/11/2004
From:	Jones T Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2004-043
Download: ML040790074 (326)

Text

esa~, ,A I-l yBaw FPL L-2004-043 10 CFR 50.55a(f)

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Fourth-10 Year Interval Inservice Testing Program The Turkey Point Units 3 and 4 Inservice Testing (IST) program has been revised to meet the requirements of the ASME OM Code for the Fourth 10-year testing interval.

This letter submits to Nuclear Regulatory Commission in Attachment 1 the Fourth 10-year testing interval IST program, Revision 0, beginning February 22, 2004 for Turkey Point Unit 3 and April 15, 2004 for Turkey Point Unit 4. The IST program includes the associated pump and valve relief requests, which have been previously submitted to NRC for approval under FPL letter L-2003-316, dated January 6, 2003. provides a current set of drawings to assist in pump and valve identification.

If you have any questions please contact Walter Parker at (305) 246-6632.

Sincerely, Terry es Vice President Turkey Point Nuclear Plant Attachments cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company

ATTACHMENT 1 L-2004-043

IST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear Powi'er Plant Turkey Point Nuclear Plant Units 3 & 4 Inservice Testing Program Fourth Ten Year Interval Revision 0 Commercial Service Dates:

Unit 3 - 12/14/72 Unit 4- 09/14/73 Florida Power and Light Company Turkey Point Nuclear Power Plant P.O. Box 3088 Florida City, Florida 33034 APPROVALS:

Prepared By: _ _ _ _ _ Date: 2--Z5;-of rrsT Coordinator Approved By: Datc: 2.l7 1,7I0 PT 7inrinf\O eratior inager Approved By: _______ ___A__ Date: -IL I I0 inager Revision Date: 02/11/04 Page I

1ST ProgramPlan FloridaPower and Light Company Turkey Point Nuclear Power Plant REVISION LOG Effective Revision Description Prepared: Date Approved: Date Date IST Engineering Coordinator Operations Support Manager 4 th Ten Year Interval, Revision 0 Submittal to NRC. In compliance with the 1998 Edition through 2000 Addenda except where relief is 21 requested. For check valve condition monitoring, this submittal is in compliance with the 1995 Edition through 1996 Addenda, Appendix II and associated Federal Register modifications.

t t t 4

I I II _

Revision Date: 02/11/04 Page 2

1ST Program Plan FloridaPower andLight Company Turkey Point Nuclear Power Plant TABLE OF CONTENTS SECTION

1.0 INTRODUCTION

1.1 Purpose 1.2 Scope 2.0 INSERVICE TESTING PLAN FOR PUMPS 2.1 Pump Inservice Testing Plan Description 2.2 Pump Plan Table Description 3.0 INSERVICE TESTING PLAN FOR VALVES 3.1 Valve Inservice Testing Plan Description 3.2 Valve Plan Table Description 4.0 ATTACHMENTS

1. System and P&ID Listing

2. Pump Relief Request Index

3. Pump Relief Requests

4. Valve Relief Request Index

5. Valve Relief Requests

6. Cold Shutdown Justification Index

7. Cold Shutdown Justifications

8. Refuel Outage Justification Index

9. Refuel Outage Justifications

10. Station Technical Position Index

11. Station Technical Positions

12. Inservice Testing Pump Table

13. Inservice Testing Valve Table Revision Date: 02/11/04 Page 3

IST Program Plan Florida Power and Light Company Turkev Point Nuclear Power Plant

1.0 INTRODUCTION

1.1 Purpose To provide requirements for the performance and administration of assessing the operational readiness of those pumps and valves whose specific functions are required to:

• Shutdown the reactor to the safe shutdown condition,

• Maintain the safe shutdown condition, or

• To mitigate the consequences of an accident.

1.2 Scope The program plan was prepared to meet the requirements of the following subsections of the American Society of Mechanical Engineers (ASME) OM Code (1998 Edition through 2000 Addenda) except for Mandatory Appendix 11 "Check Valve Condition Monitoring Program". The American Society of Mechanical Engineers (ASME) OM Code (1995 Edition through 1996 Addenda), will be used for Check Valve Condition Monitoring and will apply the modifications required in Federal Register Volume 64, No. 183 dated September 22, 1999 (see Technical Position TPv-02).

• Subsection ISTA, "General Requirements" ISTA contains the requirements directly applicable to inservice testing including the Owner's Responsibility and Records Requirements.

• Subsection ISTB, "Inser'ice Testing of Pumps in Light-Water Reactor Nuclear Power Plants" Establishes the requirements for inservice testing of pumps in light-water reactor nuclear power plants. The pumps covered are those provided with an emergency power source, that are required in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident. These pumps are either centrifugal or positive displacement type pumps.

• Subsection ISTC, "Inservice Testing of V'alves in Light-Water Reactor ANu1clear PosterPlants "

Establishes the requirements for inservice testing of valves in light-vater reactor nuclear power plants. The valves covered include those which provide overpressure protection and are required to perform a specific function, either actively by changing valve obturator position or passively by effectively maintaining required obturator position in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident.

• Mandatory Appendix 1, "Inservice Testing of PressureRelief Devices in Lighit-IYater Reactor NuclearPowver Plants" Provides the requirements for performance testing and monitoring of nuclear plant pressure relief devices. Methods, intervals, and record requirements for monitoring Revision Date: 02/11/04 Page4

ISTProgram Plan FloridaPou'erandLight Company Turkev Point Nuclear Powt-er Plant and testing are established, as well as guidelines for the evaluation of results.

Applies to safety valves, safety relief valves, pilot-operated pressure relief valves, power-actuated pressure relief valves, nonreclosing pressure relief devices and vacuum relief devices, including all accessories and appurtenances.

Mandatory Appendix II, "Check Valve ConditionAMonitoring Program" Provides an alternative to the testing or examination requirements of ISTC-3510 through ISTC-5221. The purpose of this program is both to improve valve performance and to optimize testing, examination, and preventive maintenance activities in order to maintain the continued acceptable performance of a select group of check valves.

The Turkey Point Nuclear Power Plant fourth 120-month interval Pump and Valve Inservice Testing Plan wvill be in effect as follows:

Begin End Unit 3 February 22, 2004 February 21, 2014 Unit 4 April 15, 2004 April 14, 2014 This plan will be updated as required in accordance with IOCFR50.55a(f).

This program plan provides a complete listing of those pumps and valves included in the program per the requirements of:

• ISTA "General Requirements,

• ISTB "Inservice Testing of Pumps in Lighlt-I'ater Reactor NuclearPower Plants

• ISTC "Inservice Testing of V4alves in Light- Water Reactor ANuclear Power Plants"

• Mandatory Appendix 1, "Inserlice Testing of PressureRelief Devices in Light-Water Reactor ANuclear Powt'er Plants"

• Mandatory Appendix 11, "Clheck Valve ConditionMonitoring Program" The key features of this Plan are: the Pump and Valve table listings, Relief Requests, Refueling Outage Justifications, Cold Shutdown Justifications, and Technical Positions.

The Turkey Point Nuclear Power Plant Inservice Testing Basis Document includes the justification for inclusion of components in the scope of 1ST and also the justifications for exclusion from the program. Administrative procedures, surveillance testing procedures, and other records required to define and execute the Inservice Testing Program are all retained and available at Turkey Point Nuclear Power Plant.

Revision Date: 02/11/04 Page 5

IST Program Plan FloridaPowterand Light Company Turkev Point Nuclear Pows-er Plant 2.0 INSERVICE TESTING PLAN FOR PUMPS 2.1 Pump Insert ice Testing Plan Description This program plan meets the requirements of ASME OM Code ISTB with the exception of specific relief requests contained in Attachment 3.

2.2 Pump Plan Table Description The pumps included in the Turkey Point Nuclear Power Plant 1ST Plan are listed in Attachment 12. The information contained in these tables identifies those pumps to be tested to the requirements of the ASME OM Code, the testing parameters and frequencies, and associated relief requests. The headings for the pump tables are delineated below.

Pump Tag Unique pump identification number.

Category Pump group as defined in ISTB-2000.

Group A Continuous or routinely operated pumps Group B Standby pumps not operated routinely except for testing Safetv Class ASME Code classification of the pump.

I Class I 2 Class 2 3 Class 3 SR Non-Code, Safety Related NS Non-Safety Related Pump Type Pump type.

Centrifugal Vertical Positive Displacement Pump Driver Pump driver type.

Motor Motor driven Turbine Steam turbine driven Engine Engine Driven Nominal Speed Pump speed for variable speed pumps only.

P&ID Piping and Instrumentation Drawing (Flow Diagram) on sv'hich the pump is represented.

P&ID Coor. The P&ID Coordinate location of the pump.

Revision Dale: 02/11/04 Page 6

ISTProgram Plan Florida Powlerand Light Company Turkev Point Nuclear Power Plant 2.2 Pump Plan Table Description (Cont'd)

Test Tvpe Measured pump test parameters.

N Speed DP Differential Pressure Q Flow Rate V Vibration a - Denotes a Category A Pump Test b - Denotes a Category B Pump Test c - Denotes a Comprehensive Pump Test Test Freq. Frequency for performing the specified inservice test.

M3 Quarterly (92 Days)

CS Cold Shutdown Y2 Biennially (2 Years)

Relief Request A relief request number is listed when a specific code requirement is determined to be impracticable. Attachment 2 contains an index of all the relief requests included in Attachment 3.

Tech. Pos. A technical position number is listed when the requirements of the code are not easily interpreted and clarifying information is needed. The technical position is used to document how Code requirements are being implemented at the station. Technical Positions for pumps are prefixed with "TPp". Attachment 10 contains an index of all the Station Technical Positions included in Attachment 11.

Pump Name Descriptive name of the pump.

Revision Date: 02/11/04 Page 7

IST Program Plai FloridaPowver and Light Company Turkev' Point Nuclear Power Plant 3.0 INSERVICE TESTING PLAN FOR VALVES 3.1 Valve Inservice Testing Plan Description This plan establishes the test intervals and parameters to be measured to meet the requirements of ISTA, ISTC, Appendix 1, and Appendix 11 with the exception of tile specific relief requests contained in Attachment 5.

Where the frequency requirements for valve testing have been determined to be impracticable, Cold Shutdown or Refuel Outage Justifications have been identified and written. These justifications are provided in Attachments 7 and 9 respectively.

3.2 Valve Plan Table Description The valves included in the Turkey Point Nuclear Power Plant 1ST Plan are listed in Attachment 13. The information contained in these tables identify those valves that are required to be tested to the requirements of ISTC and Appendix 1, the test parameters, frequency of testing, and tie associated relief requests. The headings for the valve tables are delineated belowv.

Valve Tag A unique identifier for the valve.

P&ID Piping and Instrumentation Drawing (Flow Diagram) on which the valve is represented.

P&ID Coor. The P&ID Coordinate location of the valve.

Safetv Class The ASME Class abbreviation.

1 Class I 2 Class 2 3 Class 3 SR Non-Code, Safety Related NS Non-Safety Related Cat. The ASME OM Code category (or categories) as defined in ISTC-1 300.

A Seat Leakage Limited.

B Seat Leakage Not Required.

C Self-Actuating Valves.

D Single Use Valves.

A/C Both Categories A and C.

B/C Both Categories B and C.

Size The nominal pipe size of the valve, in inches.

Revision Date: 02/11/04 Page 8

IST Program Plan FloridaPoiswer andLight Comnpany Turkev Point Nuclear Powter Plant 3.2 Valve Plan Table Description (Cont'd)

Valve Type The valve body style abbreviation.

BAL Ball Valve BTF Butterfly Valve CK Check Valve DAM Damper DIA Diaphragm Valve GA Gate Valve GL Globe Valve PLG Plug Valve RPD Rupture Disk RV Relief Valve SCK Stop Check Valve 3W 3-Way Valve 4W 4-Way Valve Act. Type The valve actuator type abbreviation.

AO Air Operator HO Hydraulic Operator MAN Manual MO Motor Operator SA Self-Actuating SO Solenoid Operator Active/Passive Active or Passive function determination for the valve in accordance with I STC-2000.

A Active P Passive Normal Position The normal position abbreviation. The valve's position during normal power operation. If the system does not operate during power operation, then the normal position is the position of the valve when the system is not operating.

C Closed LC Locked Closed DE De-energized (3-way and 4-way solenoid valves)

E Energized (3-way and 4-wvay solenoid valves) 0 Open LO Locked Open SYS System Condition Dependent Revision Date: 02/11/04 Page 9

ISTProgram Plan Florida Powver and Light Company Turkev Point Nuclear Power Plant 3.2 Valve Plan Table Description (Cont'd)

Safetv Position The safety function position(s). For valves that perform safety functions in the open and closed positions more than one safety function position may be specified.

C Closed DE De-energized (3-way and 4-way solenoid valves)

E Energized (3-way and 4-way solenoid valves)

DE/E De-energized and Energized O Open O/C Open and Closed Test Type The test type abbreviation.

AT-01 Seat Leakage Rate Test (low pressure air),

Appendix J AT-02 Seat Leakage Rate Test (high pressure water),

Pressure Isolation Valve BTC Exercise Test Closed BTO Exercise Test Open CC Exercise Test Closed - Check Valve(')

CO Exercise Test Open - Check Valve(l)

CP Partial Exercise Test - Check Valve~')

DT Rupture Disk Test FC Fail Safe Test Closed FO Fail Safe Test Open PIT Position Indication Test RT Relief Valve Test

(') Three letter designations may be used for check valve condition monitoring tests to differentiate between the various methods of exercising check valves.

The letter following "CC", "Co", or CP" should be "A" for acoustics, "D" for disassembly and examination. `F for flow indication, 'M" for magnetics, "R" for radiography, "U" for ultrasonics, or iX" for manual exercise.

Test Freq. The test frequency abbreviation.

App-J Appendix J CM Condition Monitoring(')

CS Cold Shutdown M3 Quarterly OP Operating Activities(2)

RR Refueling Outage YX X Years (X = 1,2,..., 10)

("Frequency is as indicated in respective Condition Monitoring Plan for that valve group.

(2 )Satisfied in accordance with IST Program Technical Position, TPv-01, "Bi-directional Testing of Check Valves".

Page 10 Revision Ret ision Daze: 02/11/04 Dote.' 02111104 Page 1I0

ISTProgramnPlan Florida Power and Light Company Turkei' Point Nuclear Power Plant 3.2 Valve Plan Table Description (Cont'd)

Relief Request A relief request number is listed when a specific code requirement is determined to be impracticable. Attachment 4 contains an index of all the relief requests included in Attachment 5.

Deferred Just. Deferred Test Justification. This section refers to Cold Shutdown Justifications and Refuel Outage Justifications.

A Cold Shutdown Justification number is listed when the testing frequency coincides with Cold Shutdowns instead of being performed quarterly. Cold Shutdown Justification numbers for valves are prefixed with "CSJ". Attachment 6 contains an index of all the Cold Shutdown Justifications included in Attachment 7.

A Refueling Justification number is listed when the testing frequency coincides with Refueling Justification instead of being performed quarterly or during Cold Shutdowns. Refueling Justification numbers for valves are prefixed with "RJ".

Attachment 8 contains an index of all the Refueling Justifications included in Attachment 9.

Tech. Pos. A technical position number is listed when the requirements of the code are not easily interpreted and clarifying information is needed. The technical position is used to document how Code requirements are being implemented at the station. Technical Positions for valves are prefixed with "TPv". Attachment 10 contains an index of all the Station Technical Positions included in Attachment 11.

Revision Date: 02/11/04 Page I I

ISTProgramt Plan Florida Power and Light Company Turkey Point Aluclear Powl'er Plant

4.0 ATTACHMENTS

Attachment I System and P&ID Listing Attachment 2 Pump Relief Request Index Attachment 3 Pump Relief Requests Attachment 4 Valve Relief Request Index Attachment 5 Valve Relief Requests Attachment 6 Cold Shutdown Justification Index Attachment 7 Cold Shutdown Justifications Attachment 8 Refuiel Outage Justification Index Attachment 9 Refuiel Outage Justifications Attachment 10 Station Technical Position Index Attachment 11 Station Technical Positions Attachment 12 Insen'ice Testing Pump Table Attachment 13 Inservice Testing Valve Table Page 12 Revision Date: 02/11/04 Revision Date: 02111104 Page 12

IST Program Plan FloridaPowerand Light Company Turkey Point Nuclear Pouter Plant ATTAChMIENT I SYSTEM AND P&ID LISTING System System Name P&ID 013 Instrument Air/Service Air 5610-M-3013-1 013 Instrument Air/Service Air 5613-M-3013-1,7 018 Condensate Storage 5613/4-M-3018-1 019 Intake Cooling Water 5613/4-M-3019-1 020 Primary Water Makeup 5613/4-M-3020-2 022 Emergency Diesel Generator 5613/4-M-3022- 1,2,3,4,5,6 022 Emergency Diesel Generator 5614-3022-3,4 025 Control Building Ventilation 561 0-M-3025-2 030 Component Cooling Water 5613/4-M-3030- 1,2,3,4 030 Component Cooling Water 5613-M-3030-5 033 Spent Fuel Pit Cooling 5613/4-M-3033 036 Sampling 5613/4-M-3036-1 036 Sampling 5613/4-M-3037- 1 041 Reactor Coolant System 5613/4-M-3041-2,3,4 046 Boric Acid 5610-M-3046-1 047 Chemical and Volume Control 5613/4-M-3047- 1,2,3 050 Residual Heat Removal 5613/4-M-3050- 1 053 Containment Purge 5613/4-M-3053-1 056 Emergency Containment Filtering 5610-M-3068- 1 056 Emergency Containment Filtering 5613/4-M-3056- 1 061 Liquid Waste Disposal System 5613/4-M-3061-1 062 Safety Injection 5613/4-M-3062-1,2 064 Safety Injection Accumulators 5613/4-M-3064- 1 065 Nitrogen and Hydrogen 5610-M-3065- I 068 Containment Spray 5613/4-M-3068- 1 072 Main Steam System 5613/4-M-3072-1 074 Blowdown 5613/4-M-3032- 1,4 074a Main Feedwater 5613/4-M-3074-3 075 Auxiliary Feedwater 5610-M-3075-1,2 075 Auxiliary Feedwater 5613/4-M-3075-1,2,3 094a Post Accident Hydrogen Monitors 5613/4-M-3094- 1 094b Containment Condition Monitoring 5613/4-M-3094-1 094c Post Accident Sampling 5613/4-M-3094-1 094d Post Accident Hydrogen Control 5613/4-M-3094-1 101 Breathing Air 5613/4-M-3 101-1 Page 13 02/11/04 Revision Date: 02111104 Page 13

IST Program Plan Florida Poutwerand Light Company Turkey Point Nuclear Power Plant ATTACHMENT 2 PUMP RELIEF REQUEST INDEX (Page I of 1) lReief No. Description [NRC Approval Date l PR-OI l[ Boric Acid Transfer Pump Fixed Resistance l PR-02 0.25 %Gauge Liquid PR-03 lContainment Spray Pump Comprehensive Pump

_ _Test PR-04 l RHR Discharge and Suction Pressure Gauge PRange Requirements l PR-05 llNo Comprehensive Test for Certain Group A

_ Pumps PR-06 Categorization of Residual Heat Removal Pumps as Group B (Modes 1-4) and Group A

.(Modes 5-6)l Page 14 Revision Date: 02/11/04 Revision Date: 02111104 Page 14

IST Program Plan Florida Powerand Light Company Turkev Point Nuclear Power Plant ATTACHMENT 3 PUMP RELIEF REQUESTS Revision Date: 02/11/04 Page 15

IST Program Plan FloridaPowerand Light Company Turkel Point Nuclear Powter Plant 10 CFR 50.55a Request Number PR-01 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Lcvel of Quality and Safety

1. ASME Code Component(s) Affected 3P203A 3A Boric Acid Transfer Pump 3P203B 3B Boric Acid Transfer Pump 4P203A 4A Boric Acid Transfer Pump 4P203B 4B Boric Acid Transfer Pump

2. Applicable Code Edition andl Addenda ASME OM Code 1998 Edition through 2000 Addenda

3. Applicable Code Requirement ISTB-5121(c) - Where it is not practical to vary system resistance, flow rate and pressure shall be determined and compared to their respective reference values.

4. Reason for Request Pursuant to 10 CFR 50.55a, "Codes and Standards", paragraph (a)(3), relief is requested from the requirement of ASME OM Code ISTB-5121(c). The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

The normal test loop for the subject pumps consists of fixed resistance flow paths to limit flow, however, flow measuring instruments are not installed. See Attachment 1, Boric Acid Transfer Pump Test Diagram. Since the system resistance is fixed and can be assumed to be constant, pump degradation can be detected by comparing successive measurements of pump differential pressure.

5. Proposed Alternative and Basis for Use An alternate test circuit is available in which flow rate may be measured, however this flow path requires injection of highly concentrated boric acid solution into the reactor coolant system. During the quarterly group A test at normal powver operations, this test is highly impractical since severe power level fluctuations would be created which would lead to a potential transient and subsequent trip of the reactor. Performing this test at cold shutdown intervals would also result in excessive boration of the reactor coolant system resulting in potential difficulties and delays in restarting the plant.

Revision Date: 02/11/04 Page 16

ISTProgram Plan Florida Powterand Light Company Turkel' Point Nuclear Power Plant 10 CFR 50.55a Request Number 11lR-01 (Continued)

As an alternative to measuring differential pressure and flow during the group A quarterly test, only the differential pressure will be measured and compared to its reference value. Additionally, vibration measurements are also recorded and compared to their reference values. Manual isolation valves are closed and flow is recirculated back to the boric acid tank. See Attachment 1, Boric Acid Transfer Pump Test Diagram.

During the comprehensive inservice test when flow may be measured, full spectrum analysis will be performed above the required vibration analysis by the Code. When performing the comprehensive pump test, all required parameters will be measured and compared to their reference values.

Additionally, these pumps are included in the station preventive maintenance program wVhich requires a pump inspection and oil analysis to be performed periodically.

Based on the preventive maintenance inspection results, full spectrum analysis, and continued quarterly and comprehensive testing, an accurate assessment of pump health and operational readiness is determined. This alternative provides an acceptable level of quality and safety.

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 4 "' 120 month interval.

7. Precedents This relief request was previously approved for 3rd Ten Year Interval at Turkey Point as PR-1, and satisfies the requirements of Generic Letter 89-04, Position 9.

Revision Date: 02/11/04 Page 17

ISTProgram Plan FloridaPower and Light Conipany Turkev Point Nuclear Power Plant I0 CFR 50.55a Request Number PR-01 (Continued)

Attachment I Boric Acid Transfer Pump Test Diagram Boric Acid Tank Fl 113 Boric Acid Blender Boric Acid Transfer Pump 0 Charging Pump Suction Pi Primary Water Supply Page 18 Revision Date:

Revision 02/11/04 Date: 02111104 Page 18

ISTProgram Plan Florida Poiler and Light Company Turker Point Aluclear Power Plant 10 CFlZ 50.55a Request Number PR-02 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASME Code Component(s) Affected 3P203A 3A Boric Acid Transfer Pump 3P203B 3B Boric Acid Transfer Pump 4P203A 4A Boric Acid Transfer Pump 4P203B 4B Boric Acid Transfer Pump 3P21 IA 3A Component Cooling Water Pump 3P2 I B 3B Component Cooling Water Pump 3P21 IC 3C Component Cooling Water Pump 4P21 IA 4A Component Cooling Water Pump 4P21 lB 4B Component Cooling Water Pump 4P21 IC 4C Component Cooling Water Pump 3P215A 3A Safety Injection Pump 3P215B 3B Safety Injection Pump 4P215A 4A Safety Injection Pump 4P215B 4B Safety Injection Pump

2. Applicable Code Edition and Addenda ASME OM Code 1998 Edition through 2000 Addenda

3. Applicable Code Requirement ISTB-3520(a) - Gage Lines. If the presence or absence of liquid in a gage line could produce a difference of more than 0.25% in the indicated value of the measured pressure, means shall be provided to ensure or determine the presence or absence of liquid as required for the static correction used.

4. Reason for Request Pursuant to 10 CFR 50.55a, "Codes and Standards", paragraph (a)(3), relief is requested from the requirement of ASME OM Code ISTB-3520(a). The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

For the group A and comprehensive pump tests, applying the 0.25% limit to low pressure measurements to these pumps results in complex venting procedures requiring valve manipulations, component disassembly, and breech of radioactive and chemically treated systems to perform the test. Turkey Point has implemented and mandated programs and policies to minimize the causes of these types of waste products.

Revision Dale: 02/11/04 Page 19

IST Program Plan FloridaPowterand Light Company Turkev Point Nuclear Pous'er Plant 10 CFR 50.55a Renuest Number PR-02 (Continued)

Venting of the suction gages for the purposes of testing does not significantly effect the overall differential pressure measurement, while it significantly impacts the plant waste reduction program.

For the subject pumps, discharge pressure exceeds suction pressure by at least a factor of six, for which a 0.25% error introduced into the suction pressure measurement typically results in an error of 0.05% in the differential pressure calculation. This error is insignificant with respect to the potential 6% error allowance applied to both the suction and discharge pressure instruments.

5. Proposed Alternative and Basis for Use As an alternative, the introduced error in conjunction with the specific range and accuracy of the gauges utilized will be verified to comply with the minimum Code required accuracy for calculation of the differential pressure. This calculation will verify that the square root of the sum of the errors of the specific gauges utilized, and will include a term to account for the error associated with the presence or absence of liquid, is less than the square root of the sum of the squares of 6 % of the associated suction and discharge lines.

This request applies to the Boric Acid Transfer and Component Cooling water pumps' group A test and all of the subject pumps' comprehensive tests. The Safety Injection pumps are considered group B. Flow rate is the only measured parameter during the group B test of the Safety Injection pumps.

This alternative provides an acceptable level of quality and safety.

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 4"' 120 month interval.

7. IPrecedents This relief request was previously approved for 3rd Ten Year Interval at Turkey Point as PR-4.

Revision Date: 02/11/04 Page 20

IST Program Plan FloridaPowlerand Light Company Turkel Point Nuclear Powver Plant 10 CFR 50.55a Reciuest Number PR-03 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASM1E Code Component(s) Affected 3P214A 3A Containment Spray Pump 3P214B 3B Containment Spray Pump 4P214A 4A Containment Spray Pump 4P214B 4B Containment Spray Pump

2. Applicable Code Edition and Addenda

ASME OM Code 1998 Edition through 2000 Addenda

3. Applicable Code Req uirement ISTB-3300(e)(1) - Reference values shall be established within +/- 20% of pump design flow rate for the comprehensive test.

4. Reason for Request

Pursuant to 10 CFR 50.55a, "Codes and Standards", paragraph (a)(3), relief is requested from the requirement of ASME OM Code ISTB-3300(e)(1). The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

The specified +/- 20% of pump design flow rate can not be achieved for the subject pumps during normal quarterly Group B testing or during Comprehensive testing. The design flow rate of the containment spray pump is 1450 gpm. This point is also the best efficiency point of the pump.

Attachment I is tile pump characteristic curve which is representative of the Containment Spray pumps at Turkey Point.

5. Proposed Alternative and Basis for Use The design of the containment spray system is such that the test loop for the pump consists of a 6" discharge line which separates into a 2" recirculation line back to the pump suction. The 6" discharge line terminates inside containment at the spray nozzles.

Testing of the pump at the design flow rate, would require discharging flow through the spray nozzles and subsequently wetting containment. The discharge piping was not designed to be temporarily modified to allow pump design flow wvithout flow being discharged to the containment via the spray nozzles.

Revision Date: 02/1/04a Page 2 1

ISTProgram Plan FloridaPower and Light Company Turkey Point Nuclear Powt'er Plant 10 CFR 50.55a Request Number PR-03 (Continued)

During preoperational testing (1971 and 1972 for Unit #3 and Unit #4 respectively), the containment spray pumps were full flow tested. A test loop was constructed by installing a 6" section of piping in place of the discharge check valve (*-890A/B). This temporary section of piping was routed to the plant sump. See Attachment 2, Containment Spray System Preoperational Test Flow Diagram. With the discharge to containment isolated, the pumps were run for at least an hour in the recirculation mode (1" line) taking suction from the Refueling Water Storage Tank (RWST). After operating in recirculation, the pumps were then operated at substantial flow using the temporary test line. Three points on the manufacturers curne were then verified, with the acceptance criteria that the pump head and capacity be above the FSAR performance curve shown in Attachment 1. Each of the pumps delivered at least 1450 gpm when preoperationally tested. Attachments 3 and 4 contain the preoperational data plotted against the performance curve.

It should be noted that the originally installed 1" recirculation line was designed for a flow rate of 50 gpm to prevent pump damage when pumping to a closed loop. In 1982, a test recirculation line was installed for each containment spray pump to allow each pump to be tested at a minimum of 400 gpm for inservice testing purposes. During the design change process it was identified by the pump manufacturer (Gould) that a minimum recirculation flow of 300 gpm be provided for the short duration monthly test and 400 gpm be provided for the annual hour-long test. Turkey Point installed the necessary recirculation test flow path under design change PC/M 82-19, 20 on both Unit #3 and Unit #4. See Attachment 5, Current Containment Spray System Diagram.

As an alternative to testing at +/- 20 % of design flow, the test recirculation loop shown in Attachment 5 will be used. The reference flows are established at approximately 400 gpm, versus a design flow of 1450 gpm. The low flow rate is due to the 2" recirculation line. At this reference point of 400 gpm, the characteristic curve for the pump is not horizontal. Pump degradation as noted by measuring differential pressure can be detected for a given flow rate reference value.

The reference flow rate of 400 gpm corresponds to 27.6 % of pump design flow. At the reference conditions the flow values are currently at a point on the curve (Attachment 1) that is well sloped and repeatable. Any degradation in pump performance at the set flow rate be recognized or detected through a substantial change in measured pump differential pressure.

To establish the flow rate within +/- 20 % of design would require a flow rate of at least 1160 gpm. Establishing flows at 1160 gpm does not increase the ability to detect degradation or assess pump conditions since the slope of the pump curve is essentially constant from shutoff head to 1250 gpm. Therefore, testing at higher flows does not increase the ability to detect hydraulic degradation.

Revision Date: 02/11/04 I'age 22

IST ProgramPlan Florida Powver and Light Company Turkel' PointNuclear Powter Plant 10 CFR 50.55a Request Number PR-03 (Continued)

Past, test data for the Unit #3 and #4 containment spray pumps is presented in Attachments 6 and 7 respectively. This test data was collected during the corresponding inservice test with the pump operating at a set flow rate of 400 gpm. Comparing this test data to the original pump performance and preoperational curves in Attachments 3 and 4 demonstrates the pumps are operating above the original performance curve and at or above the original preoperational curve. Additionally, vibration data collected during the inservice tests, has been below 0.325 in/sec in all cases. Based on this mechanical and hydraulic data, and the maintenance history, there is reasonable assurance that the pumps would perform their intended design function. Projecting the hydraulic pump performance at substantial flow rates would be expected to be above the performance curve at the design point, with adequate margin. Mechanical vibration projected at substantial flows would tend to be less than that at the reduced flow test point.

As expected, insignificant degradation has been experienced since these pumps are only operated for testing purposes.

To compensate for testing the containment spray pumps at reduced flow rates during the comprehensive test, as required by ISTB-3300(e)(1), additional activities will be performed as follows to assess operational readiness and determine pump health.

During all comprehensive inservice testing, fuill spectrum analysis is performed above the required vibration analysis by the Code. Additionally, these pumps are included in the station Preventive Maintenance Program which requires a pump inspection and oil analysis to be performed periodically. Based on the preventive maintenance inspection results, full spectrum analysis, oil analysis, and continued quarterly and comprehensive testing within 27.6% of design pump flow, an accurate assessment of pump health and operational readiness is determined.

Additionally, Turkey Point has previously modified the system to increase the test flow rate. However, reestablishing the full flow test loop for the purpose of periodic testing would require modifications to the plant and removal of check valve (*-89OA/B). Post maintenance testing of system and verification of check valve (*-89OA/B) would be a substantial burden. Substantial flow can only be achieved through the 6" discharge line which ultimately requires flow through the spray nozzles. A temporary modification to plug the nozzles and install a test return line capable of passing pump design flow would be highly labor intensive and would require a permanent modification to the containment spray piping system.

Rev'ision Date: 02/11/04 Page 23

ISTProgramn Plan Florida Powierand Light Company Turkev Point Nuclear Pouwer Plant 10 CFR 50.55a Request Number PR-03 (Continued)

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 411 120 month interval.

7. Precedents

• Similar relief request PR-6 wvas previously approved for North Anna Power Station on January 8, 2002. Docket Nos. 50-338 and 50-339 (TAC Nos. MB2221and M1B2222).

• Similar relief request PR-I wvas previously approved for Seabrook Station on May 30, 2003. Docket No. 50-443 (TAC No. MB6676).

Revision Date: 02/11/04 Page 24

IST Program Plan FloridaPower and Light Company Turkev Point Nuclear Power Plant 10 CFR 50.55a Request Number PR-03 (Continued)

Attachment I Containment Spray Pump Characteristic Curve Containment Spray Pump 700 600

.4-, 500 03 03 IU- 400 300 03 200 - . _ .- _-_ _ _ . Performance Curve 100 0

0 500 1000 1500 2000 2500 Flow - GPM A - Pump Design Point (1450 gpm)

A - Pump Test Point (set parameter is flow at 400 gpm)

Revision Date: 02/11/04 Page 25

ISTProgram Plan Florida Power and Light Company Tzirkei' Point Nuclear Pouwer Plant 10 CFR 50.55a Request Number PR-03 (Continued)

Attachment 2 Containment Spray System Preoperational Test Flow Diagram Temporary Gauge Temporary 6" Test Line Page 26 Revision Date: 02/11/04 Date: 02111104 Page 26

IST ProgramPlan FloridaPouwer and Light Company Turkev Point Nuclear Power Plant 10 CFR 50.55a Request Number PR-03 (Continued)

Attachment 3 Containment Spray Pump Preoperational Data - Unit #3 Containment Spray Pump 3A 700

.. >__ .-.- - lPeoperational Curve 600 500 -

0 .~~~~~ _- .- . ... . . . ..........

400 0

300 ..- ---_ .-P r o m n e C r . _ _...

.... .....x....

200 -

100 0

0 500 1000 1500 2000 2500 3000 Flow - GPM Containment Spray Pump 3B 700 00 - - _ - - Peoperational Curve 600 - . . ... . _..

0) 0)

400 - - . .-

300 Performance Curve \ -..-..

0 X 200 - . . .-. _. - . -. __

100 . .. ._ .. __. ..- __. .- _

0 I

I 0 500 1000 1500 2000 2500 3000 Flow - GPM I

Reviio~iDat: 0211/ 4 Pa e 2 Revision Date: 02111104 Page 27

IST Program Plan Florida Power and Light Company Turkey Point Nuclear Power Plant 10 CFR 50.55a Reuqtest Number PR-03 (Continued)

Attachment 4 Containment Spray Pump Preoperational Data - Unit #4 ContinmetS y

.P.u.....mp 4 . .

I Containment Spray Pump 4A 800 Peoperational Curve 700 600 0

0 500*

a>

a) 400 Performance Curve 300 I

200 100 0

0 500 1000 1500 2000 2500 3C00.

Flow - GPM Containment Spray Pump 4B 800 Peoperational Curve 700 600 CO500

. 400 Pefrmaonce Curve

! am 300 1 200 100 0

0 500 1000 1500 2000 2500 3000 Flow - GPM Page 28 Revision Date: 02/11/04 Date: 02111104 Page 28

IST Programn Plan FloridaPower and Light Co'mpany Turkel' Point ANuclear Power Plant IOCFR 50.55a Renuest Number PR-03 (Continued)

Attachment 5 Current Containment Spray System Diagram Spray Nozzles P-19B Spray Nozzles CS Pump B

---

--- - 2' Test Recirculation Line Revision Dale: 02/11/04 Page 29

ISTProgramn Plan FloridaPowerand Light Comnpany Turkev' Point Nuclear Power Plant 10 CFR 50.55a Request Number PR-03 (Continued)

Attachment 6 Containment Spray Pump Operational Data - Unit #3 3A Containment Spray Pump DP Data @400 gpm 650 645 - - -*.-- .

6401 - . -.-.

635 4 .

630 .-- .-----.--- --

625- -- -

620- . .-- , Ag.

615 .. ..... ...-

610.. - - - .

605 - ..-.-..

1/9/01 4/19/01 7/28/01 11/5/01 2/13/02 5/24/02 9/1/02 12/10/0 3/20/03 6/28/03 2

3B Containment Spray Pump DP Data @400 gpm 650 645 .....

635 630 ...

625 ......

620....

615 _ .. .. ...

610---. .. .. . .-.- _..-

605 -

10/1/2000 4/19/2001 1115/2001 5/24/2002 12/10/2002 6/28/2003 1/14/2004 Revision Date: 02/11/04 Page 30

IST Programn Plan FloridaPowierand Light Company Turkey Point Nuclear Poiwer Plant 10 CFR 50.55a Reg nest Number PR-03 (Continued)

Attachment 7 Containment Spray Pumrp Operational Data - Unit #4 4A Containment Spray Pump DP Data @400 gpm 650.

645- . ...

635 .

630 - - --

625- - ---

620 -.- -- .

610---.-..

605 - ....

600. -. ..- .. , .

10/1/2000 4/19/2001 11/5/2001 5/24/2002 12/10/2002 6/28/2003 1/14/ 2004 4B Containment Spray Pump DP Data @400 gpm 650- . . .. .

645 -

640i-635 -- ...

630 -. .

625 - --

620 615 610 -.

605 ---- . .....

600 !-- -- - - --_

10/1/2000 4/19/2001 11/5/2001 5/24/2002 12/10/2002 6/28/2003 Revision Date: 02/111/04 Page 3 1

ISTProgram Plan FloridaPowt er and Light Company Turkel' Point Nuclear Powter Plant 10 CFR 50.55a Request Number PR-04 Proposed Alternative In Accordance wiith 10 CFR 50.55a(a)(3)(I)

Alternative Provides Acceptable Level of Quality and Safety

1. ASMIE Code Component(s) Affected 3P210A 3A Residual Heat Removal Pump 3P210B 3B Residual Heat Removal Pump 4P210A 4A Residual Heat Removal Pump 4P210B 4B Residual Heat Removal Pump

2. Applicable Code Edition and Addenda ASME OM Code 1998 Edition through 2000 Addenda

3. Applicable Code Requirement ISTB-3510(b)(1) - The fuill-scale range of each analog instrument shall be not greater than three times the reference value.

4. Reason for Request Pursuant to 10 CFR 50.55a, "Codes and Standards", paragraph (a)(3), relief is requested from the requirement of ASME OM Code IST13-3510(b)(1). The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

The installed suction and discharge pressure gauges of the residual heat removal pumps are sized to accommodate the pressure range of 4 to 600 psig expected under standby, cold shutdown, and emergency operation modes. The instrument range is 0 to 600 psig.

As a result, the instrument range exceeds the requirement of ISTB-3510(b)(1) since during the quarterly and cold shutdown inservice tests, the suction/discharge pressures may be considerably less than the range requirements of ISTB-35 I0(b)(1).

5. Proposed Alternative and Basis for Use As an alternative, the use of existing instrumentation, without meeting the 1/3 range requirements of the Code but which exceed the Code required accuracies will be applied to all inservice tests of the RIHR pumps. This alternative will adequately provide for monitoring pump health conditions for the following reasons:

These specific gauges are calibrated to an accuracy of +/- 0.25 % and are of the "twice around" type such that they may accurately indicate pressure over all modes of Residual Heat Removal operations (Shutdowvn Cooling and Emergency Core Cooling). The gauge range on the first revolution is 0 to 300 psig and 300 to 600 psig on the second revolution. See Attachment 2, RHR Suction and Discharge Pressure Gauge.

Revision Date: 02/11/04 Page 32

ISTProgram Plan FloridaPoit'erand Light Company Turkely Point Nuclear Pows'er Plant 10 CFR 50.55a Request Number PR-04 (Continued)

Suction Pressure Suction pressure measurements are recorded and used to derive the pump differential pressure through calculation. The accuracy of the suction pressure measurement normally has little or no effect on the results of this calculation since, generally, the pump discharge pressure exceeds the suction pressure by 6 to 7 times the reference value. When determining pump differential pressure (DP), typically the RHR pump DP is approximately 100 psi (discharge pressure approximately 120 psig while suction pressure is approximately 20 psig). The maximum effect of suction pressure inaccuracies is 0.25% x 600 psig, or 1.5 psig. The Code required gauge range for this suction pressure reference value (20 psig) would be 0 to 60 psig. The Code accuracy requirement of 2% would cause a maximum inaccuracy of 2.0% x 60 psig, or 1.2 psig. See Attachment 1.

Discharge Pressure Discharge pressure measurements are also recorded and used to derive the pump differential pressure through calculation. When determining pump differential pressure (DP), typically the RHR pump DP is approximately 100 psig (discharge pressure approximately 120 psig while suction pressure is approximately 20 psig). The maximum effect of the discharge pressure inaccuracies is 0.25% x 600 psig, or 1.5 psig. The Code required gauge range for this discharge pressure reference value (120 psig) would be 0 to 360 psig. The Code accuracy requirement of 2% would cause a maximum inaccuracy of 2.0% x 360 psig, or 7.2 psig. See Attachment 1.

Combination Based on the inaccuracies of the suction and discharge pressure gauges (+/- 1.5 psig), the largest possible error in the differential pressure calculation is +/- 3 psig. Use of gauges with Code required ranges, and applying the Code accuracy requirements, the largest possible inaccuracies would be 1.2 psig + 7.2 psig, or 8.4 psig. See Attachment 1.

Therefore, the use of permanently installed pressure instruments which exceed the Code required accuracies but do not meet the Code range requirements would reduce the overall instrument inaccuracies with respect to differential pressure for the quarterly test from 8.4 psig to 3.0 psig.

For the comprehensive pump test, the overall inaccuracy of the currently installed instruments is 3.0 psig versus 2.1 psig for an instrument which meets the range requirements. This difference is less than 1% (0.9 psig) of the overall reference differential pressure of 100 psi.

Additionally, during the RIIR pump comprehensive testing, full vibration spectrum analysis is performed above the Code required vibration analysis. Further, these pumps are included in the station preventive maintenance program which requires each pump to be inspected on a periodic basis.

Revision Date: 02/11/04 Page 33

ISTPrograntPlan Florida Power and Light Cormpany Turkev Point Nuclear Power Plant 10 CFR 50.55a Request Number PR-04 (Continued)

Based on the preventive maintenance inspection results, fill spectrum analysis, and continued quarterly and comprehensive testing with the permanently installed pressure gauges, an accurate assessment of pump health and operational readiness is determined.

This alternative provides an acceptable level of quality and safety.

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 4 1h 120 month interval.

7. Precedents A similar relief request was previously approved for 3rd Ten Year Interval at Turkey Point as PR-3.

Revision Date: 02/11/04 Page 34

IST Progranm Plan FloridaPower and Light Company, Turkel' Point Nuclear Power Planit 10 CFR 50.55a Reauest Number PR-04 (Continued)

Attachment 1 Gauge Ranges and Accuracy Comparison The following tables present a comparison between the permanently installed pressure gauges on the RHR pumps at Turkey Point along with the Code required ranges and accuracies for both a Group A or B test and a Comprehensive test.

Suction Pressure Gauge Range Accuracy Suction Pressure Inaccuracy Turkey Point 0 - 600 psig 0.25 % 1.5 psig Group A or B Test 0 - 60 psig 2.0 % 1.2 psig Comprehensive Test 0 - 60 psig 0.5 % 0.3 psig Discharge Pressure Gauge Range Accuracy Discharge Pressure Inaccuracv Turkey Point O- 600 psig 0.25 % 1.5 psig Group A or B Test 0 - 360 psig 2.0 % 7.2 psig Comprehensive Test 0 - 360 psig 0.5 % 1.8 psig Combination - Differential Pressure Suction Suction Pressure Discharge Discharge Total Gauge Accuracy Gauge Range Pressure Accuracy Inaccuracy Turke%' Point 0 - 600 psig 0.25 % (1.5 psig) 0 - 600 psig 0.25 % (1.5 psig) 3.0 psig Group A or B Test 0 - 60 psig 2.0 % (1.2 psig) 0 - 360 psig 2.0 % (7.2 psig) 8.4 psig Comprehensive Test 0 - 60 psig 0.5 % (0.3 psig) 0 - 360 psig 0.5 % (1.8 psig) 2.1 psig Page 35 Revision Revs ison Date: 02/11/04 Date: 02/111104 P)age 35

1ST Program Plan FloridaPower and Light Company Turkev Point Nluclear Pows'er Plant 10 CFR 50.55a Reguest Number PR-04 (Continued)

Attachment 2 RIR Suction and Discharge Pressure Gauge Revision Date: 02/11/04 Page 36

IST ProgramPlan Florida Powver and Light Company Turkel' PointNuclear Polter Plant 10 CFR 50.55a Request Number PR-05 Proposed Alternative In Accordance with IO CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASMVE Code Component(s) Affected 3P201A 3A Charging Pump 3 P201 B 31B Charging Pump 3P201C 3C Charging Pump 3P21 IA 3A Component Cooling Water Pump 3P21 IB 3B Component Cooling Water Pump 3P21 IC 3C Component Cooling Water Pump 3P9A 3A Intake Cooling Water Pump 3P913 3B Intake Cooling Water Pump 3P9C 3C Intake Cooling Water Pump 4P201A 4A Charging Pump 4P201B 4B Charging Pump 4P201C 4C Charging Pump 4P21 IA 4A Component Cooling Water Pump 4P21 I B 4B Component Cooling Water Pump 4P21 IC 4C Component Cooling Water Pump 4P9A 4A Intake Cooling Water Pump 4P9B 4B Intake Cooling Water Pump 4P9C 4C Intake Cooling Water Pump

2. Applicable Code Edition and Addenda ASME OM Code 1998 Edition through 2000 Addenda

3. Applicable Code Reqnuirement ISTB-5 123, 5223, 5323 - Comprehensive Test Procedure.

4. Reason for Reqnuest Pursuant to 10 CFR 50.55a, "Codes and Standards", paragraph (a)(3), relief is requested from the requirement of ASME OM Code ISTB-5 123, 5223, and 5323. The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

The subject pumps are all categorized as group A pumps. These pumps are operated routinely during normal plant operations. Each pump is tested in accordance with its associated group A procedure. All of these pumps are operated at conditions within +/-

20% of the design flow rate wvhen tested each quarter (see attachments to this request).

All of the required Code parameters are measured and compared to their respective reference values.

Page 37 Revision Date: 02/11/04 Date: 02111104 Page 37

ISTProgram Plan FloridaPower and Light Company Turkel' Point Nuclear Power Plant 10 CFR 50.55a Request Number PR-05 (Continued)

At least once every two years, during the group A test, a full spectrum vibration analysis will be performed above the required vibration analysis by the Code. Additionally, these pumps are included in the station preventive maintenance program which requires a pump inspection and oil analysis to be performed periodically'.

The intent of the Code required Comprehensive Test is to test the pump at substantial flow (biennially) such that pump degradation may be easily detected on the portion of the pump curve wvhich is well sloped. Turkey Point tests each of these pumps at substantial flow (+/- 20% of design) each quarter.

Intake Cooling Water Pump See Attachment 1, Intake Cooling Water Pump Cur'e Insen'ice Testing Basis The intake cooling water pump is required to operate to supply cooling water from the intake structure to the tube side of the component cooling water heat exchangers during design basis accident conditions to ensure heat removal capabilities of the component cooling water system [UFSAR 9.6.2]. The intake cooling water pumps supply cooling flow to the component cooling water and turbine plant cooling water system loads during normal plant operations, however, only one pump is required to satisfy design basis accident conditions.

The C intake cooling water pump automatically starts on a loss of power or safety injection signal if either the A or B pump breaker is open. [UFSAR 9.6.2].

The intake cooling water pump is designed to deliver 16,000 gpm at 60 feet of developed head (approximately 26 psi) to the component cooling water heat exchangers during design basis accident conditions [DBD-0 19].

Inservice Testing The Intake Cooling Water Pumps are vertical line shaft pumps. These pumps are tested each quarter in accordance with Turkey Point Operating Surveillance *-

OSP-19.1. Each pump is tested at a flow rate of 15,400 gpm, which corresponds to the design accident flow rate of the system. During this test, the flow rate is set, while the differential pressure is measured. After the stabilization period, all required parameters of Table ISTB-3000-1 are measured and compared to the acceptance criteria of Table ISTB-5200-1. The design flow rate of the Intake Cooling Water Pump is 16,000 gpm. The test point of 15,400 gpm, corresponds to 96.25% of the design flow rate.

Page 38 Revision Date: 02/11/04 Date: 02111104 Page 38

ISTPrograinPlan FloridaPowver and Light Company Turkelv PointNuclear PowrerPlant 10 CFIR 50.55a Reg nest Number PR-05 (Continued)

Test Results The following data tables indicate the hydraulic test data collected for the last inservice tests. Based on these results, pump operation has been acceptable.

Applying tile group A pump acceptance criteria to these pumps indicates acceptable performance. Additionally, if the comprehensive acceptance criteria would be applied, the data would also indicate acceptable performance.

3A ICW Pump Test Results Ilate Flo" l1' 1)1' Reference I (roup A Accept Comprnhensive Acce 9/13/03 15400 27.5 27.1 1 25.7-29.8 25.7-27.9 3B ICW Pump Test Results Date Flow DP 1)1' Reference Group A Accept Cornprehensive Acce 9/13/03 15400 27.6 27.1 25.7-29.8 25.7-27.9 3C ICW Pump Test Results Date Flois DI' 1)1' Reference Grop A Accep Comnprehensive Accept 9/13/03 15400 26.1 26.8 25.5-29.5 25.5-27.6 4A ICW Pump Test Results IDate Flo l D11' 1)1' Reference group A Accept Comprehensive Accept 9/20/03 15400 26.2 27.2 25.8-29.9 25.8-28.0 4B ICW Pump Test Results Date Flo l 1)1' 1)1' Reference Group A Accept Comprehensive Accept 9/20/03 15400 26.7 28.0 26.6 -30.8 26.6 - 28.8 4C ICW Pump Test Results l)ate Flow 1)1' l DReference l roup A Accept Compreliensive Accept 9/20/03 15400 25.8 26.8 25.5-29.5 25.5-27.6 Charying Pumps Insenice Testing Basis The charging pump is required to pump water from the emergency boration makeup system or RWST to the reactor coolant system during emergency boration conditions [UFSAR 9.2.2/14.2.6]. The charging pump is designed to deliver 77 gpm @2385 psig of developed head to the reactor coolant system

[UFSAR Table 9.2-3].

Page 39 Revision Reiision Date: 02/11/04 Date: 02111104 Page 39

ISTProgramn Plan FloridaPowrerand Light Companyl Turkev Point Nuclear Powter Plant 10 CFR 50.55a Request Number PR-05 (Continued)

The charging pump takes suction from the volume control tank and discharges to the reactor coolant system through the tube side of the regenerative heat exchanger during normal operations [UFSAR 9.2]. This function is not required for safe shutdown or accident mitigation.

Inservice Testing The Charging Pumps are positive displacement pumps. These pumps are tested each quarter in accordance with Turkey Point Operating Surveillance *-OSP-47.1. Each pump is tested at a flow rate of greater than 81 gpm, which corresponds to the design accident flow rate of the system. During this test, speed is set, while the resistance of the system can not be varied. Since the pump is a positive displacement type pump both the flow rate and the discharge pressure are measured. After the stabilization period, all required parameters of Table ISTB-3000-1 are measured and compared to the acceptance criteria of Table ISTB-5300-2. The design flow rate of the Charging Water Pump is 77 gpm. The test point of 81 gpm corresponds to 105 % of the design flow rate.

The Charging Pump is a positive displacement pump. No pump curve is provided.

Test Results The following data tables indicate the hydraulic test data collected for the last inservice tests. Based on these results, pump operation has been acceptable.

Applying the group A pump acceptance criteria to these pumps indicates acceptable performance. Additionally, if the comprehensive acceptance criteria would be applied, the data would also indicate acceptable performance.

3A Charging Pump Test Results D)ate Press Press. Group A Comp HwlowIFlow Group A Comp Rer Accept Accept Ref Accept Accept Range Range Range Range 8124103 2350 2350 2186 - 2585 2186 - 2420 77.3 81.3 77.2 - 89.4 77.2 - 83.7 3B Charging Pump Test Results D)ate Press Press. Group A Comp [low Flow Group A Comp Rcf Accept Accept Rer Accept Accept Range Range lRange Range 8/17/03 2350 2340 2176 - 2574 2176 - 2410 77.2 81.0 77.0 - 89.1 77.0 - 83.4 3C Charging Pump Test Results IDate Press Press. Group A Comp Flow Flovs Group A Comp Ref Accept Accept Ref Accept Accept 2 Range Range Range Range 8Q24/03 _2325 2350 2186 - 2585 2186 - 2420 77.8 81.4 77.3 - 89.5 77.3 - 83.8 Revision Date: 02/11/04 Page 40

IST PrograntPlan FloridaPows-er and Light Company Turkel Point Nuclear Poivser Plant l() CFR 50.55a Requlest Number PR-05 (Continued) 4A Charging Pump Test Results Date I'ress Press. Group A Comp llow 1Flo I Group A Comp r Accept Accept Ref Accept Accept

_lange - lange Range Range 7/02/03 2350 2300 2139 - 2530 2139 - 2369 81.1 81.5 77.4 - 89.7 77.4 - 83.9 4B Charging Pump Test Results Dlate I'ress Press. Group A C(omp Flow Hlow Group A Comp Ref Accept Accept Ref Accept Accept flange Rlange _lange Range 9/13/03 2390 2400 1 2232 - 2640 2232 - 2472 80.5 81.0 77.0 - 89.1 77.0 - 83.4 4C Charging Pump Test Results Date Press Press. Group A Comp Flow Flow Group A l Comp Ref Accept Accept Ref Accept Accept Range Range _ Range Ilange 9/13/03 2450 2390 2223 - 2629 2223 - 2461 80.5 82.0 77.9 - 90.2 77.9 - 84.5 Component Cooling Water Pump See Attachment 2, Component Cooling Water Pump Curve Inservice Testing Basis The component cooling water pump is required to operate to supply cooling water to the shell side of the component cooling water heat exchangers during design basis accident conditions to ensure heat removal capabilities of the component cooling water system [UFSAR 9.3.2]. One pump and three component cooling water heat exchangers are normally operated to provide cooling vater for various components located in the auxiliary and containment buildings [UFSAR 9.3.1]. Following a loss-of-coolant accident, one component cooling water pump and two component cooling wvater heat exchangers accommodate the heat removal loads [UFSAR 9.3.3].

The component cooling water pump is designed to deliver 7,500 gpm at 185 feet of developed head to the component cooling water heat exchangers during design basis accident conditions [UFSAR Table 9.3-1].

The pump is operated during nonnal operations and shutdowns to supply cooling vater for the component cooling water system loads [UFSAR 9.3.2]. These funictions are not required for safe shutdown or accident mitigation.

Revision Date: 02/11/04 Page 4 1

IST Program Plan Florida Poiverand Light Company Turkel Point Nuclear Powrer Plant 10 CFR 50.55a Request Number PR-05 (Continued)

Inservice Testing The Component Cooling Water Pumps are centrifugal pumps. These pumps are tested each quarter in accordance with Turkey Point Operating Surveillance *-

OSP-30.1. Due to the configuration of the system the A pump is tested at a flow rate of 6,500 gpm and the B and C pumps are tested at 8500 gpm each quarter.

During this test, the flow rate is set, while the differential pressure is measured.

After tile stabilization period, all required parameters of Table ISTB-3000-1 are measured and compared to the acceptance criteria of Table ISTB-5100-1. Tile design flow rate of the Component Cooling Water Pump is 7,500 gpm.

Therefore the test point of 6,500 gpm, corresponds to 86.7% of the design flow rate for the A pumps while the test point of 8,000 gprn corresponds to 106.7% for the B and C pumps.

Test Results The following data tables indicate the hydraulic test data collected for the last inservice tests. Based on these results, pump operation has been acceptable.

Applying the group A pump acceptance criteria to these pumps indicates acceptable performance. Additionally, if the comprehensive acceptance criteria would be applied, the data would also indicate acceptable performance.

3A Component Cooling Water Pump Test Results

)ate lI.low DP DP Reference Group A Acep Comprehenshe Accept 7/6/03 6500 84.0 87.7 78.9-96.5 81.6-90.3 3B Component Cooling Water Pump Test Results I)ate Hlow 1)1 l 1)1D Reference Group A Accet Comprehensive Accept 7/6103 8000 76.0 79.0 71.1-86.9 73.5-81.4 3C Component Cooling Water Pump Test Results Date MFlo Di' DI) Reference GroupAAccept Comprelhensive Accept 813/03 8000 78.0 82.5 74.3-90.8 76.7-85.0 4A Component Cooling Water Pump Test Results Date F:low lP1) 1' Reference Group A Accept Comprehensive Accept 6129/03 6500 83.0 87.7 78.9-96.5 81.6-90.3 4B Component Cooling Water Pump Test Results I lrate l)P F101A lP Reference Group A Accept Comprehensive Accept 6/27103 8000 77.0 78.5 70.7-86.4 73.0-80.9 4C Component Cooling Water Pump Test Results I)ate Ilow DP 1)1 Reference CroupAAccep ComprehensiveAccept 1 6129103 8000 78.0 78.2 70.4-86.0 72.7-80.5 Revision Date: 02/11/04 Page42

ISTProgram Plan FloridaPowver andLight Company Turkev Point Nuclear Powter Plant 10 CFR 50.55a Request Number PR-05 (Continued)

5. Proposed Alternative and Basis for Use As an alternative to performing Comprehensive Pump tests biennially, the subject pumps will be tested each quarter at +/- 20% of the design flow rate. The required inservice test parameters of Table ISTB-3000-1 based on pump type will be measured and compared to their reference values. The group A pump test acceptance criteria wvill be applied.

Additionally, once every two years, full spectrum analysis wvill be performed above the Code required vibration measurements. Continued Preventive Maintenance, including periodic pump inspections and oil analysis, on each pump will assist in determining overall mechanical and hydraulic pump health.

Based on the preventive maintenance inspection results, full spectrum analysis, and continued quarterly group A testing at +/- 20% of design pump flow, an accurate assessment of pump health and operational readiness is determined on a quarterly frequency.

This alternative provides an acceptable level of quality and safety.

6. Duration of Proposed Alternative This proposed alternative will be utilized for tile entire 4"' 120 month interval.

7. Precedents None Page 43 Revision Rev 02/11/04 ision Date: 02111104 Page 43

IST Program Plan FloridaPowver and Light Comnpany Turkeev Point Nuclear Poiv'er Plant 10 CFR 50.55a Request Number PR-05 (Continued)

Attachment I Intake Cooling Water Pump Curve Head - Feet Intake Cooling Water Pump 140 120 . -..

100.. - .. ._ .-.

80 - - .. -- - - .

60 . ..-. __

40 - .... _

20 . ......

0 . .

0 5000 10000 15000 20000 25000 Flow - GPM A - Pump Design Point (16000 gpm @ 60 feet of developed head)

A - Pump Test Point (set parameter is flow at 15400 gpm)

Revision Date: 02/11/04 Page 44

IST ProgramtPlan FloridaPouierand Light Comnpany Turkeiy Point Nuclear Poiver Plant 10 CFR 50.55a Reatiest Number PR-OS (Continued)

Attachment 2 Component Cooling Water Pump Curve Component Cooling Water Pump 240 *- --

220 200 L 140---.-

120*-.-.-.

100 - -- - - -

0 2000 4000 6000 8000 10000 12000 Flow - GPM A - Pump Design Point (7500 gpm ( 185 feet of developed head)

A\ - Pump Test Point (set parameter is flow at 8000 gpm)

Revision Date: 02/11/04 Page45

IST Programn Plan Florida Powt er and Light Company Turkel' Point Nuclear Powter Plant 10 CFR 50.55a Request Number PR-06 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASME Code Component(s) Affected Pump Number Function 3P21OA Residual Heat Removal 3P210B Residual Heat Removal 4P2 1OA Residual Heat Removal 4P2103B Residual Heat Removal

2. Applicable Code Edition and Addenda ASME OM Code 1998 Edition through 2000 Addenda

3. Applicable Code Requirement ISTB-1400(b), "identify each pump to be tested in accordance with the rules of this Subsection and categorize it as either a group A or group B pump and list the pumps in the plant records (see ISTB-9000). A pump that meets both group A and group B definitions shall be categorized as a group A pump."

4. Reason for Request Pursuant to 10 CFR 50.55a, "Codes and Standards", paragraph (a)(3), relief is requested from the requirement of ASME OM Code ISTB-1400(b). The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

The Residual Heat Removal pumps meet the categorization requirements of group A pumps in that they are operated routinely during plant shutdowns (Mode 5-6). However, these pumps also meet the requirements of group B, in that during normal operation (Modes 1-4) they are not operated except for testing.

During normal power operations, Modes 1-4, the residual heat removal pump is in a standby condition and is considered an essential part of the Emergency Core Cooling System (ECCS). The pump starts automatically upon receipt of a safety injection signal taking suction from the RWST during the injection phase of an accident. The pump is then aligned to take suction from the containment sump during the recirculation phase of an accident. The pump discharges to the reactor coolant system via the residual heat removal heat exchangers. The pump may also be aligned to pump to the suction of either the safety injection pumps or the containment spray pumps depending on plant emergency conditions. During normal plant shutdowns, the residual heat removal pump is used to cool down the reactor coolant system (shutdown cooling). This shutdown cooling function is not required for safe shutdown or accident mitigation.

Rev ision Dale: 02/11/04 Page46

IST Program Plan FloridaPower and Light Company Turkel Point Nuclear Powier Plant 10 CFli 50.55a Request Number PR-06 (Continu(ed)

ASME ISTB-1400(b) states that if a primp meets both group A and group B definitions, it shall be categorized as a group A pump. The Residual Heat Removal pumps are tested during normal operation, Modes 1-4, using the minimum flow recirculation loop. This current test is essentially a group B test in that the pump is operated at low flow conditions (approximately 300 gpm) on minimum flow recirculation. The design flow rate of the Residual Heat Removal Pumps is 3750 gpm. This flow rate can only be achieved during shutdown periods (Modes 5-6) when injection into the reactor coolant system is possible. See Attachment 1, RHR System Diagram. Attachment 2, RI-IR Pump Characteristic Curve is also supplied, The performance of a group A test at these low flow conditions does not reflect the intent of the Code for group A tests. Additionally, these pumps can not be tested as Group A or Comprehensive in these modes due to using the minimum flow recirculation line.

5. Proposed Alternative and Basis for Use Turkey Point Nuclear Plant will test the Residual Heat Removal pumps as standby (group B) during Modes 1-4 and as routinely operated pumps (group A) when the plant is in Modes 5-6. When in cold shutdown or refueling, a comprehensive test may be substituted for the group A test should the comprehensive test schedule come due. ISTB-5000 pennits substitution of a comprehensive test for a group A test.

This alternative is consistent with Generic Letter 89-04, Position 9, in which the NRC determined that, in cases wvlhere flow can only be established through a non-instrumented, minimum flow path during quarterly pump testing, and a path exists at cold shutdown or refueling outages to perfonm a test of the pump under full or substantial flow conditions, the increased interval is an acceptable alternative to the Code requirements.

Therefore testing the Residual Heat Removal pumps as group B during Modes 1-4 and as group A during Modes 5-6 provides reasonable assurance of the operational readiness of the pumps and provides an acceptable level of quality and safety.

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 4th 120 month interval.

7. Precedents Similar relief request PR-12 was previously approved for Calvert Cliffs Nuclear Power Plant on May 16, 2002.

Docket Nos. 50-317 and 50-318 TAC Nos. MB3782 and MB3783 Revision Date: 02/11/04 Page 47

JSTPrograin Plan FloridaPower and Light Conmpany Turkey Point Nuclear PowerPlant 10 CFR 50.55a Request Number PR-06 (Continued)

Attachment I RHR System Diagram Rx Coolant System Cold Legs To Other RHR Pump Revision Date: 02/11/04 Page 48

1ST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Power Plant 10 CFR 50.55a Request Number PR-06 (Continued)

Attachment 2 RHR Pump Characteristic Cunre RHR Pump 400 350 300 -_ __ -_ - ----- __

) 250

' 200 am150 150 l I 100 l 50 0 I I I 0 1000 2000 3000 4000 5000 6000 Flow -GPM A- Full Flow Test Point (3750 gpm @ 240 feet of developed head)

IL- Minimum Flow Test Point (Approximately 300 gpm)

Page 49 Rei'ision Date:

Revision 02/11/04 Date: 02/111/04 Page 49

IST Program Plan FloridaPowver and Light Company Turkey PointNuclear Power Plant ATTACHMENT 4 VALVE RELIEF REQUEST INDEX (Page 1 of I)

Relief Description NRC Approval Date lVR-0 1 lExercise Testing of Option B Check Valves with Il

[Vl lIOnly a Closed Safety Function VR-02 Position Indication Verification Performed in if Accordance with Appendix J Seat Leakage l___ _ lTesting Frequency for Solenoid Operated Valves l lf3 Auxiliary Feedwater Pump Discharge Check I IjValve,20-143, Exercise Frequency I Revision Date: 02/11/04 Page 50

1ST ProgramPlan FloridaPower and Light Company Turkey PointNuclear Power Plant ATTACHMENT 5 VALVE RELIEF REQUESTS Revision Date: 02/11/04 Page S I

IST ProgramPlan FloridaPowser and Light Company Turkey Point NAuclear Power Plant 10 CFR 50.55a Request Number VR-01 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASME Code Component(s) Affected Valve Number Class Category Function BA-3-201 2 AC Containment Breathing Air Isolation Check Valve 3-40-340A 2 AC Instrument Air to Containment Check Valve 3-40-336 2 AC Instrument Air to Containment Check Valve 3-10-567 2 AC Primary Water to Containment Check Valve 3-298A I AC Reactor Coolant Pump Seal Injection Check Valve 3-298B I AC Reactor Coolant Pump Seal Injection Check Valve 3-298C I AC Reactor Coolant Pump Seal Injection Check Valve 3-945E 2 AC Nitrogen Supply to Accumulators Check Valve 3-518 2 AC Nitrogen Supply to Pressurizer Relief Tank 3-519 2 AC Nitrogen Supply to Pressurizer Relief Tank BA-4-201 2 AC Containment Breathing Air Isolation Check Valve 4-40-340A 2 AC Instrument Air to Containment Check Valve 4-40-336 2 AC Instrument Air to Containment Check Valve 4-10-567 2 AC Primary Water to Containment Check Valve 4-298A 1 AC Reactor Coolant Pump Seal Injection Check Valve 4-298B 1 AC Reactor Coolant Pump Seal Injection Check Valve 4-298C 1 AC Reactor Coolant Pump Seal Injection Check Valve 4-945E 2 AC Nitrogen Supply to Accumulators Check Valve 4-518 2 AC I Nitrogen Supply to Pressurizer Relief Tank 4-519 2 AC Nitrogen Supply to Pressurizer Relief Tank

2. Applicable Code Edition and Addenda ASME OM Code 1998 Edition through 2000 Addenda

3. Applicable Code Requirement ISTC-3510 Exercising Test Frequency, states that "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC 3560, ISTC-5221, and ISTC-5222.".

Specifically, relief is requested from performing both the open and closed exercise tests in accordance with ISTC-3510. These valves will be exercised open and closed commensurate Appendix J Option B test frequency requirements.

Revision Date: 02/11/04 Page 52

ISTProgramPlan FloridaPower andLight Company Turkey Point Nuclear PowerPlant 10 CFR 50.55a Request Number VR-01 (Continued)

4. Reason for Request Pursuant to 10 CFR 50.55a, "Codes and Standards", paragraph (a)(3), relief is requested from the requirement of ASME OM Code ISTC-3510. The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

The subject valves are all categorized as AC and are all considered containment isolation valves per the plant safety analysis. All of the subject valves have a safety function to close in order to isolate containment from their respective non-safety related systems during a Loss of Coolant Accident (LOCA) requiring containment isolation. The open function for each of these valves is considered a non-safety function since the systems are not required to shut the plant down to a safe shutdown condition, maintain safe shutdown or mitigate the consequences of an accident (See IST Basis Documents - Safety Function in Attachment 1). However, the current ASME OM Code requirements complied with by Turkey Point (1998 Edition through 2000 Addenda) for the 4 th 120-Month Interval, requires testing of the non-safety "open" direction function of each of these check valves.

The Code required frequency specified in ISTC-3520 is once every quarter with the exceptions listed above. Those exceptions which apply to check valves are ISTC-3520, ISTC-5221 and ISTC-5222.

Since these valves can be exercised adequately with flow in the open direction and seat leakage tested in the reverse direction, they are not candidates for a disassembly and examination program or condition monitoring program as delineated in ISTC-5221 and ISTC-5222 respectively.

Therefore the frequency requirements of ISTC-3520 would typically apply. That is, if exercising is not practicable during normal power operations the exercising shall be performed during cold shutdowns. If exercising is not practicable during normal power operations and cold shutdown, exercising shall be performed during refueling outages.

Each of the subject valves is required to be exercised both open and closed and seat leakage tested in accordance with the inservice testing requirements of Table ISTC-3500-1, INSERVICE TESTING REQUIREMENTS. For all of the subject valves, the seat leakage test constitutes the exercise closed test. This frequency is in accordance with the Appendix J frequency, since the only safety function of the valves in the closed direction is for containment isolation only. (See ISTC-3620 and Attachment 1, 1ST Basis Documents - Safety Function)

The open, non-safety direction test, can only be performed using flow when the containment isolation seat leakage test is performed, and only during refueling outages when containment entry is possible. Since the individual valve being tested must have its system properly drained, vented, and aligned correctly prior to performing the seat leakage test, an opportune window will exist to perform the open check valve test using flow. Additionally, test personnel, radiation exposure, and time/labor involved will be significantly reduced by performing the open exercise test along with the seat leakage/closure test (keeping in mind that this open test is the non-safety position test).

On October 4, 1996, Turkey Point received a Safety Evaluation with approval to implement Option B of the IOCFR50 Appendix J Program. (Technical Specification Revision Date: 02/11/04 Page 53

lSTProgram Plan FloridaPowerand Light Company Turkey Point Nuclear Powver Plant 10 CFR 50.55a Request Number VR-01 (Continued)

Amendments 192/186 for Unit #3 and #4 respectively). This program permits the extension of the Appendix J seat leakage testing to a frequency corresponding to the specific valve performance. Valves whose leakage test results indicate good performance may have their interval of testing increased based on these test results. The Turkey Point administrative program which implements Appendix J Option B requires individual containment isolation valves to pass four successful seat leakage tests before it can be included in the Option B program.

5. Proposed Alternative and Basis for Use For the subject valves, Turkey Point Nuclear Plant will perform the check valve closure test in conjunction with the seat leakage test at a frequency in accordance with IOCFR50 Appendix J. The corresponding check valve open test (non-safety direction) will be performed at the same interval as the check valve closure test. This interval may be adjusted to a frequency of testing commensurate with Option B of IOCFR50 Appendix J Type C leakage testing based on valve seat leakage performance.

The only safety function of these valves is to provide a containment isolation barrier.

Since they are not connected to any ECCS system and the open function is not required for safe shutdown or accident mitigation, a seat leakage test is their primary functional test. By verification of forward flow, along with a seat leakage test, an adequate assessment of valve health may be determined.

Performance of the both the open and closed tests during the same frequency has been endorsed by the ASME OM Code as stated in ISTC-3522(a), which states that "open and closed tests need only be performed at an interval when it is practicable to perform both tests". Additionally, performance of the check valve open test will include verification of fluid flow to open the check valve. This test will be performed during the same surveillance which seat leakage tests the valve (*-OSP-51.5) and will be scheduled and documented in the plant record system. Corrective actions will be taken in accordance with ISTC-5224 as stated.

Additionally, all of the subject check valves are included in the plant Check Valve Program which monitors check valve test performance, work history, industry experience and vendor correspondence to determine preventive maintenance (PM) activities. The Turkey Point Option B program further monitors the performance of the valve in that the allowable seat leakage limits for each individual valve are administratively set well below the Appendix J limit.

Therefore, the ability to detect degradation and ensure the operational readiness of the subject check valves to perform their intended function is not jeopardized by performing the open and closed check valve tests at the same frequency as specified by Option B.

This frequency of testing provides reasonable assurance of the operational readiness of the subject check valves and provides an acceptable level of quality and safety.

Revision Date: 02/11/04 Page54

IST Program Plan FloridaPowerand Light Company Turkey PointNuclear Power Plant 10 CFR 50.55a Request Number VR-0I

. (Continued)

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 4 th 120 month interval.

7. Precedents None Revision Date: 02/11/04 Page 55

1ST Program Plan FloridaPower andLight Company Turkey Point Nuclear Power Plant 10 CFR 50.55a Request Number VR-01 (Continued)

Attachment 1 IST Basis Documents - Safety Function Valve Group - BA-201, Containment Breathing Air Isolation Check Valve This check valve must close to isolate containment from the breathing air system. This valve provides containment isolation for Penetration 30. Penetration 30 is considered a non essential penetration which is not required to be in service post accident [UFSAR Table 6.6-1].

This valve opens to provide a flowv path from the breathing air receiver to containment during cold shutdown or refueling [5613/5614-M-3 101-1]. This function is not required for safe shutdown or accident mitigation. The breathing air system is only required to function during cold shutdown or refueling [0-OP-101]. Additionally, upstream air operated valve CV-*-6165 outside containment is administratively maintained in the locked and pinned closed position during normal plant operation [0-OSP-205].

This penetration is isolated during all modes of operation when containment integrity is required and is not in service during any emergency or post accident conditions [0-OP-101]. Therefore, this valve only performs a containment isolation function and is not required to open or close for any other safety function.

Since the valve is normally closed, with the upstream piping administratively locked and pinned closed by CV-*-6165, and a dead leg exists downstream, this valve is considered passive. No exercising is required.

Penetration 30 BA-N3 _2l3 BA-3112 cv-Jei FROM HEADER tCOMPRESSORS B 26 , BA-3 20 BA-3-114 fA-3-113 Valve Group-340A, Instrument Air to Containment Check Valve This check valve must close to isolate containment from the non safety instrument air system. This valve provides containment isolation for Penetration 29 [UFSAR Table 6.6-1]. The valve opens to provide a flow path of instrument air to the containment supply header when the instrument air system is operating. This function is not required safe shutdown or accident mitigation since the instrument air system is non safety related. Safety related equipment normally supplied by the instrument air system is designed to either fail to the required safe position or is provided with a safety related backup pneumatic supply. [UFSAR 9.17]

Penetration 29 I

I 3-40-340A 3-40-362 I

I Page 56 Revision Date: 02/11/04 Date: 02/11/104 Page 56

1ST ProgramPlan FloridaPowerand Light Company Turkey Point NuclearPowrer Plant 10 CFR 50.55a Reauest Number VR-01 (Continued)

Attachment I (Continued)

IST Basis Documents - Safety Function Valve Group-336, Instrument Air to Containment Check Valve This check valve must close to isolate containment from the non safety instrument air system. This valve provides containment isolation for Penetration 29 [UFSAR Table 6.6-l].

The valve opens to provide a flow path of instrument air to the containment supply header when the instrument air system is operating. This function is not required safe shutdown or accident mitigation since the instrument air system is non safety related. Safety related equipment normally supplied by the instrument air system is designed to either fail to the required safe position or is provided with a safety related backup pneumatic supply. [UFSAR 9.17]

Penetration 29 3 D3-40361 ro 3A40340A 3-40336

,-ONT j go 9 - ^>

3-03408 CV-3-2803 343A 340-336B 340-336A A3-40.362 3 j 3-40.709 Valve Group - 567, Primary Water to Containment Check Valve This check valve must close to isolate containment from the primary water system. This valve provides containment isolation for Penetration 47. Penetration 47 is considered a non essential penetration which is not required to be in service post accident [UFSAR Table 6.6-1].

This valve opens to provide a flow path from the primary water supply header to containment during cold shutdown or refueling. This function provides a supply source to facilitate maintenance and testing during outages [OP-020]. This function is not required for safe shutdown or accident mitigation. Additionally, downstream manual valve *-10-582 inside containment is administratively maintained in the locked closed position during normal power operations [OP-020/OSP-205]. The primary water system is not required for safe shutdown [UFSAR 9.6.2]. This penetration is isolated during all modes of operation when containment integrity is required and is not in service during any emergency or post accident conditions.

Therefore this valve only performs a containment isolation function and not required to open or close for any other function. Since the valve is normally closed, since a dead leg exists downstream, this valve is considered passive. No exercising testing is required.

Penetration 47 RV-3-302 L lCK-3-10-567 3-10-584 3-10-582 3-10-583 To Containment l -

P.W.Serevie 3-10-586 Header 10-580 i

Revision Date: 02/11/04 Page 57

ISTProgramPlan FloridaPoiwerand Light Company Turkey Point Nuclear Power Plant 10 CFR 50.55a Request Number VR-01 (Continued)

Attachment 1 (Continued)

IST Basis Documents - Safety Function Valve Group - 298A/1B/C, Reactor Coolant Pump Seal Injection Check Valve This check valve must close to isolate containment from the chemical and volume control system during accident conditions when RCP seal injection flow is not required. The valve is considered a containment isolation valve for Penetration 24A/B/C [UFSAR Table 6.6-1).

This check valve opens to provide a flow path from the charging pump to the reactor coolant pump seals during normal plant operation [UFSAR 9.2.2]. This function is not required for safe shutdown or accident mitigation since the reactor coolant pumps are not required for safe shutdown or accident mitigation.

[UFSAR 4.1.1] Additionally, the seal injection return valves (MOV-*-381 and MOV-8-6386) receive automatic closure signal to isolate the seal injection return flow path during a safety injection [UFSAR Table 6.6-1]

Penetration 24A. B and C

-2850 OD CK-3-298A n29 A 3-285E 3-28i CK;3-298BY 3-297B CHARGING PUMP INJECTION SEAL WATER Revision Date: 02/11/04 Page58

1ST Program Plan FloridaPower andLight Company Turkev Point Nuclear Power Plant 10 CFR 50.55a Request Number VR-01 (Continued)

Attachment I (Continued)

IST Basis Documents - Safety Function Valve Group - 945E, Nitrogen Supply to Accumulators Check Valve This check valve must close to isolate containment from the non safety related nitrogen supply system during accident conditions. This valve is considered a containment isolation valve for Penetration 42

[UFSAR Table 6.6-I].

The valve opens to support safety injection accumulator refill to recharge and maintain the accumulators pressurized during normal power operations [*-OP-064]. This function is not required for safe shutdown or accident mitigation since the safety injection accumulators are considered a passive injection system and tank pressure is continuously monitored during normal plant operations [UFSAR 6.2].

Perrtrmtion 42 TO FLX MAPPER 3G61OL Valve Group - 518/519, Nitrogen Supply to Pressurizer Relief Tank This check valve must close to isolate containment from the non safety nitrogen supply system. This valve provides containment isolation for Penetration 6 [UFSAR Table 6.6-1].

The valve opens to provide a flow path from the nitrogen supply header to the pressurizer relief tank. This function is not required safe shutdown or accident mitigation since the nitrogen system is non safety related. The pressurizer relief tank is designed for full vacuum conditions to prevent tank collapse if the tank contents cool without nitrogen being supplied. [UFSAR 4.2]

Penetration 6 351 8 PAT I 3-5A Revision Date: 02/11/04 Page 59

IST ProgramPlan FloridaPowerand Light Company Turkev PointNuclear Power Plant 10 CFR 50.55a Request Number VR-02 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASME Code Component(s) Affected Valve Number Class Category Function SV-3-6385 2 A Pressurizer Relief Tank Vent Sample Isolation SV-3-6427A 2 A Reactor Coolant System Hot Leg Sample Isolation SV-3-6427B 2 A Reactor Coolant System Hot Leg Sample Isolation SV-3-6428 2 A Reactor Coolant System Hot Leg Sample Isolation SV-3-2911 2 A Continuous Containment Air Monitor Isolation SV-3-2912 2 A Continuous Containment Air Monitor Isolation SV-3-2913 2 A Continuous Containment Air Monitor Isolation SV-4-6385 2 A Pressurizer Relief Tank Vent Sample Isolation SV-4-6427A 2 A Reactor Coolant System Hot Leg Sample Isolation SV-4-6427B 2 A Reactor Coolant System Hot Leg Sample Isolation SV-4-6428 2 A Reactor Coolant System Hot Leg Sample Isolation SV-4-2911 2 A Continuous Containment Air Monitor Isolation SV-4-2912 2 A Continuous Containment Air Monitor Isolation SV-4-2913 2 A Continuous Containment Air Monitor Isolation

2. Applicable Code Edition and Addenda ASME OM Code 1998 Edition through 2000 Addenda

3. Applicable Code Requirement ISTC-3700 Position Verification Testing, states "Valves with remote position indicators shall be observed locally at least once every 2 years to verify that valve operation is accurately indicated."

Specifically, relief is requested from performing the position indication verification on a 2 year frequency. Position indication verification will be performed at a frequency commensurate with the Option B test frequency for performing leakage rate testing.

4. Reason for Request Pursuant to 10 CFR 50.55a, "Codes and Standards", paragraph (a)(3), relief is requested from the requirement of ASME OM Code ISTC-3700. The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

The subject valves are all categorized as AC and are all considered containment isolation valves per the plant safety analysis. All of the subject valves have a safety function to close in order to isolate containment from their respective non-safety related systems during a Loss of Coolant Accident (LOCA) requiring containment isolation.

Revision Date: 02/11/04 Page 60

IST ProgramPlan FloridaPower and Light Company Turkey PointNuclear Power Plant 10 CFR 50.55a Request Number VR-02 (Continued)

Since these valves are considered containment isolation valves, they are each individually seat leakage testing in accordance with IOCFR50 Appendix J. The test arrangement for each valve is listed in Attachment I - Local Leak Rate Test Diagrams. Note that only the test arrangements for Unit #3 are provided in the attachment. Unit #4 is typical.

Each of the subject valves is a solenoid operated valve designed such that the position of the valve is not locally observable. The design of these valves is such that the coil position is internal to the valve body and not observable in either the energized or de-energized state. See Attachment 2 - Typical Solenoid Valve Diagram, which is typical for the subject valves.

In accordance with ISTC-3700, where local observation is not possible, other indications shall be used to verify valve position. The method used a Turkey Point is a pressure test using the local leakage rate testing equipment. This method involves pressurizing the containment penetration volume to approximately 40 psia, and verifying the penetration remains pressurized while the valve is indicating closed on the main control room board.

The valve is then opened using the control switch in the main control room. A decrease in pressure is then verified along with valve position indicating open in the main control room. This method satisfies the requirement for position indication verification and ensures that the indicating system accurately reflects the valve position.

Since each of these valves is seat leakage tested using local leakage rate testing equipment during refueling outages, the current leakage rate tests have been modified to also perform the position indication verification test at the same time. Since the individual valve being tested must have its system properly drained, vented, and aligned correctly prior to performing the seat leakage test, an opportune window exists to perform the position indication verification. Additionally, test personnel, radiation exposure, and time/labor involved will be significantly reduced by performing the position indication verification test along with the seat leakage test.

On October 4, 1996, Turkey Point received a Safety Evaluation with approval to implement Option B of the IOCFR50 Appendix J Program. (Technical Specification Amendments 192/186 for Unit #3 and #4 respectively. This program permits the extension of the Appendix J seat leakage testing to a frequency corresponding to the specific valve performance. Valves whose leakage test results indicate good performance may have their interval of testing increased based on these test results. The Turkey Point administrative program which implements Appendix J Option B requires individual containment isolation valves to pass four successful seat leakage tests before it can be included in the Option B program.

5. Proposed Alternative and Basis for Use For the subject valves, Turkey Point Nuclear Plant will perform the position indication verification in conjunction with the seat leakage test at a frequency in accordance with IOCFR50 Appendix J. This interval may be adjusted to a frequency of testing commensurate with Option B of IOCFR50 Appendix J Type C leakage testing based on valve seat leakage performance.

02/11/04 Page 61 Revision Date: 02111104 Revision Date: Page6 1

ISTProgram Plan FloridaPower andLight Company Turkey Point Nuclear Power Plant 10 CFR 50.55a Request Number VR-02 (Continued)

Additionally, each of these subject valves is exercised on a quarterly frequency and their stroke times measured and compared to the ASME OM Code acceptance criteria. By continuing quarterly valve exercising and performance of the position indication verification and seat leakage test in accordance IOCFR50 Appendix J, an adequate assessment of valve health may be determined..

Therefore, the ability to detect degradation and ensure the operational readiness of the subject valves to perform their intended function is not jeopardized by performing the position indication verification test at the same frequency as specified by Option B. This frequency of testing provides reasonable assurance of the operational readiness of the subject valves and provides an acceptable level of quality and safety.

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 4 th 120 month interval.

7. Precedents None Revision Date: 02/11/04 Page 62

1ST ProgramPlan FloridaPowver and Light Company Turkey Point Nuclear Power Plant 10 CFR 50.55a Request Number VR-02 (Continued)

Attachment 1 Local Leak Rate Test Diagrams Valve Group - SV-*-6385 Penctrtmion 5 II I

FROM PRT 5 SV-3-8385 C 616 pCV.3-480 34600fA 51SiA 3-51CC 3-5160 bkt372 Valve Group - SV-*-6427AfB and SV-*-6428 Penetration 20 SAMPLE 3-995C I ROOM I TO SAMPLE RHX oms TO PASS PASS-3010 3-997D SV-3-6427B Page 63 Date: 02/11/04 Revision Date: 02111104 Page 63

1ST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Power Plant 10 CFR 50.55a Request Number V"R-02 (Continued)

Attachment I Local Leak Rate Test Diagrams (Continued)

Valve Group - SV-*-2912 Penetnrtion 32 Valve Group - SV-*-2911/2912 Penetration 33 I

Page 64 Revision Date: 02/11/04 Revision Date: 02/11/104 Page 64

IST ProgramPlan FloridaPowver andLight Company Turkev Point Nuclear Powter Plant 10 CFR 50.55a Request Number VR-02 (Continued)

Attachment 2 Typical Solenoid Valve Diagram ITEM DESCRIPTION ITEM DESCRIPTION I Cover Bolts 10 Seal 2 Locknut 11 Nameplate 3 Cover 12 Strap 4 O-Ring 14 Buckle 5 Bolt 15 Bolt 6 Lockwasher 16 Lockwasher 8 Switch Block Assy. 17 Spacer 9 Coil Shell Assy.

Page 65 Revision Date: 02/11/04 Date: 02111104 Page 65

ISTProgranm Plan FloridaPower andLight Company Turkey Point Nruclear PowerPlant 10 CFR 50.55a Request Number VR-03 Relief Requested In Accordance with 10 CFR 50.55a(a)(3)(ii)

Hardship or Unusual Difficulty without Compensating Increase in Level of Quality or Safety

1. ASME Code Comnonent(s) Affected V'alve Number Class Category Function 20-143 3 C Auxiliary Feedwater Pump Train A Discharge l Check Valve

2. Applicable Code Edition and Addenda ASME OM Code 1998 Edition through 2000 Addenda

3. Applicable Code Requirement ISTC-3510 Exercising Test Frequency, states that "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC 3560, ISTC-5221, and ISTC-5222.".

Specifically, relief is requested from performing the closed exercise test in accordance with ISTC-35 10.

4. Reason for Renuest Pursuant to 10 CFR 50.55a, "Codes and standards," paragraph (a)(3), relief is requested from the requirement of ASME OM Code, ISTC-3510. The basis of the relief request is that the Code requirement presents an undue hardship without a compensating increase in level of quality or safety.

The subject valve,20-143 is categorized as C in the Inservice Testing Program with both an open and closed safety function. The following Inservice Testing Basis Document describes the valve functions in detail (See Attachment I - AFW System Diagram).20-143 Basis This check valve must open to provide a flow path from the auxiliary feedwater pump to the steam generators when the auxiliary feedwater pump is required to be operated. The auxiliary feedwater pump takes suction from the condensate storage tank. [UFSAR 9.11]

This check valve must open to provide 466.8 gpm of auxiliary feedwater flow to the steam generators to maintain sufficient water level in the steam generators of both units.

This flow rate is based on one AFW pump supplying a total of 233.4 gpm to three steam generators, the AFW system being shared between the units, and a loss of AC power simultaneously on both units. [UFSAR 14.1.12]

Revision Date: 02/11/04 Page 66

1ST Program Plan FloridaPower and Light Company Turkey Point Nuclear Power Plant 10 CFR 50.55a Request Number VR-03 (Continued)20-143 Basis (continued)

This check valve must close to prevent diversion of flow when the Auxiliary Feedwater Pump C is supply the Train I discharge header. This function is necessary in the event that the Auxiliary Pump A is out of service with Pump C is supplying Train I auxiliary feedwater. This alignment is considered an infrequent operation (*-OP-75) and is not the preferred alignment of the system. Additionally, downstream manual isolation valve *-

142 may be closed after alignment of the C pump to the Train I discharge header.

However, for a brief period time, prior to closure of the manual valve, this check valve must close.

During normal system alignment, this check valve closes when the auxiliary feedwater pump is not in operation to prevent reverse flow. Since Train I is normally isolated from Train 2 closure of this valve to prevent diversion of flow is not required. [UFSAR 9.11]

Isolation of the Train I auxiliary feedwater during a steam generator tube rupture event is accomplished by closing the downstream flow control valve on the affected steam generator [UFSAR 14.2.4/DBD-075]. Therefore the closure of this valve is not required for safe shutdown or accident mitigation during normal system alignment.

Inservice Testing Requirements - Exercise Open and Closed on a Quarterly Frequency Check valve 20-143 is exercised open on a quarterly frequency with flow during the performance of the quarterly inservice test of the "A" Auxiliary Feedwater Pump. *-

OSP-75.6 verifies that during pump testing, design accident flow rate is achieved downstream of the check valve (> 466.8 gpm). Achieving this flow rate verifies the ability of check valve 20-143 to open to the position required to fulfill its intended function and satisfies the open exercise test requirements.

To test check valve 20-143 closed requires removing the Train 1, (Auxiliary Feedwater Pump A) from service and performing a reverse flow test to verify check valve closure.

Since the Auxiliary Feedwater System at Turkey Point is a shared system, when the Train I pump (AFW Pump A) is removed from service, both Unit #3 and #4 Train I is supplied by the C AFW pump. In accordance with Turkey Point Operating Procedure, OP-75, the C AFW pump is manually aligned to the Train I supply piping by alignment of manual valves (See Attachment 1). Prior to declaring the pump operable in this configuration the corresponding Inservice Test is performed on the C AFW pump to ensure AFW Train Operability requirements are met in accordance with plant Technical Specification Table 3.7-3. During this test the AFW Pump A Train I supply manual isolation valve *-142 may be left locked open to allow flow from the C AFW pump to close valve 10-142.

Since this manual valve is the only isolation valve between the A AFW Pump Train I and AFW Pump C when it is aligned to Train 1, it is then closed to provide additional isolation should maintenance be required on the A AFW Pump. Afier testing is complete and the manual isolation valve (*-142) is closed, check valve 20-143 does not perform any safety function. Isolation of the out of service A AFW Pump is provided by the manual isolation valves.

Page 67 Revision Date: 02/11/04 Date: 02111104 Page67

ISTProgramnPlan FloridaPowver and Light Company Turkev Point Nuclear Powver Plant 10 CFR 50.55a Request Number VR-03 (Continued)

Therefore, check valve 20-143 performs a closed safety function only during a limited time period when the AFW system Train I is being aligned from C AFW Pump.

Manual isolation valves, *-142 are included in the Inservice Testing Program and tested in accordance with ISTC.

5. Proposed Alternative and Basis for Use Turkey Point Nuclear Plant will continue to perform the full open exercise test on check valve 20-143 during the quarterly during performance of the A AFW pump inservice test.

The closure test of 20-143 will be performed only when the A AFW pump is taken out of service for maintenance. Since the C AFW pump will be operated to verify operability of Train I in accordance with Technical Specification Table 3.7-3 during this period, check valve 20-143 may be tested close.

To test this check valve closed requires removing the A AFW Pump from service and operating the C AFW Pump to verify closure. Although this test is not difficult, it does place undue hardship on the plant by placing the Auxiliary Feedwater System in an undesirable configuration without the designed redundancy. Since no function exists for check valve 20-143 during normal system alignment, the frequency of testing provides reasonable assurance of the operational readiness of the subject valve and provides an acceptable level of quality and safety. Strict adherence to the Code test frequency for testing the valve closed does not provide any increase in the level of quality or safety.

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 4 th 120 month interval.

7. Precedents None Page 68 Revision Date: 02/11/04 Date: 02111104 Page 68

1ST Program Plan FloridaPoiverand Light Company Turkey Point Nuclear Power Plant 10 CFR 50.55a Request Number VR-03 (Continued)

Attachment 1 AFWN' System Diagram 3-20-142 Steam Generator A Steam Generator B Steam Generator C Train 1

- - - - - - - - - - Train 2 Note: Manual valves AFPD-001002/003 and 14212421342 are nomially Woced Inthe positions shown.

Revision Date: 02/11/04 Page69

1ST ProgramPlan FloridaPowver andLight Company Turkey Point Nuclear Power Plant ATTACHMENT 6 COLD SHUTDOWN JUSTIFICATION INDEX (Page I of 1)

Cold Shutdown Description Justification No.

CSJ-01 l AFW Turbine Steam Supply Valve (381/382/383) Closure Testing CSJ-02 l[ Containment Purge Supply/Exhaust Valve Exercising CSJ-03 ll Safety Injection Hot Leg Injection Valve (MOV-*-866A/B) Exercising CSJ-04 Safety Injection Pump Discharge Header Cross Tie Valve (MOV-878A/B) 11Exercising CSJ-05 ]` Sl/CS Recirc to RWST Valve (MOV-*-856A/B) Exercising CSJ-06 1jRWST Outlet Isolation Valve (MOV-*-864A/B) Exercising CSJ-07 l[ SI Cold Leg Injection Check Valve (*-875A/B/C) Exercise Close Test CSJ-08 lFRHR Cold Leg Injection Check Valve (*-876A/B/C) Exercise Close Test CSJ-09 Component Cooling to Excess Letdown Hx Check Valve (*-738) Exercise Close l Test CSJ-10 ll CCW to Containment Cooler Valve (MOV-*- 1417/1418) Exercising CSJ-l I ][ CCW to RCP Valve (MOV-*-626/716A/B/730) Exercising CSJ-12 ][ Main Steam Non-Return Check Valve (*-10-4/5/6) Close Exercise Test CSJ-13 l[ Main Steam Atmospheric Dump Valve (CV-*-16O6/7/8) Exercising CSJ-14 J( RHR to Cold Leg Injection Valve (MOV-*-744A/B) Exercising CSJ-15 1F SI Accumulator Isolation Valve (MOV-*-865A/B/C) Exercising CSJ-16 CVCS Letdown Line Isolation Valve (CV-*-204) Exercising CSJ- 17 J! Feedwater Control Valve (FCV-*-478/488/498) Exercising CSJ-18 ]l Feedwater Control Valve Bypass Valve (FCV-*-479/489/499) Exercising CSJ-19 1( CVCS Charging to Regen Hx Valve (HCV-*- 121) Exercising CSJ-20 ][ RWST to Charging Suction Valve (LCV-*-I 115B) Exercising CSJ-21 CVCS VCT to ChargingValve (LCV-*- 15C) Exercising CSJ-22 l[ Emergency Boration to Charging Check Valve (*-357) Open Exercise Test CSJ-23 l[ Power Operated Relief Valve (PCV-*-455C/456) Exercising CSJ-24 ll Reactor Vessel Head Vent Valve (SV-*-6318A/B/6611/6612) Exercising CSJ-25 Reactor Coolant Pump Return Valve (MOV-*-381/63 86) Exercising CSJ-26 ]l RHR Suction from RWST Isolation Valve (MOV-*-862A/B) Exercising CSJ-27 ] Reactor Coolant System RHR Suction Valve (MOV-*-750/75 1) Exercising CSJ-28 l RHR Alternate Discharge Isolation Valve (MOV-*-863A/B) Exercising CSJ-29 JI RHR Pump Discharge Check Valve (*-753A/B) Open/Close Exercise Test CSJ-30 ll Main Steam Isolation Valve (POV-*-2604/2605/2606)Close Exercise Test CSJ-31 0 RHR Alternate Low Head Safety Injection Valve (MOV-*-872) Exercising Revision Date: 02/11/04 Page 70

1STProgramPlan FloridaPowerand Light Company Turkev Point Nuclear Power Plant ATTACHMENT 7 COLD SHUTDOWN JUSTIFICATIONS Revision Date: 02/11/04 Page 7 1

1ST ProgramPlan FloridaPoiwer andLight Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-01 Component TaE System Safetv Class Cateeory 3-10-381 075 3 C 3-10-382 075 3 C 3-10-383 075 3 C 4-10-381 075 3 C 4-10-382 075 3 C 4-10-383 075 3 C Function These check valves open to provide a flow path from the steam generators to the auxiliary feedwater pump turbine when the auxiliary feedwater pump is required to be operating. They close to prevent backflow in the event of a steam line rupture upstream of the valve and to prevent reverse flow between the units.

Justification It is impracticable to exercise these check valves closed during normal power operation since closure testing at normal power imposes a significant safety hazard to plant personnel.

To verify closure of these valves requires isolation of the associated steam supply line from the steam generator and depressurization of the line on the upstream side of the valve. During normal operations, steam in excess of 800 psig is required to be vented to allow the valve to close. This testing imposes a significant safety hazard on plant personnel. Additionally, to performn this testing during normal plant operations, the auxiliary feedwater system would be required to be placed in an undesirable lineup.

Alternative Test These check valves will be exercised closed during cold shutdowns when auxiliary steam at much lower pressure (approximately 250 psig) may be used to close the valve.

Page 72 Revision Date: 02/11/04 Date: 02/111/04 Page 72

]ST Program Plan FloridaPower andLight Company Turkey Point Nuclear PowerPlant Cold Shutdown Justification CSJ-02 Component Ta System Safety Class Cate2ory POV-3-2600 053 2 A POV-3-2601 053 2 A POV-3-2602 053 2 A POV-3-2603 053 2 A POV-4-2600 053 2 A POV-4-2601 053 2 A POV-4-2602 053 2 A POV-4-2603 053 2 A Function These normally closed, air operated valves must close/remain closed to isolate containment from the Containment Purge Supply line. The valve closes automatically upon receipt of a Containment Ventilation System (CVS) Isolation signal. Additionally, this valve fails closed on loss of electrical power or pneumatic supply. This valve is opened to purge containment to support personnel entry - during unit shutdowns.

Justification It is impracticable to exercise these butterfly valves closed during normal power operation since closure testing at normal power imposes possible operational considerations regarding valve operability.

To verify closure of these valves requires opening of the valve to perform exercise and fail safe testing. Opening of the valve during normal plant operations may cause significant operability concerns based on the valve design. Due to the history of these valves with respect to operational-related seat leakage, the plant staff has imposed restrictions on valve operation whereby unnecessary cycling of the valves is to be avoided and additional leaktests are performed based on cycling frequency. The plant staff has administratively controlled the operating cycles (fuses not normally installed) such that cycling of these valves at power is allowed only when absolutely necessary.

Alternative Test These valves will be exercised closed and fail safe tested during cold shutdowns when containment integrity is not required.

Revision Date: 02/11/04 Page 73

1ST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-03 Component TaL System Safeh' Class Catceory MOV-3-866A 062 1 A MOV-3-866B 062 1 A MOV-4-866A 062 1 A MOV-4-866B 062 1 A Function These motor operated valve must close or remain closed to isolate the hot leg injection line from the safety injection system during emergency conditions when hot leg injection is not required.

This function ensures adequate core filling and cooling through the cold legs during a loss of coolant accident. The valve is maintained administratively locked closed with the breaker open to ensure valve closure since initial accident conditions require core cooling through the cold legs.

This valve also receives a safety injection signal (SIS) to close to isolate containment from the safety injection system. The valve is required to open to provide a flow path from the safety injection pump to the reactor coolant system hot leg, during hot leg recirculation operation This function requires operator action to open the valve since it is normally closed with the breaker in the locked open position Justification It is impracticable to exercise these valves open or closed during normal power operation since opening of this valve during normal power operations places the plant in an undesirable configuration.

Exercising this valve open or closed requires aligning the system in a configuration where the Class I reactor coolant system is isolated from the lower pressure Class 2 safety injection system by only one valve (simple check). This configuration would place the plant in an undesirable alignment and cause undue risk.

Alternative Test These valves will be exercised open and closed during cold shutdowns when reactor coolant system pressure is below 600 psig.

Revision Date: 02/11/04 Page 74

1ST Program Plan FloridaPower andLight Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-04 Component Tat SVstem Safety Class Catcorv MOV-878A 062 2 B MOV-878B 062 2 B Function These motor operated valves must remain open to provide a flow path from the safety injection pump to the opposite unit during the injection phase of safety injection following a loss of coolant accident. The valves are maintained in the open position during normal power operations due to single failure analysis requiring at least two safety injection pumps for injection into the reactor coolant system. These valves may be closed prior to switch over to the recirculation phase of safety injection to isolate the non accident unit piping from the contaminated recirculated water on the accident unit.

Justification It is impracticable to exercise these valves closed during normal power operation since closure of this valve during normal power operations places the plant in an undesirable and unanalyzed configuration.

Exercising these valves closed places the plant in a condition where the shared safety injection pumps are not available as required. Closure of the valves solely for testing would place the plant in an undesirable alignment and cause undue risk.

Alternative Test These valves will be exercised closed during cold shutdowns when the safety injection system is not required to be operable for the opposite unit.

Revision Date: 02/11/04 Page 75

ISTProgram Plan FloridaPower and Light Company Turkey Point Nuclear Poster Plant Cold Shutdown Justification CSJ-05 Component Tan Svstem Safetv Class Categorv MOV-3-856A 062 2 B MOV-3-856B 062 2 B MOV-4-856A 062 2 B MOV-4-856B 062 2 B Function These motor operated valves must remain open to provide a flow path from the safety injection and containment spray pumps to the RWST during the injection phase of an accident to prevent potential pump damage. Theses valves are maintained in the open position during normal power operations and do not receive any automatic actuation signals. Theses valves may be closed prior to switch over to the recirculation phase of safety injection to isolate the RWST from the containment spray and safety injection pumps. This function prevents contamination of the RWST.

Justification It is impracticable to exercise these valves closed during normal power operation since closure of this valve during normal power operations places the plant in an undesirable and unanalyzed configuration.

Exercising these valves closed places the plant in a condition where the associated safety injection pump may be damaged, if started, since the recirculation line would be isolated.

Closure of the valves solely for testing would place the plant in an undesirable alignment and cause undue risk.

Alternative Test These valves will be exercised closed during cold shutdowns when the safety injection pumps and containment spray pumps are not required to be operable.

Revision Date: 02/11/04 Page76

1ST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-06 Component Tag Svstem Safetv Class Catelorv MOV-3-864A 062 2 B MOV-3-864B 062 2 B MOV-4-864A 062 2 B MOV-4-864B 062 2 B Function These normally open motor operated valves must remain open to provide a flow path from the RWST to the suction of the safety injection, containment spray, and residual heat removal pumps during the injection phase of an accident. These valves are maintained administratively locked open with their breakers open to ensure the valve remains open during the injection phase. The valves must close prior to switch over to the recirculation phase of safety injection to isolate the RWST from the containment spray, safety injection and residual heat removal pumps. This function prevents contamination of the RWST.

Justification It is impracticable to exercise these valves closed during normal power operation since closure of this valve during normal power operations places the plant in an undesirable and unanalyzed configuration.

Exercising these valves closed places the plant in a condition where the associated safety injection, residual heat removal, and containment spray pumps would all be inoperable due to an isolated suction path. Closure of the valves solely for testing would place the plant in an undesirable alignment and cause undue risk.

Alternative Test These valves will be exercised closed during cold shutdowns when the safety injection pumps, containment spray pumps, and residual heat removal pumps are not required to be operable.

Revision Date: 02/11/04 Page77

1ST Program Plan FloridaPowerand Light Company Turkey Point Nuclear Powrer Plant Cold Shutdown Justification CSJ-07 Component Tal System Safent Class Catceorv 3-875A 064 I AC 3-875B 064 1 AC 3-875C 064 1 AC 4-875A 064 1 AC 4-875B 064 1 AC 4-875C 064 1 AC Function These check valves open to provide flow path from the safety injection pump to the reactor coolant system cold leg injection points during the injection phase of an accident, and to provide a flow path from the safety injection tank accumulator to the cold leg injection points when the reactor coolant system decreases below 660 psig, and must open to provide a flow path from the residual heat removal pump to the cold leg injection point during a large break LOCA when the RCS is rapidly depressurized, and during the alternate low head injection during the recirculation phase of an accident These check valves must close or remain closed to isolate the reactor coolant system from the lower pressure safety injection and residual heat removal systems during normal operations and emergency conditions when cold leg injection is not required. These valves are considered a pressure isolation valve, required to maintain the RCS pressure boundary.

The valves must close to limit leakage to <1.0 gpm.

Justification It is impracticable to exercise these valves closed during normal power operation since closure of this valve during normal power operations places the plant in an undesirable configuration along with an increase in personnel radiation exposure to perform testing.

Exercising this valve closed requires isolation and depressurization of the safety injection system accumulators to perform a leakage test to verify closure. Isolation of the accumulator during normal power operation places the plant in an undesirable condition. Personnel entry into containment would be required to perform the leakage test. This would result in an increase in personnel radiation exposure.

Alternative Test These valves will be exercised closed during cold shutdowns when the safety injection system accumulators are not required and radiation levels permit entry into containment.

Revision Date: 02/11/04 Page78

1ST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-08 Component Tat Svstem Safeth Class Categorv 3-876A 064 1 AC 3-876B 064 1 AC 3-876C 064 1 AC 4-876A 064 1 AC 4-876B 064 1 AC 4-876C 064 1 AC Function These check valves open to provide flow path from the residual heat removal system to the cold leg injection points during a large break LOCA when the RCS is rapidly depressurized. These valves must also open to provide normal low head injection during the injection phase of an accident. These check valves must close or remain closed to prevent reverse flow when the safety injection pump or accumulators are required to inject flow to the cold leg. The valves are also required to close when RHR is in service for alternate low head injection during the recirculation phase of an accident. The valves are required to close to isolate the reactor coolant system from the lower pressure residual heat removal system during emergency conditions when the residual heat removal system is not required. These valves are considered a pressure isolation valve, required to maintain the RCS pressure boundary. The valves must close to limit leakage to

<1.0 gpm.

Justification It is impracticable to exercise these valves closed during normal power operations since closure of these valves during normal power operations places the plant in an undesirable and unanalyzed configuration along with an increase in personnel radiation exposure to perform testing.

Exercising these valves closed during normal power operations requires isolation of the refueling water storage tank and depressurizing and draining of the residual heat removal system to perform leakage testing to verify closure. Isolation of the refueling water storage tank during normal operation would require defeating the normal safety injection interlocks and require declaring the low head residual heat removal system inoperable. Considering the amount of piping required to be drained, and the various LCO entered, this testing would place the plant in an unanalyzed and undesirable condition. This testing requires containment entry and significant test preparation, which may cause a delay in plant startup. Additionally, entry into containment for test preparation, performance and restoration imposes a significant increase in radiation exposure to plant personnel.

Alternative Test These valves will be exercised closed during cold shutdowns when the residual heat removal system is not required and the RWST may be isolated.

Page 79 02/11/04 Revision Date: 02111104 Page 79

1ST ProgramPlan FloridaPowver andLight Company Turkey Point Nuclear Pouer Plant Cold Shutdown Justification CSJ-09 Component Ta2 SVstem Safety Class Cateforv 3-738 030 2 C 4-738 030 2 C Function This check valve must close to isolate containment from the component cooling water system.

This valve is exempt from Appendix J testing since it is connected to a closed system inside containment. The valve provides containment isolation for Penetration 12. In the open position this valve opens to provide component cooling water to the excess letdown heat exchanger during normal plant operating modes. This open function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise this valve closed during normal power operations since significant plant piping would be required to be drained to perforrm a backflow test to verify closure.

Additionally, performance of this test places the plant in an undesirable condition during plant operations.

To exercise this check valve closed requires performance of a backflowv/leakage test. This test requires draining of the piping upstream and downstream of the check valve. Since the component cooling water is chemical treated with a corrosion inhibitor, a significant amount of time and labor is necessary to manage the disposal of this chemically treated water. Considering the amount of piping required to be drained, and the various LCO entered, this testing would place the plant in an undesirable condition during plant power operations.

Alternative Test These valves will be exercised closed during cold shutdowns when component cooling water and excess letdown are not required.

Page 80 Revision Date. 02/11/04 Date: 02/11/104 Page 80

IST ProgramPlan FloridaPowver andLight Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-10 Component Tat! Svstem Safetv Class Cateord MOV-3-1417 030 2 B MOV-3-1418 030 2 B MOV-4-1417 030 2 B MOV-4-1418 030 2 B Function These valves must close to provide containment isolation for the component cooling water supply/return line to the normal containment coolers and CRDM coolers. These valves close automatically on a Phase A containment isolation signal. The valve provides containment isolation for Penetrations 21 and 22. The valves are normally open to provide component cooling water to the normal containment coolers and CRDM coolers during normal plant operating modes and during plant fires. This open function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves closed during normal power operations since damage to plant equipment may occur.

Exercising these valves closed during normal power operations would isolate the normal cooling water supply to the normal containment coolers, control rod drive mechanism coolers, and the primary shield cooling coils. Isolation of the cooling water supply to this equipment may cause severe damage due to overheating of the equipment. Failure of this equipment due to overheating during normal power operations would result in potential equipment damage and subsequent plant shutdown.

Alternative Test These valves will be exercised closed during cold shutdowns when the associated equipment being cooled is not required to be in operation.

Revision Date: 02/11/04 Page 8 1

1ST Program Plan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-1 1 Component Tae Svstem Safetv Class Cateeorv MOV-3-626 030 2 B MOV-3-716A 030 3 B MOV-3-716B 030 2 B MOV-3-730 030 2 B MOV-4-626 030 2 B MOV-4-716A 030 3 B MOV-4-716B 030 2 B MOV-4-730 030 2 B Function These valves close to provide containment isolation for the component cooling water supply/return line from the RCP bearing coolers. The valves close automatically on a Phase B containment isolation signal. These valves are normally open to provide cooling water to the reactor coolant pump seals and the main drive motors. The open function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves closed during normal power operations since damage to plant equipment may occur.

Exercising these valves closed during normal power operations would isolate the normal cooling water supply to reactor coolant pump seals and the main drive motors. Isolation of the cooling water supply to this equipment may result in degradation of the reactor coolant pump seals and motors, eventually resulting in potential damage to the reactor coolant pump and subsequent plant shutdown.

Alternative Test These valves will be exercised closed during cold shutdowns when the associated reactor coolant pumps are not required to be in operation.

Revision Date: 02/11/04 Page 82

1ST ProgramPlan FloridaPower and Light Company Turkey PointNuclear Powver Plant Cold Shutdown Justificntion CS.T-12 Component Ta2 Svstem Safetv Class Cateaorv 3-10-004 072 SR C 3-10-005 072 SR C 3-10-006 072 SR C 4-10-004 072 SR C 4-10-005 072 SR C 4-10-006 072 SR C Function These check valves must close to prevent reverse flow due to a rupture upstream of the check valve. This prevents a single line rupture from affecting other Steam Generators by preventing uncontrolled blow down of the intact Steam Generators. This valve is open during normal operations by system flow to provide steam to the turbine. This function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves closed during normal power operations since closure may result in a plant trip.

Exercising these valves closed during normal power operations to perform testing would require the steam generator to be isolated. Isolation of the steam generators during normal operation vould cause a severe transient in the reactor coolant system and a subsequent trip of the reactor.

Alternative Test oalves will be exercised closed during cold shutdowns when the steam generator These check may be isolated.

Revision Date: 02/11/04 Page 83

ISTProgramPlan FloridaPower and Light Company Turkey Point Nuclear Powver Plant Cold Shutdown Justification CSJ-13 Component Tag Svstem Safet Class Cateorv CV-3-1606 072 2 B CV-3-1607 072 2 B CV-3-1608 072 2 B CV-4-1606 072 2 B CV-4-1607 072 2 B CV 1608 072 2 B Function This valve is an air operated relief valve with a controllable setpoint. This valve is opened (non-faulted S/G) after a SGTR with a concurrent loss of offsite power to control reactor coolant system cooldown. The RCS cooldown allows RCS depressurization which will limit radioactive release to the faulted S/G. Theses valves are considered containment isolation valves for Penetrations 26A/B/C. They are considered secondary system barrier since the Steam Generators are a closed loop inside containment. During accidents requiring the use of the AFW Turbine, these valves must remain closed to prevent diverting steam from the AFW Turbine. The valves must close or remain closed to isolate the Steam Generator from atmosphere during a SGTR (faulted S/G) because this mitigates the release of radioactivity to atmosphere. These valves also fail to the closed position on loss of power. The valves are opened during normal operations, and their setpoints are modulated, to control RCS cooldown to RHR entry conditions.

Justification It is impracticable to exercise these valves open or closed during normal power operations since exercising these valves may result in a plant transient and subsequent reactor trip.

Exercising these valves during normal power operations to perform testing would cause a power transient during normal plant operations due to the amount of steam released when the valve is opened. Exercising the valve may be performed with the block valve closed to limit the amount of steam released, however, this alignment places the plant in an undesirable condition. Normal operations with the block valve closed would limit the capability of the plant to limit a pressure transient and prevent lifting of a safety valve in the event of a pressure transient.

Alternative Test These valves will be exercised open and closed during cold shutdowns when overpressure protection the reactor coolant system is not required.

Revision Date: 02/11/04 Page 84

IST ProgramPlan FloridaPowver and Light Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-14 Component Tag Svstem Safetv Class Catcaorv MOV-3-744A 064 2 B MOV-3-744B 064 2 B MOV-4-744A 064 2 B MOV-4-744B 064 2 B Function These valves must open automatically upon receipt of a safety injection signal to provide a flow path from the RHR pump to the reactor coolant system cold legs during the injection phase of an accident. These valves are also required to be opened/closed by remote manual operations during the recirculation phase of an accident to support hot/cold leg recirculation depending on reactor coolant system pressure. The valves are also opened during normal shutdown cooling operations to facilitate normal decay heat removal. These valves are required to close by remote manual operation to isolate the RHR system when the system is aligned for hot leg injection and alternate low head injection. However, this function is redundant to downstream check valves which are required to close to isolate the reactor coolant system pressure boundary.

Justification It is impracticable to exercise these valves open or closed during normal power operation since opening of this valve during normal power operations places the plant in an undesirable configuration.

Exercising these valves open or closed requires aligning the system in a configuration where the Class I reactor coolant system is isolated from the lower pressure Class 2 residual heat removal system by two check valves. This configuration would place the plant in an undesirable alignment and cause undue risk.

Alternative Test These valves will be exercised open and closed during cold shutdowns when reactor coolant system pressure is below residual heat removal system design pressure (600 psig).

Page 85 Revision Rev ision Date: 02/11/04 Date: 02111104 Page 85

IST ProgramPlan FloridaPowver andLight Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-15 Comnonent Tae System Safetv Class Categon' MOV-3-865A 064 2 B MOV-3-865B 064 2 B MOV-3-865C 064 2 B MOV-4-865A 064 2 B MOV-4-865B 064 2 B MOV-4-865C 064 2 B Function These valves must remain open to provide a flow path from the safety injection accumulator to the reactor coolant system during injection when the reactor coolant system pressure falls below the accumulator pressure. During normal operation, this valve is maintained in the open position with it's power removed to prevent inadvertent operation. Since these valves are not required to change positions to perform this function, the open position is considered passive. These valves must close by remote manual operation to isolate the safety injection accumulator from the reactor coolant system after injection is complete to assist in maintaining the safe shutdown condition.

Justification It is impracticable to exercise these valves open or closed during normal power operation since closing this valve during normal power operations places the plant in an undesirable configuration.

Exercising these valves closed during normal plant operations requires the safety injection accumulator to be isolated. Isolating the a safety injection accumulator during normal power operations places the plant in an undesirable plant configuration and an unanalyzed condition.

Alternative Test These valves will be exercised closed during cold shutdowns when the safety injection accumulators are not required.

Revision Date: 02/11/04 Page 86

IST Program Plan FloridaPower and Light Company Turkey PointNuclear Pow-er Plant Cold Shutdown Justification CSJ-16 Component Tag Svstem Safehv Class Category CV-3-204 047 2 A CV-4-204 047 2 A Function This air operated valve must close automatically to isolate containment from the chemical volume control system letdown line. This valve provides containment isolation for Penetration 14. The valve closes automatically upon receipt of a Phase A containment isolation signal and fails closed on loss of electrical power or pneumatic supply. The valve is open during normal power operations to provide a letdown flow path from the reactor coolant system and regenerative heat exchanger to the non regenerative heat exchanger via the letdown orifices.

Justification It is impracticable to exercise this valve closed during normal power operation since closing this valve during normal power operations may result in a plant trip.

Exercising this valve closed during normal plant operations would causes pressurizer level fluctuations and potential chemical volume and control system transients which would result in a potential trip of the plant.

Alternative Test These valves will be exercised closed and fail safe tested during cold shutdowns when reactor coolant system normal letdown is not required.

Page 87 Revision Date: 02/11/04 Date: 02111104 Page 87

1ST ProgramPlan FloridaPoiwer andLight Company Turkey Point Nuclear PoiterPlant Cold Shutdown Justification CSJ-17 Component Tag Svstem Safety Class Categorv FCV-3-478 074 2 B FCV-3-488 074 2 B FCV-3-498 074 2 B FCV-4-478 074 2 B FCV-4-488 074 2 B FCV-4-498 074 2 B Function These normally open valves must close automatically on a Feedwater Isolation Signal (FWIS) during accident conditions requiring feedwater isolation. The valves are required to close within 9.0 seconds upon receipt of a Safety Injection signal and they fail closed on loss of pneumatic supply or electrical power. The valves are used to throttle flow in response to a signal from the Steam Generator Water Level Control System. These valves are opened to allow flow into the associated steam generator during normal power operations.

Justification It is impracticable to exercise these valves closed during normal power operation since closing this valve during normal power operations would result in a plant trip.

Exercising these valves closed during normal plant operations would causes a severe steam generator level transient and subsequent reactor trip.

Alternative Test These valves will be exercised closed and fail safe tested during cold shutdowns when feedwater flow control is not required.

Revision Date: 02/11/04 Page 88

ISTProgramPlan FloridaPowerand Light Company Turkey Point NAuclear Power Plant Cold Shutdown Justification CSJ-18 Component Tag Svstem Safety Class Cate2orv FCV-3-479 074 2 B FCV-3-489 074 2 B FCV-3-499 074 2 B FCV-4-479 074 2 B FCV-4-489 074 2 B FCV-4-499 074 2 B Function These valves must close automatically on a Feedwater Isolation Signal (FWIS) during accident conditions requiring feedwater isolation. These valves are required to close within 13.0 seconds upon receipt of a safety injection signal and fails closed on loss of electrical power or pneumatic supply. The valves are opened to bypass the main feedwater regulating valve to allow flow into the associated S/G during low power operations.

Justification It is impracticable to exercise these valves closed during normal power operation since exercising this valve during normal power operations would result in a plant trip.

To exercise these valves closed requires opening the valve to perform the close and fail safe tests.

Opening of these valves during normal plant operations may cause a severe steam generator level transient and subsequent reactor trip. Additionally, this testing requires the installation of electrical jumpers to defeat various safeguards logic which could also lead to an inadvertent plant transient or trip.

Alternative Test These valves will be exercised closed and fail safe tested during cold shutdowns when feedwater flow control is not required.

Revision Date: 02/11/04 Page 89

1ST ProgramPlan FloridaPower andLight Company Turkey Point NuclearPower Plant Cold Shutdown Justification CSJ-19 Component Tae System Safet Class Cateiorv HCV-3-121 047 2 B HCV-4-121 047 2 B Function This air operated valve opens to provide a flow path from the charging pump to the reactor coolant system via the regenerative heat exchanger during emergency boration. The valve is required to open to provide a flow path to the RCS during a rod cluster control assembly accident requiring emergency boration. During normal power operation, this valve is open to provide the normal return flow path from the charging pump to the reactor coolant system via the regenerative heat exchanger to support processing of the water let down from the reactor coolant system. The valve does not receive any automatic actuation signals and fails open on loss of electrical power or pneumatic supply. The valve is closed when the charging system is removed from service (charging pumps not operating).

Justification It is impracticable to exercise this valve open during normal power operation since exercising this valve during normal power operations would result in a potential plant trip.

To exercise this valve open requires closing the valve to perform the open stroke time and fail safe open tests. Closing of this valve during normal plant operations would disrupt the normal charging return flow and result in reactor coolant pump seal flow loss and pressurizer level oscillations which may result in a reactor trip.

Alternative Test These valves will be exercised open and fail safe tested during cold shutdowns when charging is not required and the charging pumps are not in operation.

Page 90 Revision Rev ision Date: 02/11/04 Date: 02111104 Page90

IST ProgramPlan FloridaPoiwer andLight Company Turkev Point Nuclear Poiver Plant Cold Shutdown Justification CSJ-20 Component Ta System Safet Class Category LCV-3-115B 047 2 B LCV-4-115B 047 2 B Function This normally closed air operated valve must open during emergency boration to provide a backup borated water suction source from the RWST to the charging pumps. This valve is opened by remote manual operation in the event that the boric pumps fail to start. This valve opens automatically upon receipt of a low level in the volume control tank to provide a flow path from the RWST to the charging pump suction for automatic makeup of borated water to the reactor coolant system. Upon initiation of a low volume control tank level the normal suction for the charging pumps is isolated by LCV-*-I 5C, which closes. To ensure a suction path is available to the charging pumps, the valve is interlocked such that LCV-*-I 15C will not begin to close until LCV-*-I 15B is full open. The valve may also be opened by remote manual operation.

This valve must remain closed to isolate the charging pump suction piping from the RWST during normal power operations and during emergency boration when the boric acid pumps are providing emergency boration. This function is considered passive since the valve is not required to change position to perform this function. The valve fails closed on loss of electrical power or pneumatic supply.

Justification It is impracticable to exercise this valve open during normal power operation since exercising this valve during normal power operations would cause a power transient and potential plant trip.

To exercise this valve open requires injection of refueling water storage tank borated water into the reactor coolant system. During normal power operations, this test would cause a severe power transient which may lead to a plant trip.

Alternative Test These valves will be exercised open and fail safe tested during cold shutdowns when the chemical volume and control system is not required to be in operation.

Revision Date: 02/11/04 Page 91I

IST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-21 Component Tag System Saretv Class Cateeorv LCV-3-115C 047 2 B LCV-4-115C 047 2 B Function This valve closes automatically upon receipt of a low level in the volume control tank to isolate the volume control tank. Valve LCV-*-I 15B opens to provide a flow path from the RWST to the charging pump suction for automatic makeup of borated water to the reactor coolant system. To ensure a suction path is available to the charging pumps, the valve is interlocked such that LCV-

• -1 15C will not begin to close until LCV-*-1 15B is full open. The valve is required to be closed by remote manual operation during emergency boration in the event of a failure of the boric acid pumps, when the RWST is aligned to the charging pump suction. The valve opens/remains open during normal operations to provide a flow path from the VCT to the charging pump suction.

Justification It is impracticable to exercise this valve closed during normal power operation since exercising this valve during normal power operations would cause a power transient and potential plant trip.

To exercise this valve closed requires aligning the charging pumps take suction from the refueling water storage tank during normal operation. This would cause injection of refueling water storage tank borated water into the reactor coolant system. During normal power operations, this test would cause a severe power transient which may lead to a plant trip.

Alternative Test This valve will be exercised closed during cold shutdowns when the chemical volume and control system is not required to be in operation.

Page 92 Date: 02/11/04 Revision Date: 02/111/04 Page 92

ISTProgram Plan FloridaPower andLight Company Turkey PointNuclear Power Plant Cold Shutdown Justification CSJ-22 Component Tan System Safeht Class Cateiorv 3-357 047 2 C 4-357 047 2 C Function This check valve opens to provide a flow path from the RWST to the charging pump suction wvhen a low level in the volume control tank automatically opens LCV-*-1 15B for automatic makeup of borated water to the reactor coolant system. Upon initiation of a low volume control tank level the normal suction for the charging pumps is isolated by LCV-*- I15C, which closes.

This valve closes to isolate the charging pump suction piping from the RWST during normal power operations and during emergency boration when the boric acid pumps are providing emergency boration. However, normally closed downstream valves LCV-*115B and *-358 are relied upon for isolating the emergency boration flow path when it is not required.

Justification It is impracticable to exercise this valve open during normal power operation since exercising this valve during normal power operations would cause a power transient and potential plant trip.

To exercise this valve open requires aligning the charging pumps take suction from the refueling water storage tank during normal operation. This would cause injection of refueling water storage tank borated water into the reactor coolant system. During normal power operations, this test would cause a severe power transient which may lead to a plant trip.

Alternative Test This valve will be exercised open during cold shutdowns when the chemical volume and control system is not required to be in operation.

Revision Date: 02/11/04 Page 93

ISTProgramPlan FloridaPowter and Light Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-23 Component Tan Svstem Safety Class Cateorv PCV-3-455C 041 1 B PCV-3-456 041 1 B PCV-4-455C 041 1 B PCV-4-456 041 1 B Function This normally closed air operated valve must close to maintain the RCS pressure boundary in order to contain the coolant under operating temperature and pressure conditions. This valve must open during reactor heat up and cooldown when the Overpressure Mitigation System is in operation. During OMS operation, the reactor temperature and pressure are below normal operating bands. The lower temperature of the RCS requires lower relief setpoints to avoid brittle fracture. During these conditions the PORV setpoints are varied by the OMS according to system conditions. The subject valve must open to allow a relief path since the Safety Valve setpoints are too high to provide protection during these conditions. This valve will also automatically open at 2335 psig during normal operations (normal operating temperature and pressure) to mitigate pressure transients during a SGTR or an Appendix R fire. This function is considered important to safety but does not support safe shutdown or accident mitigation since the Pressurizer Safety Valves (RV-*-55IA/B/C) are relied upon for overpressure protection of the reactor coolant system.

Justification It is impracticable to exercise this valve open and closed during normal power operation since exercising this valve during normal power operations may cause equipment damage or a plant trip.

Exercising this valve during normal power operations would cause a rapid depressurization of the reactor coolant system causing a pressure transient and subsequent trip of the plant. Additionally, exercising this valve each quarter at power would eventually damage the valve seat.

Alternative Test This valve will be exercised open and closed and fail safe tested during cold shutdowns when the reactor coolant system pressure is depressurized.

Revision Date: 02/11/04 Page94

IST Program Plan FloridaPowver and Light Company Turkey Point NuclearPower Plant Cold Shutdown Justification CSJ-24 Comnonent Ta¢ Svstem Safetv Class Cateeory SV-3-6318A 041 2 B SV-3-6318B 041 2 B SV-3-6611 041 2 B SV-3-6612 041 2 B SV-4-6318A 041 2 B SV-4-6318B 041 2 B SV-4-6611 041 2 B SV-4-6612 041 2 B Function Valves SV-*-6318A/B must open during post-accident conditions to vent the vessel head so that the non-condensible gas bubble does not disrupt cooling to the core by inhibiting natural circulation. The reactor vessel head vent system provides a means of venting the vessel head to either the containment sump or the pressurizer relief tank. These valves must remain closed during normal operations to establish the RCS pressure boundary. These valves are administratively maintained closed when RCS temperature exceeds 200F by locking their control switches and removing the fuses to the valves' power supply. These valves isolate the reactor vessel head from downstream piping which leads to the containment sump, containment atmosphere, pressurizer relief tank or a sample connection. Since these valves are not required to change position to perform the closed safety function they are considered passive in the closed direction.

Valves SV-*-6611/6612 must open during post-accident conditions to vent the vessel head so that the non-condensible gas bubble does not disrupt cooling to the core by inhibiting natural circulation. The reactor vessel head vent system provides a means of venting the vessel head to either the containment sump or the pressurizer relief tank. These valves isolate the reactor vessel head vent from piping which leads to either the containment sump or containment atmosphere.

This closed function is considered passive since the valves are administratively maintained closed when RCS temperature exceeds 200F by locking its control switch and removing the fuses to the valve's power supply. These valve fail closed on loss of electrical power.

Justification It is impracticable to exercise these valves during normal power operation since exercising these valves during normal power operations may result in a loss of coolant in excess of allowable limits. Exercising these valves during normal power operations may lead to a loss of coolant in excess of allowable limits and potential plant shutdown. These valves are administratively maintained closed to isolate the Class I reactor coolant system pressure boundary. Failure of these valves during testing at normal power conditions would require a containment entry and potential shutdown of the plant.

Alternative Test The SV-*-6318A/B will be exercised open during cold shutdowns when the reactor coolant system pressure is depressurized. Valves SV-*-6611/6612 will be exercised open and fail safe tested open during cold shutdowns when the reactor coolant system pressure is depressurized.

Revision Date: 02/11/04 Page95

IST ProgramPlan FloridaPowver and Light Company Turkey Point Nuclear Power Plant Cold Shutdow n Justification CSJ-25 Component Tan Svstem Safety Class Category MOV-3-381 047 2 A MOV-3-6386 047 2 A MOV-4-381 047 2 A MOV-4-6386 047 2 A Function These motor operated valve must close automatically to isolate containment from the chemical volume and control system seal .water injection return line. These valves provide containment isolation for Penetration 25. The valves close automatically upon receipt of a Phase A containment isolation signal. These valves may also be closed by remote manual operation.

The valves are open during normal power operations to provide a return flow path from the reactor coolant pump seal injection system (and excess letdown if in operation) to the volume control tank. This function is not required for safe shutdown or accident mitigation since the reactor coolant pumps (and letdown) are not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves during normal power operation since exercising these valves during normal power operations may result in damage to the reactor coolant pump seals.

Exercising these valves closed during normal power operations would interrupt flow from the reactor coolant pump seals. Loss of reactor coolant pump seal flow with the reactor coolant pump in operation would damage the seals due to overheating.

Alternative Test These valves will be exercised closed during cold shutdowns when the reactor coolant pumps are not in operation.

Revision Date: 02/11/04 Page96

1ST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear PowerPlant Cold Shutdown Justification CSJ-26 Component Tat System Safetv Class Categorv MOV-3-862A 050 2 B MOV-3-862B 050 2 B MOV-4-862A 050 2 B MOV-4-862B 050 2 B Function These normally locked open motor operated valves must remain open to provide a flow path from the RWST to the suction of the residual heat removal pumps during the injection phase of an accident. These valves are maintained administratively locked open with the breaker open to ensure the valves remain open during the injection phase. The valves are maintained in the open position during normal power operations and does not receive any automatic actuation signals.

After the valves are closed during the recirculation phase, they are not required to be reopened to support any accident analysis events. Therefore, the open function is considered passive.

These valves must close prior to switch over to the recirculation phase of safety injection to isolate the RWST from the residual heat removal pumps. This function prevents contamination of the RWST. The valves are closed by remote manual operation in accordance with procedure.

These valves are also closed when RHR is initiated for normal plant cooldown (shutdown cooling). The valves are interlocked such that when they ares open, the shutdown cooling isolation valves (MOV-*-750/75 1)are closed.

Justification It is impracticable to exercise these valves closed during normal power operation since closure of either valve during normal power operations places the plant in an undesirable and unanalyzed configuration.

Exercising these valves closed places the plant in a condition where the shared residual heat removal pumps are not available as required. Closure of the valves solely for testing would place the plant in an undesirable alignment and cause undue risk.

Alternative Test These valves will be exercised closed during cold shutdowns when the residual heat removal pumps are not required to be in operation.

Page 97 Revision Date: 02/11/04 Date: 02/111/04 Page 97

ISTProgramPlan FloridaPowver and Light Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-27 Component Tan SVstem Safety Class Categorv MOV-3-750 050 1 A MOV-3-751 050 1 A MOV-4-750 050 1 A MOV-4-751 050 1 A Function These normally closed motor operated valves must open to provide a flow path from the reactor coolant system hot leg to the suction of the residual heat removal pumps during alternate hot leg recirculation operations. This function is initiated by the operator following switchover from the RWST to containment sump and requires opening the valve by remote manual operation. These valves are also opened when RHR is initiated for normal plant cooldown (shutdown cooling).

The valves are maintained in the closed position during normal power operations and do not receive any automatic actuation signals. The valves are interlocked such that they can not be opened until the RWST suction isolation valves (MOV-*-862A/B) are closed. Additionally, the valves are interlocked with reactor pressure such that they will automatically close and can not be opened with reactor pressure greater than 525 psig.

These valves must close to isolate the reactor coolant system from the lower pressure residual heat removal system during emergency conditions when hot leg recirculation is not required to be in service. These valves are considered a pressure isolation valve, required to maintain the RCS pressure boundary. The valves must close to limit leakage to <1.0 gpm.

Justification It is impracticable to exercise these valves open or closed during normal power operation since exercising this valve during normal power operations places the plant in an undesirable and unanalyzed configuration.

Exercising these valves open/closed during normal operations would require defeating the reactor pressure interlock and RWST suction valve interlocks to cycle the valves open and closed. This testing would place the plant in an undesirable alignment and cause undue risk.

Alternative Test These valves will be exercised open and closed during cold shutdowns when the residual heat removal system is not required to be in operation and reactor pressure is less than 525 psig.

Page 98 Revision Date: 02/11/04 Date: 02/11/104 Page 98

ISTProgramPlan FloridaPowerand Light Company Turkey PointNuclear Power Plant Cold Slhutdowvn Justification CSJ-28 Comnonent Tah Svstem Safetv Class Catelorv MOV-3-863A 050 2 B MOV-3-863B 050 2 B MOV-4-863A 050 2 B MOV-4-863B 050 2 B Function These normally locked closed motor operated valves must open by remote manual operation to provide a flow path from the discharge of the RHR heat exchanger to the suction of the safety injection pumps during recirculation. This function is initiated by the operator following switchover from the RWST to containment sump and requires opening the valve by remote manual operation after the RWST suction valves (MOV-*-862A/B and MOV-*-864A/B) are closed. These valves are also opened to provide a flow path to the containment spray pumps and/or alternate low head injection path in the event that the safety injection pump can not be started.

The valves are required to remain closed to prevent divergence of injection flow to the RHR pump suction during the injection phase of an accident. These valves do not receive any automatic actuation signals and are administratively maintained closed with the breaker locked in the off position. Since these valves are not required to be closed to support any accident conditions after being open during recirculation, the closed position is considered passive.

Justification It is impracticable to exercise these valves open during normal power operation since exercising these valves during normal power operations places the plant in an undesirable and unanalyzed configuration.

Exercising these valves open during normal operations would require alignment of the plant in a undesirable configuration in which the residual heat removal system could not perform its function.

Alternative Test These valves will be exercised open during cold shutdowns when the residual heat removal system is not required to be in operation.

Page 99 Revision Revision Date: 02/1)104 Date: 02/111/04 Page99

1ST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear Powver Plant Cold Shutdown Justification CSJ-29 Component Ta2 Svstem Safety Class Cateponr 3-753A 050 2 C 3-753B 050 2 C 4-753A 050 2 C 4-753B 050 2 C Function These check valves must open to provide a flow path from the residual heat removal pump to the reactor coolant system during ECCS injection and recirculation modes of operation.

These valves must close to prevent backflow through an idle pump during ECCS injection and recirculation modes of operation. Closure of these valves ensures adequate flow to the reactor coolant system in the event of a failure of the respective residual heat removal pump to start.

Justification It is impracticable to fail safe test these valves during normal power operation since exercising these valve during normal power operations would require injection into the reactor coolant system.

To perform the necessary check valve open and closed testing requires operating the residual heat removal pump at full flow conditions. This testing can only be performed by injection into the reactor coolant system. During normal power operations, this test would require injection of borated refueling water storage tank water into the reactor. During normal power operations, this test would cause a severe power transient which may lead to a plant trip.

Alternative Test These check valves will be exercised open and closed during cold shutdowns when the residual heat removal system is not required to be in operation and full flow testing may be performed.

Revision Date: 02/11/04 Page 100

ISTProgram Plan FloridaPower andLight Company Turkey Point Nuclear Power Plant Cold Shutdown Justification CSJ-30 Component Tae System Safetv Class Category POV-3-2604 072 2 B POV-3-2605 072 2 B POV-3-2606 072 2 B POV-4-2604 072 2 B POV-4-2605 072 2 B POV-4-2606 072 2 B Function These valves must close to isolate containment from the Steam Generators (closed loop inside containment) from the Main Steam Header. These valves are a secondary system barrier since the Steam Generators are a closed loop inside containment. These valves are required to close in the event of a Main Steam Line Break or Steam Generator Tube Rupture. The valves will close in response to a Main Steam Isolation Signal. These valves open during normal operation. These valves held open by an air actuator. The open function does not support safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves closed during normal power operation since exercising this valve during normal power operations would cause a plant trip.

Closing these valves for testing during normal power operations would interrupt steam flow from the steam generator to the main steam/turbine systems. Exercising these valves closed would isolate the steam generator which would result in a severe power transient in the steam and reactor coolant systems which would lead to a subsequent trip of the plant.

Alternative Test These valves will be exercised closed during cold shutdowns when the main steam system is not required to be in operation.

Revision Date: 02/11/04 Page 101

1ST Program Plan FloridaPowerand Light Company Turkey Point Nuclear PowerPlant Cold Shutdown Justification CSJ-31 Component Tag System Safetv Class Categoric MOV-3-872 050 2 B MOV-4-872 050 2 B Function These normally closed motor operated valves must open by remote manual operation to provide a flow path from the discharge of the RHR heat exchanger to the alternate low head safety injection points in the event that the safety injection pump can not be started. This function is initiated by the operator following switchover from the RWST to containment sump and requires opening the valves by remote manual operation after the RWST suction valves (MOV-*-862A/B and MOV-*-

864A/B) are closed.

The valves are considered containment isolation valves for penetration 11, however, they are exempt from Appendix J Type C testing since they are connected to a penetration which is considered essential and may be in service post accident. These valves do not receive any automatic actuation signals and are operated by remote manual operation.. Since the valves are not required to be closed to support any accident conditions after being open to support alternate low head injection, the closed position is considered passive.

Justification It is impracticable to exercise these valves open during normal power operation since exercising this valve during normal power operations places the plant in an undesirable and unanalyzed configuration.

Exercising this valve open during normal operations would require alignment of the plant in a undesirable configuration in which the residual heat removal system could not perform its function.

Alternative Test These valves will be exercised open during cold shutdowns when the residual heat removal system is not required to be in operation.

Revision Date: 02/11/04 Page 102

1ST ProgramPlan FloridaPower and Light Company Turkev Point Nuclear Power Plant ATTACHMENT 8 REFUELING OUTAGE JUSTIFICATION INDEX (Page I of 1)

Refueling Outage Description Justification No.

lRJ-0o ll Service Air to Containment Check Valve (3-40-205) Closure Testing I RJ-02 l[ Instrument Air to Containment Check Valve (*-40-336) Closure Testing I RJ-03 l[ Instrument Air to Containment Check Valve (*-40-340A) Closure Testing

[RJ-04 l[ Boric Acid Pump Discharge Check Valve (3-397A/B,4-397C1D) Open Testing lRJ-05 ][ N2 to PRT Check Valve (*-518/519) Closure Testing RJ-06 l[ Si Hot-Leg Injection Check Valve (*-874A/B) Open/Close Testing

[RJ-07 l[ SI Pump Discharge Check Valve (*-879A/B/C/D) Open Testing

[RJ-08 lSI Cold Leg Branch Injection Check Valve (*-873A/B/C) Open/Close Testing

[RJ-09 Si Cold Leg Injection Check Valves (*-875A/B/C) Open Testing I RJ-10 ll Sl Accumulator Discharge Check Valves (*-875D/E/F)

RM I lContainment Atmosphere Sample Return Check Valve (*-I 1-003) Closure

- Testing RJ-12 ][ Alternate Low Head Injection Check Valve (*-876D/E) Closure Testing lRJ-13 RJ-14 I[

lCCW Supply to RCP Thermal Barrier Check Valve (8-721A/B/C) Closure

][

Testing Charging Header Containment Isolation Check Valve (*-312C) Closure Testing RJ-15 }[ Emergency Boration Check Valve (*-351) Open Testing RJ-16 RCP Seal Water Containment Isolation Check Valve (*-298A/B/C) Closure l ]I Testing lRJ-17

[lJ~I RJ-18

](

]l Containment Spray Suction Relief Discharge Check Valve (*-2052)

Open/Close Testing Safety nJection N2 Supply Check Valve (*-945E) Closure Testing RJ-19 ][ Low Head Injection Check Valve (*-876AIB/C) Open Testing Revision Date: 02/11/04 Page 103

IST ProgramPlan FloridaPower and Light Company Turkey Point Nuclear Power Plant ATTACHMENT 9 REFUELING OUTAGE JUSTIFICATIONS Revision Date: 02/11/04 Page 104

1ST ProgramPlan FloridaPouer and Light Company Turkey Point Nuclear PowerPlant Refueline Outage Justification RJ-01 Component Tae Svstem Safetv Class Categorw 3-40-205 013 2 AC Function This check valve must close to isolate containment from the non safety related service air system.

This valve provides containment isolation for penetration 34. This valve opens to provide service air to containment in order to facilitate testing and maintenance. This function is not required for safe shutdown or accident mitigation since the penetration is normally isolated by upstream locked closed manual valve 3-40-204.

Justification It is impracticable to exercise this check valve open or closed during normal power operations or cold shutdowns since closure testing imposes an increase in personnel radiation exposure.

To verify closure of this valve requires a backflowvleakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure.

Alternative Test This check valve will be exercised open and closed during each refueling outage.

Revision Date: 02/11/04 Page 105

IST ProgramPlan FloridaPowerand Light Company Turkey PointNuclear Powser Plant Refueling Outage Justification RJ-02 Comnonent Tag System Safety Class Categorv 3-40-336 013 2 AC 4-40-336 013 2 AC Function This check valve must close to isolate containment from the non safety instrument air system.

This valve provides containment isolation for penetration 29.

The valve opens to provide a flow path of instrument air to the containment supply header when the instrument air system is operating. This function is not required safe shutdown or accident mitigation since the instrument air system is non safety related.

Justification It is impracticable to exercise this check valve open or closed during normal power operations or cold shutdowns since closure testing imposes an increase in personnel radiation exposure and requires significant system off normal alignments to perform testing which may delay a unit startup.

To exercise this valve open/closed requires a forward flow test coupled with a backflow or leakage test. This testing requires entry into containment for test alignment and performance.

During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure. Additionally, the instrument air supply to containment would be required to be isolated. Isolation of the instrument air system during normal operations or during cold shutdown periods would essentially require all components served by the system to be out of service causing the unit to be shutdown.

Alternative Test This check valve will be exercised open and closed during each refueling outage.

ReiinDt:021/4Pg 0 Revision Date: 02111104 Page 106

1ST Program Plan FloridaPower and Light Company Turkey Point Nuclear Power Plant Refueline Outa2e Justification RJ-03 Component Tai! SVstem Safety Class Catceorv 3-40-340A 013 2 AC 4-40-340A 013 2 AC Function This check valve must close to isolate containment from the non safety instrument air system.

This valve provides containment isolation for penetration 29.

The valve opens to provide a flow path of instrument air to the containment supply header when the instrument air system is operating. This function is not required safe shutdown or accident mitigation since the instrument air system is non safety related.

Justification It is impracticable to exercise this check valve open or closed during normal power operations or cold shutdowns since exercise testing imposes an increase in personnel radiation exposure and requires significant system off normal alignments to perform testing which may delay a unit startup.

To exercise this valve open/closed requires a forward flow test coupled with a backflow or leakage test. This testing requires entry into containment for test alignment and performance.

During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure. Additionally, the instrument air supply to containment would be required to be isolated. Isolation of the instrument air system during normal operations or during cold shutdown periods would essentially require all components served by the system to be out of service causing the unit to be shutdown.

Alternative Test This check valve will be exercised open and closed during each refueling outage.

Revision Date: 02/11/04 Page 107

IST Program Plan FloridaPowerand Light Company TurkeV Point Nuclear Power Plant Refueline Outage Justification RJ-04 Component Ta2 SN stem Safety Class Cateeorw 3-397A 046 2 C 3-397B 046 2 C 4-397C 046 2 C 4-397D 046 2 C Function These check valves are required to open to provide a flow path from the boric acid transfer pump to the charging pumps suction header in the event that emergency boration is required. The valves also open during normal power operation to support normal boric acid batching/transfer.

This function is not required for safe shutdown or accident mitigation. These valves must close to prevent backflow when the associated pump is idle and the other pump is required for emergency boration.

Justification It is impracticable to exercise these check valves open during normal power operations or cold shutdowns since testing during power operations may cause a plant trip. Testing during cold shutdowns would delay a unit startup.

To exercise open these check valves requires operating the boric acid transfer pump at conditions which provide full design accident flow through the check valve. During normal power operations this testing would lead to the injection of high concentrations of boric acid into the reactor coolant system which may cause a plant trip. During cold shutdown periods this testing would cause a potential delay in unit startup due to the high boric acid concentrations in the reactor coolant system.

Alternative Test These check valves will be exercised open closed during each refueling outage.

Revision Date: 02/11/04 Page 108

1ST ProgramPlan FloridaPowver and Light Company Turkey Point Nuclear Power Plant Refueling Outage Justification RJ-05 Component Taa Svstem Safety Class Catezorv 3-518 065 2 AC 3-519 065 2 AC 4-518 065 2 AC 4-519 065 2 AC Function This check valve must close to isolate containment from the non safety nitrogen supply system.

This valve. provides containment isolation for Penetration 6. The valve opens to provide a flow path from the nitrogen supply header to the pressurizer relief tank. This function is not required safe shutdown or accident mitigation since the nitrogen system is non safety related. The pressurizer relief tank is designed for full vacuum conditions to prevent tank collapse if the tank contents cool without nitrogen being supplied.

Justification It is impracticable to exercise these check valves open or closed during normal power operations or cold shutdowns since closure testing imposes an increase in personnel radiation exposure and requires significant system off normal alignments to perform testing which may delay a unit startup.

To exercise this valve open/closed requires a forward flow test coupled with a backflow or leakage test. This testing requires entry into containment for test alignment and performance.

During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure. Additionally, the nitrogen supply to the pressurizer relief tank would be interrupted, which may cause a pressure transient in the tank.

Alternative Test This check valve will be exercised open and closed during each refueling outage.

Page 109 Revision Revision Date: 02/11/04 Date: 02111104 Page 109

1ST ProgramPlan FloridaPower and Light Company Turkey Point ANuclear Power Plant Refueline Outage Justification RJ-06 Component Tag Svstem Safetv Class 'Category 3-874A 062 1 AC 3-874B 062 1 AC 4-874A 062 1 AC 4-874B 062 1 AC Function These check valves must open to provide flow path from the safety injection pump to the reactor coolant system hot leg during the hot leg recirculation phase of operation following a loss of coolant accident. The hot leg recirculation phase is initiated by manual operation since the upstream motor operated valve MOV-*-866A/B is maintained closed with power source removed during normal operation. These check valves must close or remain closed to isolate the reactor coolant system from the lower pressure safety injection system during emergency conditions when hot leg recirculation is not required to be in service. These valves are considered a pressure isolation valve, required to maintain the RCS pressure boundary.

Justification It is impracticable to exercise these check valves open during normal power operations or cold shutdowns since open testing requires injection of borated water into the reactor coolant system.

It is impracticable to exercise these check valves closed during normal power operations or cold shutdowns since closure testing imposes an increase in personnel radiation exposure and requires significant system off normal alignments to perform testing which may delay a unit startup.

To verify check valve full open position requires operation of the safety injection pump and injection in to the reactor coolant system. This test can not be performed during normal power operations since the safety injection pump discharge pressure is lower than the normal reactor coolant system pressure. This test can not be performed during cold shutdowns since injection into the reactor coolant system requires placing the plant in a configuration outside of design.

Additionally, injection of borated refueling water storage tank water may cause a delay in plant startup due to the high concentration of boric acid in the reactor coolant system.

Verification of valve closure requires the performance of a leakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure. Additionally, due the amount of piping required to be isolated, drained, and vented to perform a leakage test, a delay in plant startup from the cold shutdown condition would be incurred.

Alternative Test These check valves will be exercised open and closed during each refueling outage.

Page 110 Revision Revision Date: 02/11/04 Date: 02111104 Page I 10

ISTProgram Plan FloridaPowver andLight Company Turkey Point Nuclear PowerPlant Refueline Outage Justification RJ-07 Component Tag Svstem Safetv Class Categorv 3-879A 062 2 C 3-879B 062 2 C 4-879C 062 2 C 4-879D 062 2 C Function These check valves must open to provide a flow path from the safety injection pump to the reactor coolant system during ECCS injection and recirculation modes of operation. These valves must close to prevent backflow through an idle pump during ECCS injection and recirculation modes of operation. Closure of this valve ensures adequate flow to the reactor coolant system in the event of a failure of the respective safety injection pump to start.

Justification It is impracticable to exercise these check valves open during normal power operations or cold shutdowns since open testing requires injection of borated water into the reactor coolant system.

To verify check valve full open position requires operation of the safety injection pump at design accident conditions, and injection in to the reactor coolant system. This test can not be performed during normal power operations since the safety injection pump discharge pressure is lower than the normal reactor coolant system pressure. This test can not be performed during cold shutdowns since injection into the reactor coolant system requires placing the plant in a configuration outside of design. Additionally, injection of borated refueling water storage tank water may cause a delay in plant startup due to the high concentration of boric acid in the reactor coolant system.

Alternative Test These check valves will be exercised open during each refueling.

Page 111 Revision Date: 02/11/04 Date: 02/11/104 Page 11I1

IST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Refueling Outnae Justification RJ-08 Component Tag System Safety Class Category 3-873A 064 1 AC 3-873B 064 1 AC 3-873C 064 1 AC 4-873A 064 1 AC 4-873B 064 I AC 4-873C 064 1 AC Function This check valve must open to provide flow path from the safety injection pump to the reactor coolant system cold leg injection points during the injection phase of an accident. This check valve must close or remain closed to isolate the reactor coolant system from the lower pressure safety injection system during emergency conditions when cold leg injection is not required. This valve is considered a pressure isolation valve, required to maintain the RCS pressure boundary.

The valve must close to limit leakage to <1.0 gpm.

Justification It is impracticable to exercise these check valves open during normal power operations or cold shutdowns since open testing requires injection of borated water into the reactor coolant system.

It is impracticable to exercise these check valves closed during normal power operations or cold shutdowns since closure testing imposes an increase in personnel radiation exposure and requires significant system off normal alignments to perform testing which may delay a unit startup.

To verify check valve full open position requires operation of the safety injection pump and injection in to the reactor coolant system. This test can not be performed during normal power operations since the safety injection pump discharge pressure is lower than the normal reactor coolant system pressure. This test can not be performed during cold shutdowns since injection into the reactor coolant system requires placing the plant in a configuration outside of design.

Additionally, injection of borated refueling water storage tank water may cause a delay in plant startup due to the high concentration of boric acid in the reactor coolant system.

Verification of valve closure requires the performance of a leakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure. Additionally, due the amount of piping required to be isolated, drained, and vented to perform a leakage test, a delay in plant startup from the cold shutdown condition would be incurred.

Alternative Test These check valves will be exercised open and closed during each refueling outage.

Revision Date: 02/11/04 Page 112

ISTPrograinPlan FloridaPower andLight Company Turkey Point Nuclear Power Plant Refuelin2 Outa2e Justification RJ-09 Component Ta2 Svstem Safetv Class Cate2orv 3-875A 064 I AC 3-875B 064 1 AC 3-875C 064 1 AC 4-875A 064 1 AC 4-875B 064 1 AC 4-875C 064 1 AC Function This check valve must open to provide flow path from the safety injection pump to the reactor coolant system cold leg injection points during the injection phase of an accident. The valve must also open to provide a flow path from the safety injection tank accumulator to the cold leg injection points when the reactor coolant system decreases below 660 psig. Additionally, this check valve must open to provide a flow path from the residual heat removal pump to the cold leg injection point during a large break LOCA when the RCS is rapidly depressurized and during the alternate low head injection during the recirculation phase of an accident. This check valve must close or remain closed to isolate the reactor coolant system from the lower pressure safety injection and residual heat removal systems during normal operations and emergency conditions when cold leg injection is not required. This valve is considered a pressure isolation valve, required to maintain the RCS pressure boundary. The valve must close to limit leakage to <1.0 gpm.

Justification It is impracticable to exercise these check valves open during normal power operations or cold shutdowns since open testing requires injection of borated water into the reactor coolant system which would cause a delay in plant startup.

To verify check valve full open position requires injection of the safety injection accumulator to verify full design accident flow through the subject valve. This test can not be performed during normal power operations since the safety injection accumulator pressure is lower than the normal reactor coolant system pressure. This test can not be performed during cold shutdowns since injection into the reactor coolant system from the safety injection accumulators requires significant plant preparation to perform the test. Additionally, injection of borated safety injection accumulator water during cold shutdowns would cause a delay in plant startup due to the high concentration of boric acid in the reactor coolant system. Additionally, the performance of this test during cold shutdowns would result in an increase in personnel radiation exposure.

Alternative Test These check valves will be exercised open during each refueling outage.

Revision Date: 02/11/04 Page 113

IST Program Plan FloridaPower andLight Company Turkey Point Nuclear PoiverPlant Refueling Outage Justification RJ-10 Component Tan Svstem Safetv Class Cateeorv 3-875D 064 1 C 3-875E 064 1 C 3-875F 064 1 C 4-875D 064 1 C 4-875E 064 1 C 4-875F 064 1 C Function This check valve must open to provide a flow path from the safety injection tank accumulator to the reactor coolant system cold leg during accident conditions whenever the reactor coolant system pressure decreases below 660 psig. This valve must close to prevent reverse flow during the injection phase of an accident when the safety injection pump is providing flow to the reactor coolant system cold leg injection path. The valve must also close when the residual heat removal pump is providing flow to the cold leg injection path or during recirculation when the alternate low head injection path is used.

Justification It is impracticable to exercise these check valves open or closed during normal power operations or cold shutdowns since open testing requires injection of borated water into the reactor coolant system which would cause a delay in plant startup. It is impracticable to exercise these check valves closed during normal power operations or cold shutdowns since closure testing imposes an increase in personnel radiation exposure and requires significant system off normal alignments to perform testing which may delay a unit startup.

To verify check valve full open position requires injection of the safety injection accumulator to verify full design accident flow through the subject valve. This test can not be performed during normal power operations since the safety injection accumulator pressure is lower than the normal reactor coolant system pressure. This test can not be performed during cold shutdowns since injection into the reactor coolant system from the safety injection accumulators requires significant plant preparation to perform the test. Additionally, injection of borated safety injection accumulator water during cold shutdowns would cause a delay in plant startup due to the high concentration of boric acid in the reactor coolant system.

Verification of valve closure requires the performance of a leakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure. Additionally, due the amount of piping required to be isolated, drained, and vented to perform a leakage test, a delay in plant startup from the cold shutdown condition would be incurred.

Alternative Test These check valves will be exercised open and closed during each refueling outage.

Revision Date: 02/11/04 Page 114

1ST ProgramPlan FloridaPower and Light Company Turkey Point Nluclear Power Plant Refueling Outane Justification RJ-I I Component Tau System Safetv Class CategorT 3-11-003 094 2 AC 4-11-003 094 2 AC Function This check valve must close to isolate containment Penetration 32 from the exhaust of the Containment Air Monitor. The valve will close due to reverse flow if the associated containment isolation valves do not close or the line ruptures. This check valve must open to establish a flow path from the exhaust of the Containment Air Monitor and Hydrogen Monitors back to containment. This function is required to allow operators to monitor post accident conditions and take necessary actions to mitigate the consequences of an accident. The Containment Air Monitor takes a suction from the Containment Cooler Exhaust Header.

Justification It is impracticable to exercise this check valve open or closed during normal power operations or cold shutdowns since closure testing imposes an increase in personnel radiation exposure.

To exercise this valve open/closed requires a forward flow test coupled with a backflow or leakage test. This testing requires entry into containment for test alignment and performance.

During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure.

Alternative Test This check valve will be exercised open and closed during each refueling outage.

Revision Date: 02/11/04 Page 115

1ST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear Powver Plant Refuelin2 Outage Justification RJ-12 Component Tao System Safetv Class Catefory 3-876D 064 1 AC 3-876E 064 1 AC 4-876D 064 1 AC 4-876E 064 1 AC Function This check valve must open to provide flow path from the residual heat removal system to the cold leg injection points. The valve opens to provide alternate low head injection during the recirculation phase of an accident. This check valve must close or remain closed to prevent reverse flow when the safety injection pump or accumulators are required to inject flow to the cold leg. The valve is also required to close when RHR is in service for low head injection during the recirculation phase of an accident. The valve is required to close to isolate the reactor coolant system from the lower pressure residual heat removal system during emergency conditions when the residual heat removal system is not required. This valve is considered a pressure isolation valve, required to maintain the RCS pressure boundary. The valve must close to limit leakage to

<1.0 gpm.

Justification It is impracticable to exercise this check valve open or closed during normal power operations or cold shutdowns since closure testing imposes an increase in personnel radiation exposure and may delay plant startup.

To exercise this valve open/closed requires a forward flow test coupled with a backflow or leakage test. This testing requires entry into containment for test alignment and performance.

During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure along with a high potential for delaying plant startup due to the significant amount of piping required to be filled and vented.

Alternative Test This check valve will be exercised open and closed during each refueling outage.

Revision Date: 02/11/04 Page 116

IST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear Power Plant Refueling Outae Justification RJ-13 Component Ta2 System Safety Class Cateomrv 3-721A 030 3 C 3-721B 030 3 C 3-721C 030 3 C 4-721A 030 3 C 4-721B 030 3 C 4-721C 030 3 C Function These check valves must close to prevent uncontrolled RCS blowdown into the low pressure CCW system in the event of a RCP thermal barrier cooling coil rupture. The piping downstream of these check valves is designed for full RCS pressure, whereas the piping upstream is designed to CCW system pressure requirements. These valves open to allow cooling water flow to the reactor coolant pumps and motors during normal plant operating modes. This function prevents RCP pump damage and degradation of the pump seals that could result because a blockage of RCP cooling water. This function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these check valves closed during normal power operations or cold shutdowns since closure testing imposes an increase in personnel radiation exposure and may delay plant startup.

To verify closure of this valve requires a backflow/leakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure along with a high potential for delaying plant startup due to the significant amount of piping required to be filled and vented.

Alternative Test This check valve will be exercised open and closed during each refueling outage.

Page 117 Revision Revision Date: 02/11/04 Date: 02/11/104 Page 117

1ST ProgramPlan FloridaPower andLight Company TurkeV Point Nuclear Power Plant Refueling Outage Justification RJ-14 Component Ta2 SVstem Safety Class Cate0orv 3-312C 047 1 AC 4-312C 047 1 AC Function This check valve must open to provide a flow path from the charging pump to the reactor coolant system during emergency boration. The valve must open to provide a flow rate of 45 gpm during a rod cluster control assembly accident requiring emergency boration. During normal power operation, this valve opens to provide the normal return flow path from the charging pump to the reactor coolant system to support processing of the water let down from the reactor coolant system. This valve must close to isolate containment from the chemical and volume control system during accident conditions when the charging line is not required. The valve is considered a-containment isolation valve for Penetration 15.

Justification It is impracticable to exercise this check valve closed during normal power operations since interruption of charging flow may result in a plant trip. During cold shutdowns it is impracticable to exercise this check valve closed since closure testing imposes an increase in personnel radiation exposure and may delay plant startup.

To verify closure of this valve requires a backflow/leakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure along with a high potential for delaying plant startup due to the significant amount of piping required to be filled and vented.

Alternative Test This check valve will be exercised closed during each refueling outage.

Page 118 Revision Date: 02/11/04 Date: 02/111/04 Page 118

ISTProgramPlan FloridaPower and Light Company Turkey PointNuclear Power Plant Refueling Outage Justification RJ-15 Component Ta2 Svstem Safety Class Catesorv 3-351 047 2 C 4-351 047 2 C Function This check valve must open to provide a flow path from the boric acid pumps to the suction of the charging pumps during emergency conditions requiring emergency boration. The valve closes to prevent backflow and isolate the emergency boration flow path during normal operations and during emergency conditions when the RWST is supplying the charging pump suction for emergency boration However, normally closed upstream motor operated valve MOV-*-350 is relied upon for isolating the emergency boration flow path when it is not required. Therefore, this check valve does not perform a safety function in the closed position.

Justification It is impracticable to exercise this check valve open during normal power operations since injection of highly concentrated boric acid into the reactor coolant system may lead to a plant trip.

During cold shutdowns it is impracticable to exercise this check valve open since injection of highly concentrated boric acid into the reactor coolant system may lead to a delay in plant startup.

To exercise open position this check valve requires operation of the boric acid transfer pump at design accident flow conditions (60 gpm) to verify the check valve full open position.

Performing this test during normal power operations would result in highly concentrated boric acid being injected into the reactor coolant system resulting in a power transient and possible trip of the plant. Performance of this test during cold shutdowns would result in a potential delay of plant startup due to the high boric acid concentration in the reactor coolant system.

Alternative Test This check valve will be exercised open during each refueling outage.

Revision Date: 02/11/04 Page 119

ISTProgranm Plan FloridaPowver and Light Company Turkey Point Nuclear Power Plant Refueline Outage Justification RJ-I 6 Component Tat Svstem Safet- Class Cateeorv 3-298A 047 1 AC 3-298B 047 1 AC 3-298C 047 1 AC 4-298A 047 1 AC 4-298B 047 1 AC 4-298C 047 1 AC Function These check valves must close to isolate containment from the chemical and volume control system during accident conditions when RCP seal injection flow is not required. The valves are considered containment isolation valves for Penetrations 24A/B/C. These check valves open to provide a flow path from the charging pump to the reactor coolant pump seals during normal plant operation. This function is not required for safe shutdown or accident mitigation since the reactor coolant pumps are not required for safe shutdown or accident mitigation. Additionally, the seal injection return valves (MOV-*-381 and MOV-8-6386) receive automatic closure signal to isolate the seal injection return flow path during a safety injection.

Justification It is impracticable to exercise these check valves closed during normal power operations since interrupting seal injection flow would damage the reactor coolant pump seals. During cold shutdowns it is impracticable to exercise these check valves closed since closure testing imposes an increase in personnel radiation exposure and may delay plant startup.

To verify closure of this valve requires a backflow/leakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure along with a high potential for delaying plant startup due to the significant amount of piping required to be filled and vented.

Additionally, interrupting reactor coolant pump seal injection flow when the reactor coolant pumps are in operation would damage the pump seal and ultimately the pump.

Alternative Test These check valves will be exercised closed during each refueling outage.

Revision Date: 02/11/04 Page 120

1ST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Refueling Outage Justification RJ-17 Component Tag Svstem Safety Class Categorv 3-2052 050 2 C 4-2052 050 2 C Function This check valve must open to provide a flow path from the containment spray suction relief line to the containment recirculation sump. The containment spray suction relief valve (RV-*-871) opens to prevent overpressurization of the containment spray pump suction piping.

Overpressurization could occur due to thermal expansion should the piping become isolated with fission products in the water. This valve must close to isolate containment from the containment spray system. This valve is considered a containment isolation valve for penetration 54A.

Justification It is impracticable to exercise this check valve open or closed during normal power operations or cold shutdowns since testing requires leakage testing (to verify closure) and forward flow testing (to verify open) which would result in airborne contamination in the containment sump resulting in significant clean up efforts. which would delay unit startup. Additionally, this testing would impose an increase in personnel radiation exposure.

To verify check valve full open position requires injection of either water or air into the containment sump at 25 gpm to verify full design accident flow. This testing would cause the containment to be breached and requires the containment spray system to be aligned in an unanalyzed condition. The addition of air or water to the containment sump to perform this test would create a significant cleanup effort due to the potential for airborne contamination, thus personnel radiation exposure would be increased.

Verification of valve closure requires the performance of a leakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure. Additionally, due the amount of piping required to be isolated, drained, and vented to perform a leakage test, a delay in plant startup from the cold shutdown condition would be incurred.

Alternative Test This check valve will be exercised open and closed during each refueling outage.

Page 121 Revision Date: 02/11/04 Date: 02/11/104 Page 121

1ST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear Power Plant Refueling Outage Justification RJ-I 8 Component Tag System Safetv Class Cateeory 3-945E 064 2 AC 4-945E 064 2 AC Function This check valve must close to isolate containment from the non safety related nitrogen supply system during accident conditions. This valve is considered a containment isolation valve for Penetration 42. The valve opens to support safety injection accumulator refill to recharge and maintain the accumulators pressurized during normal power operations. This function is not required for safe shutdown or accident mitigation since the safety injection accumulators are considered a passive injection system and tank pressure is continuously monitored during normal plant operations.

Justification It is impracticable to exercise this check valve closed during normal power operations or during cold shutdowns since closure testing imposes an increase in personnel radiation exposure and may delay plant startup due the significant amount of piping required to isolated.

To verify closure of this valve requires a backflow/leakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure along with a high potential for delaying plant startup due to the significant amount of piping required to be realigned, drained, and vented.

Additionally, interrupting nitrogen supply would cause all of the safety injection accumulator tanks to be inoperable which would place the plant in an unanalyzed condition.

Alternative Test This check valve will be exercised open and closed during each refueling outage.

Revision Date: 02/11/04 Page 122

ISTProgramPlan FloridaPower and Light Company Turkey PointNuclear Power Plant Refueling Outane Justification RJ-I9 Component Tag Svstem Safety Class Categorv 3-876A 064 I AC 3-876B 064 1 AC 3-876C 064 1 AC 4-876A 064 1 AC 4-876B 064 1 AC 4-876C 064 1 AC Function These check valves open to provide flow path from the residual heat removal system to the cold leg injection points during a large break LOCA 'when the RCS is rapidly depressurized. The valve must also open to provide normal low head injection during the injection phase of an accident. These check valves must close or remain closed to prevent reverse flow when the safety injection pump or accumulators are required to inject flow to the cold leg. The valve is also required to close when RHR is in service for alternate low head injection during the recirculation phase of an accident. The valve is required to close to isolate the reactor coolant system from the lower pressure residual heat removal system during emergency conditions when the residual heat removal system is not required. This valve is considered a pressure isolation valve, required to maintain the RCS pressure boundary. The valve must close to limit leakage to

<1.0 gpm.

Justification It is impracticable to exercise these valves open during normal power operations or during cold shutdowns since injection into the reactor is required to perform open exercise testing. The residual heat removal system is not designed to inject at elevated pressures and testing imposes an increase in personnel radiation exposure and may cause a delay in plant startup.

Exercising these valves open requires the residual heat removal pump to deliver flow to the reactor vessel, thereby, exercising open the subject check valves. This testing cannot be performed during normal power operations since the reactor vessel is at approximately 2000 psig.

The design discharge pressure of the residual heat removal pump is approximately 600 psig.

Additionally, injection into the vessel would cause severe thermal transients resulting in a trip of the reactor. Since these valves do not have individual flow instruments, non-intrusive techniques are required to verify the full open exercise. This testing requires containment entry and significant test preparation, which may cause a delay in plant startup. Additionally, entry into containment for test preparation, performance and restoration even during cold shutdowns imposes a significant increase in radiation exposure to plant personnel.

Alternative Test These valves will be exercised open during each refueling outage.

Page 123 Revision Date: 02/11/04 Date: 02/111/04 Page 123

IST ProgramPlan FloridaPouer and Light Company Turkev Point Nuclear Power Plant ATTACHMENT 10 STATION TECHNICAL POSITION INDEX (Page I of I)

Technical es tion Position No. i TPv-0I ll Bi-directional Testing of Check Valves TPv-02 ll Check Valve Condition Monitoring TPv-03 I[ Passive Valves Without Test Requirements TPv-04 l Fail Safe Testing of Valves TPv-05 I[Classification of Skid Mounted Components TPv-06 l[ D/E of AFW Pump Lube Oil Cooling Water Return Check Valves TPv-07 l Primar Water Check Valve Considered Passive TPv-08 Check Valve Closure Verification in Conjunction with Appendix J Seat Leakage if l_ _ lTesting TPv-09 Testing of Power Operated Valves with both Active and Passive Safety l_ Functions TPv- 10 ll Breathing Air Check Valve Considered Passive TPv- II Manual Valve Exercise Frequency TPv-12 [ Method for Establishing Acceptance Criteria for Power Operated Valves TPp-01 I[ Containment Spray Pump Category B Pump Testing lTPp-A l Categorization of IST Pumps (Group A or B)

Revision Date: 02/11/04 Page 124

IST Program Plan FloridaPower andLight Company Turkey Point Nuclear Power Plant ATTACHMENT 11 STATION TECHNICAL POSITIONS Revision Date: 02/11/04 Page 125

IST ProgramPlan FloridaPower andLight Company Turkey PointNuclearPowter Plant Technical Position TPv-01 (Page I of 3)

Bi-directional Testing of Check Valves Purpose The purpose of this Technical Position is to establish the station position for the verification of the non-safety direction exercise testing of check valves by normal plant operations.

Applicabiliht This Technical Position is applicable to testing of the non-safety function (direction) of check valves which are included in the Inservice Testing Program. This position applies to those check valves required to be tested in accordance with Subsection ISTC (ASME OM Code 1998 Edition through 2000 Addenda) and Appendix 11 - Condition Monitoring (ASME OM Code 1995 Edition through 1996 Addenda). This Technical Position does not apply to testing of the safety function (direction) of check valves included in the Inservice Testing Program.

Background

The ASME OM Code 1998 through 2000 Addenda section ISTC-3550, "Valves in Regular Use",

states:

"Valves that operate in the course of plant operation at a frequency that would satisfy the exercising requirements of this Subsection need not be additionally exercised, provided that the observations otherwise required for testing are made and analyzed during such operation and recorded in the plant record at intervals no greater than specified in ISTC-3510."

Section ISTC-3510 requires that check valves shall be exercised nominally every 3 months with exceptions (for extended periods) referenced.

Section ISTC-5221(a)(2) states:

"Check valves that have a safety function in only the open direction shall be exercised by initiating flow and observing that the obturator has traveled to either the full open position or to the position required to perform its intended function(s) (see ISTC- I100),

and verify closure."

Section ISTC-5221(a)(3) states:

"Check valves that have a safety function in only the close direction shall be exercised by initiating flow and observing that the obturator has traveled [to] at least the partially open position,2 and verify that on cessation or reversal of flow, the obturator has traveled to the seat."

"2The partially open position should correspond to the normal or expected system flow."

Revision Date: 02/11/04 Page 126

1ST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Powver Plant Technical Position TPv-01 (Page 2 of 3)

Normal or expected system flow may vary with plant configuration and alignment, however, the open "safety function" of a check valve typically requires a specified design accident flow rate.

Since Turkey Point Operations staff is trained in recognizing normal plant conditions, Operator judgment is acceptable in determining the check valve non-safety direction by obtaining normal or expected flow rates for the plant operating condition.

In summary, check valve non-safety function direction is satisfactorily demonstrated by verifying closure or passing normal or expected flow as applicable.

Position Turkey Point will verify the non-safety position of check valves included in the Inservice Testing Program using the plant surveillance program. In lieu of a dedicated surveillance to perform the non-safety direction testing, the following alternate verifications may be performed as follows:

1. An appropriate means shall be determined which establishes the method for determining the open/closed non-safety function of the check valve during normal operations. The position determination may be by direct indicator, or by other positive means such as changes in system pressure, flow rate, level, temperature, seat leakage, etc. This determination shall be documented in the respective Condition Monitoring Plan for the specific check valve group. For check valves included in the Inservice Testing Program and not included in the Condition Monitoring Plan, this determination shall be documented in the IST Bases Document for the specific check valve group.

2. Observation and analysis of plant processes that a check valve is satisfying its' non-safety direction function may used. As an example, a check valve that has a safety function only in the closed direction and normally provides a flow path to maintain plant operations. If the check valve is not open to pass flow, an alarm or indication would identify a problem to the operator. The operator would respond to take appropriate actions. A Condition Report would then be generated for the abnormal plant condition which would identify the check valve failure.

3. Observation and analysis of plant logs and other records satisfied by Operator or Engineering reviews may be an acceptable method for verifying a check valves non-safety direction during normal plant operations.

The open/closed non-safety function shall be recorded at a frequency required by ISTC-3510, nominally every 3 months, with exceptions as provided, in plant records such as Turkey Point Operating Logs, Electronic Rounds, chart recorders, automated data loggers, etc. The safety function direction testing requires a Quality Record in the form of a surveillance test. Records as indicated above in I through 3 are satisfactory for the non-safety direction testing. A condition report shall be generated for any issues regarding check valve operability.

Revision Date: 02/11/04 Page 127

1ST ProgramPlan FloridaPowver andLight Company Turkey Point Nuclear Power Plant Technical Position TPv-01 (Page 3 of 3)

Justification This Technical Position requires that the method of determining the non-safety position be established and documented in either the Condition Monitoring Plan or the IST Bases Document.

The plant systems and operator actions provide for the observations and analysis that the valve is satisfying its' non-safety function. Additionally, the recording of parameters which demonstrate valve position is satisfied at a frequency in accordance with ISTC-3510. These actions collectively demonstrate the non-safety position of Inservice Testing Program check valves in regular use as required by ISTC-3550.

Revision Date: 02/11/04 Page 128

1ST Program Plan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Technical Position TPv-02 (Page I of 5)

Check Valve Condition Monitoring Purpose The purpose of this Technical Position is to document Turkey Point's position on establishing and implementing a Check Valve Condition Monitoring Program in accordance with mandatory Appendix 11 of the ASME OM Code 1995 Edition through 1996 Addenda and the associated modifications delineated in the Federal Register Volume 64, No. 183. The Condition Monitoring Program specified in Appendix 11 provides certain flexibility in establishing test types, examinations, and preventive maintenance activities along with their associated intervals, when justified based on check valve performance and operating condition.

Applicability This Technical Position is applicable to certain valves or groups of valves as permitted by ISTC-5222, Condition Monitoring Program.

Background

IOCFR50.55a was revised 9/22/99 to endorse the ASME OMa-1995 Edition with 1996 Addenda with modifications. This edition of the ASME OM Code provides provisions to implement a check valve condition monitoring program for selected valves or groups of valves in accordance with mandatory Appendix 11. Turkey Point's Inservice Testing Program for the 4 th Ten Year Interval has been developed in accordance with the ASME OM Code 1998 Edition through 2000 Addenda. This edition of the Code provides an alternative in section ISTC-5222, Condition Monitoring Program, to the testing requirements of ISTC-3510, ISTC-3520, ISTC-3540 and ISTC-5221. This section specifies that the program shall be implemented in accordance with Appendix 11, Check Valve Condition Monitoring Program and the modifications stated in the Federal Register.

Position Turkey Point will implement a Check Valve Condition Monitoring program for selected valves or groups of valves in accordance with ISTC-5222 and Appendix II. The following guidelines will be adhered to for administering this program. Additionally, if the Appendix 11 program is discontinued for a valve or group of valves, then the requirements of ISTC-3510, ISTC-3520, ISTC-3550, and ISTC-3521 shall be implemented.

1. Purpose The purpose of the Check Valve Condition Monitoring Program is to improve check valve performance and to optimize testing, examination, and preventive maintenance activities in order to maintain the continued acceptable performance of a select valve or group of valves.

Revision Date: 02/11/04 Page 129

IST ProgramPlan FloridaPowver and Light Company Turkey Point Nuclear Power Plant Technical Position TPv-02 (Page 2 of 5)

2. Scope The Turkey Point Valve Check Valve Condition Monitoring Program will be applied to individual check valves or groups of check valves which are either candidates for improved performance or candidates which will be monitored for improved valve performance.

a. Candidates for improved valve performance are those check valves which may exhibit one or more of the following attributes:

i. The valve(s) exhibits an unusually high failure rate during inservice testing or operations; ii. The valve(s) can not be exercised under normal operating conditions or during shutdown; iii. The valve(s) exhibits unusual, abnormal, or unexpected behavior during exercising or operations.

b. Candidates for monitoring for improved valve performance using optimization techniques, examination, and preventive maintenance activities are those check valves with documented acceptable performance that:

i. Have had their performance improved under this program; ii. Cannot be exercised or are not readily exercised during normal operating condition or during shutdown; iii. Can only be disassembled and examined; or iv. It is decided that all of the associated activities of the valve or group will be optimized.

3. Groupings For valves which are grouped together the following valve attributes shall be considered:

a. Valves shall be of the same manufacturer, design, size, service media, materials of construction, and orientation.

b. Maintenance and modification history shall be reviewed.

c. Test history and results shall be reviewed.

d. System design shall be considered to determine potential flow instabilities, degree of disassembly, and the need for tolerance and dimensional measurements Page 130 Revision Date: 02/11/04 Date: 02/11/104 Page 130

1ST ProgramPlan FloridaPowver andLight Company Turkey Point NuclearPowver Plant Technical Position TPv-02 (Page 3 of 5)

4. Analysis An analysis of the test and maintenance history shall be performed to establish the basis for specifying inservice testing, examination, and preventive maintenance activities. This analysis shall include the following:

a. Identify any common failure mode or corrective maintenance patterns.

b. Analyze these common patterns to determine their significance and to identify potential failure mechanisms:

i. Determine if certain preventive maintenance activities would mitigate the failure or maintenance patterns; ii. Determine if certain condition monitoring activities are possible and effective in monitoring for these failure mechanisms; iii. Determine if periodic disassembly and examination would be an effective method in monitoring for these failure mechanisms.

iv. Determine if the valve grouping is required to be changed.

5. Condition Monitorinig Activities

a. Performance Improvement Activities

i. If sufficient information is not available or the results of the analysis performed in 4 above are not conclusive, an interim period not to exceed 2 refueling outages shall be established to determine the cause of the failure or maintenance patterns. The following activities shall be performed at sufficient intervals over the interim period.

1. Identify interim tests (e.g. nonintrusive) to assess the performance of the valve of group of valves.

2. Identify interim examinations to evaluate potential degradation mechanisms.

3. Identify other types of analysis to be performed which will assess check valve condition.

4. Identify which of these activities will be performed on each valve.

5. Identify the interval of each activity.

ii. Complete or revise the condition monitoring test plans to document the check valve program performance improvement activities and their associated frequencies.

iii. Perform these activities at their assigned intervals unit:

1. Sufficient information is obtained to permit an adequate analysis.

2. Until the end of the interim period (2 refueling outages or 3 years, whichever is longer).

Revision Date: 02/11/04 Page 13 1

1ST Program Plan FloridaPowver andLight Company Turkey Point Nuclear PowterPlant Technical Position TPv-02 (Page 4 of 5) iv. After performance, a review shall be performed for each activity to determine if changes to the program are required. If changes are required, the program shall be revised before the next performance of the activity.

b. Optimization of Condition Monitoring Activities

i. If sufficient information is available to assess the performance adequacy of the check valve or group, then the following activities shall be performed:

1. Identify appropriate preventive maintenance activities including the intervals that are required to maintain the continued acceptable performance of the check valve or group of check valves.

2. Identify the applicable examination activities including the interval that will be used to periodically assess the condition of each check valve or group of check valves.

3. Identify the applicable test activities including intervals that will be used to periodically verify the acceptable performance of each check valve or group of check valves.

4. Identify which of these activities, including the interval, will be performed on each valve in the group.

ii. Revise the condition monitoring plans to document the optimized condition monitoring program activities and associated intervals for each activity.

iii. Continue performance of these activities at their associated intervals.

iv. Review the results of the performance of each activity to determine if changes to the optimized condition monitoring program are required.

6. Test Requirements and Frequency The following requirements apply when implementing the above plans for a single valve or group of valves

a. Valve opening and closing functions must be demonstrated when flow testing or examination methods (nonintrusive, or disassembly and inspection) are used.

b. The initial interval for tests and associated examinations may not exceed two fuel cycles or 3 years, whichever is longer.

c. Extension of the initial interval may not exceed one fuel cycle per extension with the maximum interval not to exceed 10 years.

Revision Date: 02/11/04 Page 132

IST ProgramPlan FloridaPowver and Light Company Turkey Point Nuclear Powver Plant Technical Position TPv-02 (Page 5 of 5)

d. Trending and evaluation of existing data must be used to reduce or extend the time interval between tests.

7. Documentation The condition monitoring program shall be documented per the Check Valve Condition Monitoring Administrative Procedure. The plan for each check valve or group of check valves shall be documented in the Condition Monitoring Tab and shall contain as a minimum the following information:

a. The list of valves in each group including the group basis.

b. Date the valve or group of valves was evaluated for inclusion or exclusion from the condition monitoring program.

c. Safety function of valve or valve group.

d. Analysis/justification which forms the basis for the program.

e. Identification of the failure or maintenance patterns for each valve

f. Condition monitoring activities including intervals for each valve or valve group.

g. Expert Panel review results and comments Revision Date: 02/11/04 Page 133

ISTProgram Plan FloridaPower and Light Company Turkey Point Nuclear Power Plant Technical Position TPv-03 (Page 1 of 1)

Passive Valves Without Test Requirements Purpose The purpose of this Technical Position is to establish the station position for valves which perform a passive safety function, however, no testing in accordance with ISTC is required.

Applicability This Technical Position is applicable to valves wvhich perform a passive function in accordance with ISTC-2000 and do not have inservice testing requirements per Table ISTC-3500-1. This position is typical of Category B, passive valves which do not have position indication.

"An example is a manual valve which must remain in its normal position during an accident, to perform its intended function."

Typically, manual valves which perform a safety function, are locked in their safety position and administratively controlled by TPN procedures. These valves would be considered passive. If they do not have remote position indicating systems and categorized as B, they would not be subjected to any test requirements in accordance with Table ISTC-3500-1.

Position The TPNP Inservice Testing Program, Valve Tables - Attachment 13, will not list valves which meet the following criteria.

• The valve is categorized B (seat leakage in the closed position is inconsequential for fulfillment of the valves' required function(s)) in accordance with ISTC-1300.

• The valve is considered passive (valve maintains obturator position and is not required to change obturator position to accomplish the required function(s)) in accordance with ISTC-2000.

• The valve does not have a remote position indicating system which detects and indicates valve position.

Justification Valves which meet this position will not be listed in the TPNP Inservice Testing Program, Valve Tables - Attachment 13, however, the basis for categorization and consideration of active/passive functions shall be documented in the IST Program Basis Document.

Page 134 Date: 02/11/04 Revision Date: 02111104 Page 134

1ST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Technical Position TP%-04 (Page 1 of 1)

Fail Safe Testing of Valves Purpose The purpose of this Technical Position is to establish the station position for fail safe testing of valves in conjunction with stroke time exercising or position indication testing.

Applicabilitv This Technical Position is applicable to valves with fail safe actuators required to be tested in accordance with ISTC-3560.

Background

The ASME OM Code 1998 through 2000 Addenda section ISTC-3560 requires; "Valves with fail-safe actuators shall be tested by observing the operation of the actuator upon loss of valve actuating power in accordance with the exercising frequency of ISTC-3510."

Section ISTC-3510 states; "Active Category , Category B, and Category C check valves shall exercised nominally every 3 months..."

Position In cases where normal valve operator action moves the valve to the open or closed position by de-energizing the operator electrically, by venting air, or both, the exercise test will satisfy the fail safe test requirements and an additional test specific for fail safe testing will not be performed.

Turkey Point Nuclear Plant will also use remote position indication as applicable to verify proper fail safe operation, provided that the indication system for the valve is periodically verified in accordance with ISTC-3700.

Justification Turkey Point Nuclear Plant Inservice Testing Program valves that fail open or closed upon loss of actuator power use the fail safe mechanism to stroke the valve to its safety position. For example, an air operated valve that fails closed may use air to open the valve against spring force. When the actuator control switch is placed in the closed position, air is vented from the diaphragm and the spring moves the obturator to the closed position.

Page 135 Revision Revision Date: 02/11/04 Date: 02111104 Page 135

1ST ProgramPlan FloridaPouer andLight Company Turkey Point Nuclear Pointer Plant Technical Position TPv-05 (Page 1 of 2)

Classification of Skid Mounted Components Purpose The purpose of this technical position is to clarify requirements for classification of various skid mounted components, and to clarify the testing requirements of these components.

Background

The ASME Code allows classification of some components as skid mounted when their satisfactory operation is demonstrated by the satisfactory performance of the associated major components. Testing of the major component is sufficient to satisfy Inservice Testing requirements for skid mounted components. In section 3.4 of NUREG 1482, the NRC supports the designation of components as skid mounted:

"The staff has determined that the testing of the major component is an acceptable means for verifying the operational readiness of the skid-mounted and component subassemblies if the licensee documents this approach in the IST Program. This is acceptable for both Code class components and non-Code class components tested and tracked by the IST Program."

In the 1996a addenda to the ASME OM Code (endorsed by IOCFR50.55(a) in October 2000), the term skid-mounted was clarified by the addition of ISTA paragraph 1.7:

ISTA 1.7 Definitions Skid mounted components and component sub assemblies - components integral to or that support operation of major components, even though these components may not be located directly on the skid. In general, these components are supplied by the manufacturer of the major component. Examples include: diesel skid-mounted fuel oil pumps and valves, steam admission and trip throttle valves for high-pressure coolant injection or auxiliary feedwater turbine-driven pumps, and solenoid-operated valve provided to control the air-operated valve.

This definition was further clarified in the 1998 Edition of the ASME Code:

ISTA-2000 DEFINITIONS Skid mounted pinups and valves - pumps and valves integral to or that support operation of major components, even though these components may not be located directly on the skid. In general, these pumps and valves are supplied by the manufacturer of the major component. Examples include:

(a) diesel fuel oil pumps and valves; (b) steam admission and trip throttle valves for high-pressure coolant injection pumps; (c) steam admission and trip throttle valves for auxiliary feedwvater turbine driven pumps; (d) solenoid-operated valves provided to control an air-operated valve.

Revision Date: 02/11/04 Page 136

ISTProgramPlan FloridaPower and Light Company Turkey Point Nuclear Power Plant Technical Position TP~v-05 (Page 2 of 2)

Additionally the Subsections pertaining to pumps (ISTB) and valves (ISTC) includes exclusions/exemptions for skid mounted components; ISTB-1200(c) Exclusions Skid-mounted pumps that are tested as part of the major component and are justified by the Owner to be adequately tested.

ISTC-1200 Exemptions Skid-mounted valves are excluded from this Subsection provided they are tested as part of the major component and are justified by the Owner to be adequately tested.

Position The 1998 ASME OM Code definition of skid mounted should be used for classification of components in the Turkey Point Inservice Testing Program. In addition, for a component to be considered skid mounted:

• The major component associated with the skid mounted component must be surveillance tested at a frequency sufficient to meet ASME Code test frequency for the skid mounted component.

• Satisfactory operation of the skid mounted component must be demonstrated by satisfactory operation of the major component.

• The IST Bases Document should describe the bases for classifying a component as skid mounted, and the IST Program Plan should reference this technical position for the component.

Justification Classification of components as skid mounted eliminates the need for testing of sub components that are redundant with testing of major components provided testing of the major components demonstrates satisfactory operation of the "skid mounted" components.

Revision Date: 02/11/04 Page 137

1ST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear Power Plant Technical Position TPv-06 (Page 1 of 2)

Disassembly and Examination of AFW Pump Lube Oil Cooling Water Return Check Valves Purpose The purpose of this Technical Position is to establish the station position for the sample disassembly and examination program for groups of check valves which are impractical to test using flow, system pressure, level, temperature, seat leakage or nonintrusive techniques in accordance with ISTC-5221(a) and ISTC-5221(b).

Applicability This Technical Position is applicable to Auxiliary Feedwater Pump Lube Oil Cooling Water Return Check Valves AFWU-3-017 AFWU-4-016 This check must open to provide a return flow path of cooling water from the auxiliary feedwater pump lube oil cooler to the condensate storage tank when the auxiliary feedwater pump is required to be operated. Lube oil cooling water is required to ensure proper AFW pump operation. The valve must open to provide 60 gpm (20 gpm per pump) of return flow when three auxiliary feedwater pumps are operating. This check valve is required to close to prevent backflow from the condensate storage tank to the lube oil cooling water return header when the auxiliary feedwater pumps are not in operation. This function is necessary to conserve condensate storage tank inventory.

Background

The ASME OM Code 1998 through 2000 Addenda section ISTC-3510 requires check valves to be exercised nominally every 3 months, except as provided in ISTC-5221 and ISTC-5222.

ISTC-5221(c) states that, "If the test methods in ISTC-522 1(a) and ISTC-522 I(b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement."

Position For the subject valves, TPNP will verify check valve obturator movement using a disassembly and examination program in accordance with the following:

• Check valves are grouped in accordance with ISTC-5221(c) such that the valve in the group are of similar design, application and service condition. In accordance with ISTC-5221(c)(1) the grouping of check valves shall consider as a minimum, valve manufacturer, design, service, size, material of construction , and orientation.

Revision Date: 02/11/04 Page 138

ISTProgram Plan FloridaPower andLight Company Turkey Point Nuclear Powrer Plant Technical Position TPv-06 (Page 2 of 2)

• In accordance with ISTC-5221(c)(2) during the disassembly process, the full stroke motion of the obturator shall be verified. Immediately prior to reassembly, the full stroke motion of the obturator shall be reverified. Check valves that have their obturator disturbed before full stroke motion is verified shall be examined to determine if a condition exists that could prevent full opening or reclosure of the obturator.

• At least one valve from the group shall be disassembled and examined at each refueling outage with all valves in the group being disassembled and examined at least once every 8 years in accordance with ISTC-5221(c)(3).

• Per the requirements of ISTC-5221(c)(4), before return to service, valves that were disassembled for examination or that have received maintenance that could affect their performance, shall be exercised full or partial stroke, if practicable, with flow. Those valves shall also be tested for other requirements if applicable (closure verification or seat leakage testing) before returning them to service.

• The corrective actions of ISTC-5224 shall be applied. Check valves in a sample disassembly and examination program that are not capable of full stroke movement, or have failed or have unacceptably degraded valve internals, shall have the cause of failure analyzed and the condition corrected. Other check valves in the sample group that may also be affected by this failure mechanism shall be examined or tested during the same refueling outage to determine the condition of internal components and their ability to function.l

'An evaluation should be made to determine if there are valves outside the sampling group that could be affected by the failure mechanism. Valves that are determined to be directly affected by the failure mechanism should be examined or tested.

Justification To full stroke exercise these check valves requires operation of the design accident flow conditions. This test is impracticable to perform during any operating or non operating condition due to the extensive amount of cleanup required.

These valves will be included in a sample disassembly and examination program in accordance with ISTC-5221(c).

Page 139 Date: 02/11/04 Revision Date: 02111104 Page 139

IST Program Plan FloridaPowver andLight Company Turkev Point Nuclear Power Plant Technical Position TPv-07 (Page I of 2)

Primary Water Check Valve Considered Passive Purpose The purpose of this Technical Position is to establish the station position for classification and categorization of the Primary Water to Containment Check Valve as Passive category A.

Applicability This Technical Position is applicable to Primary Water to Containment Check Valve:

3-10-567 4-10-567 This check valve must close to isolate containment from the primary water system. This valve provides containment isolation for Penetration 47. Penetration 47 is considered a non essential penetration which is not required to be in service post accident. This valve opens to provide a flow path from the primary water supply header to containment during cold shutdown or refueling. This function provides a supply source to facilitate maintenance and testing during outages. This function is not required for safe shutdown or accident mitigation. Additionally, downstream manual valve *-10-582 inside containment is administratively maintained in the locked closed position during normal power operations. The primary water system is not required for safe shutdown or accident mitigation.

Background

The ASME OM Code 1998 through 2000 Addenda section ISTC-2000 provides a definition of passive valves.

"passive valves: valves that maintain obturator position and are not required to change obturator position to accomplish the required function(s)"

The Code also provides valve category definitions as follows:

"Category A - valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required function" "Category C - valves that are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) for fulfillment of the required functions" Position Turkey Point Nuclear Plant classifies this valve as passive since it is not required to change position to perform its intended function. The valve has been categorized as Category A since it is not self actuated due to the downstream line being isolated.

Revision Date: 02/11/04 Page 140

1ST Program Plan FloridaPowver and Light Company Turkey Point Nuclear Powver Plant Technical Position TPv-07 (Page 2 of 2)

Justification This penetration is isolated during all modes of operation when containment integrity is required and is not in service during any emergency or post accident conditions. Therefore this valve only performs a containment isolation function and not required to open or close for any other function. Since the valve is normally closed, and since a dead leg exists downstream, this valve is considered passive. No exercising testing is required since the valve is considered a category A valve based on ISTC-1300, Valve Categories.

The valve is seat leakage tested in accordance with Appendix J requirements.

Revision Date: 02/11/04 Page 14 1

IST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear PowerPlant Technical Position TP-*-08 (Page 1 of 1)

Check Valve Closure Verification in Conjunction with Appendix J Seat Leakage Testing Purpose The purpose of this Technical Position is to establish the station position for the verification of check valve closure in conjunction with Appendix J leakage testing.

Applicability This Technical Position is applicable check valves included in the 1ST Program which are categorized as AC and are Containment Isolation Valves:

Back2round These check valves are categorized as AC in accordance with ASME OM Code ISTC-1300, Valve Categories:

"Category A - valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required function" "Category C - valves that are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) for fulfillment of the required functions" Based on the valve category, the following test requirements of Table ISTC-3500-1 apply:

Category A test Leakage Test in accordance with Appendix J Program Category C test Check Valve Exercise Test Open and Closed Position These valves require a seat leakage test in accordance with IOCFR50 Appendix J and a closure verification in accordance with ISTC-3522. Turkey Point Nuclear Plant will perform the Category C testing in accordance with the frequency requirements of ISTC-3510 where practicable. If testing is not practicable during quarterly operations or during shutdowns, the check valve will be tested during refueling outages.

The verification of check valve closure will be performed as the seat leakage test required by Appendix J.

Justification All valves for this position will be documented in the 1ST Program Plan as category AC. A deferred testing justification shall also be documented describing the impracticability of performing a closure test during normal operations or during cold shutdowns.

Revision Date: 02/11/04 Page 142

1ST Program Plan FloridaPower and Light Company Turkev Point Nuclear Power Plant Technical Position TPv-09 (Page 1 of 2)

Testing of Power Operated Valves with Both Active and Passive Safety Functions Purpose The purpose of this Technical Position is to establish the testing requirements for power operated valves which have both an active and passive safety function.

Applicabilitv This Technical Position is applicable to power operated valves which have an active safety function in one direction while performing a passive safety function in the other direction. The following valves apply to this situation at TPNP:

Valve Tag No. Active Safety Passive Safety Direction Direction LCV-*-1 15B Open Closed MOV-*-350 Open Closed MOV-*-535 Closed Open MOV-*-536 Closed Open MOV-*-749A/B Open Closed MOV-*-856A/B Closed Open MOV-*-860A/B Open Closed MOV-*-861 A/B Open Closed MOV-*-862A/B Closed Open MOV-*-863A/B Open Closed MOV-*-864A/B Closed Open MOV-*-865A/B/C Closed Open MOV-*-872 Open Closed MOV-878A/B Closed Open SV-*-6318A/B Closed Open SV-*-6611 Open Closed SV-*-6612 Open Closed Backeround The IST Program requires valves to be exercised to the position(s) required to fulfill their safety function(s). In addition, valves with remote position indication shall have their position indication verified. The Code does not restrict position indication to active valves.

Position Several valves included in the plant are designed to perform passive safety functions during accident conditions, and then based on plant accident response, are designed to change positions to perform another (active) function. Once in their final position, there exist no conditions in which they would be required to be placed in their original passive position.

Page 143 Revision Date: 02/11/04 Date: 02/111/04 Page 143

1ST ProgramPlan FloridaPower and Light Company Turkey Point Nuclear Power Plant Technical Position TPv-09 (Page 2 of 2)

These valves are typically emergency core cooling system valves, which require changing position during different phases of the accident. After the original passive safety function (e.g.

provide flow path) is performed, the valves are repositioned to perform the active safety function (e.g. provide containment isolation or to allow injection from another water source). The valves are not required to return to their original position.

Power operated valves with passive functions in one direction and active in the other, will be exercised and stroke timed to only their active position. If these valves have position indication, the position indication verification will include verification of both positions.

Justification Code Interpretation 01-02 (response to inquiry OMI 99-07) addressed this issue.

Question: If a valve has safety functions in both the open and closed positions and is maintained in one of these positions, but is only required to move from the initial position to the other and is not required to return to the initial position, is stroke timing in both directions required?

Reply: No Revision Date: 02/11/04 Page 144

IST Program Plan FloridaPower and Light Company Turkey Point Nuclear Power Plant Technical Position TP'-I10 (Page 1 of 2)

Breathing Air Check Valve Considered Passive Purpose The purpose of this Technical Position is to establish the station position for classification and categorization of the Containment Breathing Air Check Valve as Passive category A.

Applicabilitv This Technical Position is applicable to Containment Breathing Air Check Valve:

BA-3-201 BA-4-201 This check valve must close to isolate containment from the breathing air system. This valve provides containment isolation for Penetration 30. Penetration 30 is considered a non essential penetration which is not required to be in service post accident. This valve opens to provide a flow path from the breathing air receiver to containment during cold shutdown or refueling. This function is not required for safe shutdown or accident mitigation. The breathing air system is only required to function during cold shutdown or refueling. Additionally, upstream air operated valve CV-*-6165 outside containment is administratively maintained in the locked and pinned closed position during normal plant operation.

Backaround The ASME OM Code 1998 through 2000 Addenda section ISTC-2000 provides a definition of passive valves.

"passive valves: valves that maintain obturator position and are not required to change obturator position to accomplish the required function(s)"

The Code also provides valve category definitions as follows:

"Category A - valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required function" "Category C - valves that are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) for fulfillment of the required functions" Position TNPP classifies this valve as passive since it is not required to change position to perform its intended function. The valve has been categorized as Category A since it is not self actuated due to the downstream line being isolated.

Page 145 Revision Date:

Revision 02/11/04 Date: 02111104 Page 145

IST ProgramPlan FloridaPowerand Light Company Turkey PointNuclear Powt'er Plant Technical Position TPv-10 (Page 2 of 2)

Justification This penetration is isolated during all modes of operation when containment integrity is required and is not in service during any emergency or post accident conditions [0-OP-101]. Therefore, this valve only performs a containment isolation function and is not required to open or close for any other safety function. Since the valve is normally closed, with the upstream piping administratively locked and pinned closed by CV-*-6165, and a dead leg exists downstream, this valve is considered passive. No exercising testing is required since the valve is considered a category A valve based on ISTC-1300, Valve Categories.

The valve is seat leakage tested in accordance with Appendix J requirements.

Page 146 Revision Date: 02/11/04 Date: 02/111/04 Page 146

ISTProgramPlan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Technical Position TPv-I1 (Page 1 of 2)

Manual Valve Exercise Frequency Purpose The purpose of this Technical Position is to establish the station position for the frequency of exercising those manual valves which are required to be exercised.

Applicability This Technical Position is applicable to the manual valves included in the Inservice Testing Program.

Backeround The ASME OM Code 1998 through 2000 Addenda section ISTC-3540 states; "Manual valves shall be full-stroke exercised at least once every 5 years, except where adverse conditions' may require the valve to be tested more frequently to ensure operational readiness."

'Harsh service environment, lubricant hardening, corrosive or sediment laden process fluid, or degraded valve components are some examples of adverse conditions.

In the Federal Register for the Proposed Rule Change dated September 26, 2002, the NRC stated the following with regards to manual valve exercise frequency; "Section 50.55a(b)(3)(vi) in the proposed rule would require an exercise interval of 2 years for manual valves within the scope of the ASME OM Code rather than the exercise interval of 5 years specified in the 1999 and the 2000 Addenda of the ASME Code. The 1998 Edition of the ASME OM Code specified an interval of 3 months for manual valves within the scope of the Code. The 1999 Addenda to the ASME OM Code revised ISTC-3540 to extend the exercise frequency for manual valves to 5 years."

The NRC goes further to state that; "Section 50.55a(b)(3)(vi) is revised to clarify that the interval for exercising manual valves may not exceed 2 years when using the 1999 Addenda and 2000 Addenda of ISTC-3540" Revision Date: 02/11/04 Page 147

ISTProgram Plan FloridaPowver and Light Company Turkey Point Nuclear Power Plant Technical Position TPv-1 I (Page 1 of 2)

Position Turkey Point Nuclear Plant will perform exercising of manual valves within the scope of the IST Program at a frequency not to exceed 2 years.

Justification The NRC Rule Change will be adopted for the frequency of exercising manual valves at least once every 2 years. This interval is more frequent than required by the Edition of the Code used by TPNP, therefore no other justification is required.

Revision Date: 02/11/04 Page 148

1ST Program Plan FloridaPowerand Light Company Turkey Point Nuclear Power Plant Technical Position TPv-12 (Page I of 2)

Method for Establish Acceptance Criteria for Power Operated Valves Purpose The purpose of this Technical Position is to establish the station position for establishing the stroke time acceptance criteria for power operated valves, including the Limiting Stroke time.

Applicabilitv Power Operated Valves Requiring Stroke Time Testing

Background

The IST Program requires that a valves' stroke time reference value be established in accordance with ASME OM Code 1998 through 2000 Addenda section ISTC-3300. In accordance with the definition in ISTC-2000, reference values are defined as follows:

"one or more values of test parameters measure when the equipment is know to be operating acceptably."

Acceptable ranges are then determined based on these reference values in accordance with ISTC-5114 for Power Operated Relief Valves, ISTC-5122 for Motor Operated Valves, ISTC-5132 for Pneumatically Operated Valves, ISTC-5142 for Hydraulically Operated Valves, and ISTC-5152 for Solenoid Operated Valves.

In accordance with the Valve Stroke Testing requirements for the various operator types, the limiting value(s) of full-stroke time of each valve shall be specified by the Owner. Subsection ISTC does not provide specific guidance on determining the limiting value(s). In accordance with NRC Generic Letter 89-04, "Guidance on Developing Acceptable Inservice Testing Programs" "the limiting value should be a reasonable deviation from this reference stroke time based on the valve size, valve type, and actuator type. The deviation should not be so restrictive that it results in a valve being declared inoperable due to reasonable stroke time variations. However, the deviation used to establish the limit should be such that corrective action would be taken for a valve that may not perform its intended function.

When the calculated limiting value for a full-stroke is greater than a Technical Specification (TS) or safety analysis limit, the TS or safety analysis limit should be used as the limiting value of full-stroke time.

Position Turkey Point Nuclear Plant will use Table TPv-12-1 to establish Acceptable Ranges in accordance with ISTC-5114 for Power Operated Relief Valves, ISTC-5122 for Motor Operated Valves, ISTC-5132 for Pneumatically Operated Valves, ISTC-5142 for Hydraulically Operated Valves, and ISTC-5152 for Solenoid Operated Valves. Table TPv-12-1 will also be used as general guidance to establish the Limiting Value(s) for power-operated valves. Establishment of Acceptable Ranges and Limiting Value(s) will be as follows:

Revision Date: 02/11/04 Page 149

IST ProgramPlan FloridaPowerand Light Company Turkey Point Nuclear PowerPlant Technical Position TPv-12 (Page 2 of 2)

• TRer is the reference value in seconds of a valve when it is know to be operating acceptably

• Reference values may be rounded off to the nearest tenth of a second. Acceptable Ranges may be rounded off to the nearest tenth of a second. Calculated IST Limiting Values may be rounded off to the nearest whole number. Standard rounding techniques are used when rounding (e.g., 10.45 rounds to 10.5, and 10.44 round to 10.4).

• The most conservative limiting value between the IST calculated limit (as determined from Table TPv-12-1), UFSAR limit, or Technical Specification limit should be used as the Maximum/Limiting stroke time. Any deviations from this criteria will be evaluated.

• When a valve or its control system has been replace, repaired, or has undergone maintenance] that could affect the valve's performance, a new reference value shall be determined or the previous value reconfirmed by an inservice test run before it is returned to service or immediately if not removed from service.

Table TPv-12-1 Valve Operator Reference Stroke Time Acceptable Range Limiting Stroke Time (Seconds)

Motor TRef > 10.0 0.85TRXf - 1.15TRef 1.25TRef Motor TRIO< 10.0 0.75TRCf - 1.25TRef 1.50TRef Pneumatic 2 TRe> 10.0 0.75TRef - 1.25TRef I.75TRie Pneumatic2 TRef* 10.0 0.5OTRef - 1.50XTRf 2.00TRef All (Optional) TRIO < 2.0 < 2.0 seconds > 2.0 seconds

'Adjustment of stem packing, limit switches, or control system valves, and removal of the bonnet, stem assembly, actuator, obturator, or control system components are examples of maintenance that could affect valve performance.

2 Pneumatic operators are air, hydraulic or solenoid operator types.

Page 150 Date: 02/11/04 Revision Date: 02111104 Page 150

ISTProgram Plan FloridaPower andLight Company Turkey Point Nuclear Power Plant Technical Position TPn-O1 (Page 1 of 2)

Containment Spray Pump Category B Pump Testing Purpose The purpose of this Technical Position is to establish the station position for performing the quarterly Containment Spray Pump test at conditions less than 20 % of Design Flow Rate.

Applicability This Technical Position is applicable to the following pumps Pump Number Class _ Group Function 3P214A 2 B Containment Spray 3P214B 2 B Containment Spray 4P214A 2 B Containment Spray 4P214B I2 JB Containment Spray Back2round The IST Program requires that each pump required to tested to the rules of Subsection ISTB, be categorized as either a Group A or Group B pump. ISTB-2000, SUPPLEMENTAL DEFINITIONS defines these groupings as follows:

group A pumps: pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations.

group B pumps: pumps in standby systems that are not operated routinely except for testing.

The Containment Spray pumps are categorized as Group B pumps since they are in a standby system and not operated routinely except for testing.

In accordance with ISTB-3300(e)(2);

Reference values shall be established within +/- 20% of pump design flow for the group A and group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow.

Position It is not practicable to test the Containment Spray pumps within +/- 20% of pump design flow during normal power operations. Turkey Point Nuclear Power Plant will perform the category B pump test at a reference flow point as high as practical.

Page 151 Revision 02/11/04 Revision Date: 02/111/04 Page 15 1

]STProgramPlan FloridaPower and Light Company Turkey Point Nuclear Power Plant Technical Position TPn-01 (Page 2 of 2)

Justification To test the containment spray pumps at +/- 20% of design pump flow conditions (1450 gpm) requires operating the pump in a range of 1160 - 1740 gpm. Since a downstream recirculation flow path capable of this flow range does not exist, injection of borated water from the Refueling Water Storage Tank into the containment is the only possible flow path to perform this test to satisfy these conditions.

This test is impracticable to perform during any mode of operation due to the extensive system alteration and amount of cleanup required.

Revision Date: 02/11/04 Page 152

1ST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear Power Plant Technical Position TPP-A (Page 1 of 2)

Position Turkey Point Nuclear Power Plant has categorized the pumps required to be included in the Inservice Testing Program as either Group A or B in accordance with the requirements of ISTB-1300/2000.

Group A pumps are pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations. The following pumps are categorized as Group A at Turkey Point Nuclear Power Plant:

Pump Number Class Group Function 3P201A 2 A Charging 3P201B 2 A Charging 3P201 C 2 A Charging 3P203A 2 A Boric Acid Transfer 3P203B 2 A Boric Acid Transfer 3P210A 2 A Residual Heat Removal 3P210B 2 A Residual Heat Removal 3P21 IA 3 A Component Cooling Water 3P21 lB 3 A Component Cooling Water 3P211C 3 A Component Cooling Water 3P9A 3 A Intake Cooling Water 3P9B 3 A Intake Cooling Water 3P9C 3 A Intake Cooling Water 4P201 A 2 A Charging 4P201B 2 A Charging 4P201C 2 A Charging 4P203A 2 A Boric Acid Transfer 4P203B 2 A Boric Acid Transfer 4P210A 2 A Residual Heat Removal 4P210B 2 A Residual Heat Removal 4P21 IA 3 A Component Cooling Water 4P21 lB 3 A Component Cooling Water 4P21 IC 3 A Component Cooling Water 4P9A 3 A Intake Cooling Water 4P9B 3 A Intake Cooling Water 4P9C 3 A Intake Cooling Water Page 153 Revision Date: 02/11/04 Date: 02111104 Page 153

IST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear Power Plant Technical Position TPp-A (Page 2 of 2)

Group B pumps are those pumps in standby systems that are not operated routinely except for testing. The following pumps are categorized as Group B at Turkey Point Nuclear Power Plant:

Pump Number Class Group Function P2A 3 B Auxiliary Feedwater P2B 3 B Auxiliary Feedwater P2C 3 B Auxiliary Feedwater 3P214A 2 B Containment Spray 3P214B 2 B Containment Spray 3P214C 2 B Containment Spray 3P215A 2 B Safety Injection 3P2155B 2 B Safety Injection 3P215C 2 B Safety Injection 4P214A 2 B Containment Spray 4P214B 2 B Containment Spray 4P214C 2 B Containment Spray 4P215A 2 B Safety Injection 4P215B 2 B Safety Injection 4P215C 2 B Safety Injection Group A Pump Tests - Group A tests are performed quarterly for each pump categorized as A.

The following inservice test parameters are measured for each Group A pump test:

• Speed (if pump is variable speed)

• Differential Pressure

• Discharge Pressure, (for positive displacement pumps)

• Flow Rate

• Vibration Group B Pump Tests - Group B tests are performed quarterly for each pump categorized as B.

The following inservice test parameters are measured for each Group B pump test.

• Speed (if pump is variable speed)

• Differential Pressure(')

• Flow RateMl)

(I) For positive displacement pumps, flow rate shall be measured or determined, for all other pumps, differential pressure or flow rate shall be measured or determined.

Comprehensive Pump Tests - Comprehensive pump tests are performed biennially for all pumps in the Inservice Testing Program. The following inservice test parameters are measured for each Comprehensive pump test:

• Speed (if pump is variable speed)

• Differential Pressure

• Discharge Pressure, (for positive displacement pumps)

• Flow Rate Revision Date: 02/11/04 Page 154

IST ProgramPlan FloridaPowver and Light Company Turkev Point Nuclear Power Plant

• Vibration The following instrument accuracy requirements apply to each test type:

Parameter Group A Group B Comprehensive Pressure +/- 2.0% +/-2.0% +/- 0.5%

Flow Rate +/- 2.0% +/- 2.0% +/- 2.0%

Speed +/- 2.0% +/- 2.0% +/- 2.0%

Vibration +/- 5.0% +/- 5.0% +/- 5.0%

Differential Pressure +/- 2.0% +/- 2.0% +/- 0.5%

Revision Date: 02/11/04 Page 155

1ST ProgramPlan FloridaPower andLight Company Turkey Point Nuclear PowerPlant ATTACHMENT 12 INSERVICE TESTING PUMP TABLE Page 156 Revision Date: 02/11/04 Date: 02111104 Page 156

Turkey Point Nuclear Plant IST Program Plan Pump Table Safety Pump Nominal P&ID Test Relief Tech.

PumpTag Class Pump Type Driver Speed P81D Coor. Category TestType Freq. Request Pos.

P2A 3 Centrifugal Turbine 5900 5610-M-3075-2 B3 Group B DPc Y2 Nb M3 Nc Y2 Ob M3 Oc Y2 Vc Y2 Pump Name: AFW Pump A P2B 3 Centriugal Turbine 5900 5610-M-3075-2 D3 Group B DPc Y2 Nb M3 Nc Y2 Qb M3 Qc Y2 Vc Y2 Pump Name: AFW Pump B P2C 3 Centrifugal Turbine 5900 5610-M-3075-2 F3 Group B DPc Y2 Nb M3 Nc Y2 Ob M3 Qc Y2 Vc Y2 Pump Name: AFW Pump C 3P201A 2 Positive Displacement Motor 1745 5613-M-3047-2 G5 GroupA Na M3 PR-05 PDa M3 PR-05 Qa M3 PR-O5 Va M3 PR-O5 Pump Name: 3A ChargIng Pump 3P201B 2 Positive Displacement Motor 1745 5613-M-3047-2 F5 Group A Na M3 PR-05 PDa M3 PR-05 Oa M3 PR-05 Va M3 PR-O5 Pump Name: 3B Charging Pump Revision Date: 2111/2004 Page 157

Turkey Point Nuclear Plant IST Program Plan Pump Table Safety Pump Nominal P&ID Test Relief Tech.

PumpTag Class Pump Type Driver Speed P&ID Coor. Category Test Type Freq. Request Pos.

3P201C 2 Positive Displacement Motor 1745 5613-M-3047-2 D5 GroupA Na M3 PR-05 PDa M3 PR-05 Oa M3 PR-05 Va M3 PR-05 Pump Name: 3C Charging Pump

\, 3P203A 2 Centrifugal Motor 1800 5610-M-3046-1 D6 Group A DPa M3 PR401,02 DPc Y2 PR-02 Qc Y2 Va M3 PR-01 Vc Y2 Pump Name: Boric Acid Transfer Pump 3A 3P203B 2 Centrifugal Motor 1800 5610-M-3046-1 E5 Group A DPa M3 PR-01,02 DPc Y2 PR-02 Cc Y2 Va M3 PR-01 Vc Y2 Pump Name: Boric Acid Transfer Pump 3B 3P210A 2 Centrifugal Motor N/A 5613-M-3050-1 C3 GroupA DPa CS PR-04 DPb M3 PR-04,06 DPc Y2 PR-04 Oa CS Cc Y2 Va CS Vc Y2 Pump Name: 3A Residual Heat Removal Pump 3P210B 2 Centrifugal Motor N/A 5613-M-3050-1 E3 Group A DPa CS PR-04 DPb M3 PR-04,06 DPc Y2 PR-04 Ga CS Qc Y2 Va CS Vc Y2 Pump Name: 3B Residual Heat Removal Pump Revision Date: 2/11/2004 Page 158

Turkey Point Nuclear Plant IST Program Plan Pump Table Safety Pump Nominal P&ID Test Relief Tech.

PumpTag Class Pump Type Driver Speed P&8D Coor. Category Test Type Freq. Request Pos.

3P211A 3 Centrifugal Motor 1800 5613-M-3030-1 F5 Group A DPa M3 PR-02,05 Qa M3 PR-05 Va M3 PR-05 Pump Name: Component Cooling Water Pump 3A 3P211B 3 Centrifugal Motor 1800 5613-M-3030-1 F3 Group A DPa M3 PR-02,05 Qa M3 PR-05 Va M3 PR-05 Pump Name: Component Cooling Water Pump 3B 3P211C 3 Centrifugal Motor 1800 5613-M-3030-1 F2 Group A DPa M3 PR-02,05 Ga M3 PR-05 Va M3 PR-05 Pump Name: Component Cooling Water Pump 3C 3P214A 2 Centrifugal Motor 1800 5613-M-3068-1 D3 Group B DPa M3 PR-03 Oa M3 PR-03 TPp-01 Va M3 PR-03 Pump Name: Containment Spray Pump 3A 3P214B 2 Centrifugal Motor 1800 5613-M-3068-1 G3 Group B DPa M3 PR-03 Oa M3 PR-03 TPp-01 Va M3 PR-03 Pump Name: Containment Spray Pump 3B 3P215A 2 Centrifugal Motor 1800 5613-M-3062-1 E3 Group B DPc Y2 PR.02 Qb M3 Oc Y2 Vc Y2 Pump Name: Safety Injection Pump 3A 3P215B 2 Centrifugal Motor 1800 5613-M-3062-1 G3 Group B DPc Y2 PR-02 Qb M3 Qc Y2 Vc Y2 Pump Name: Safety Injection Pump 3B Revision Date: 2111/2004 Page 159

Turkey Point Nuclear Plant IST Program Plan Pump Table Safety Pump Nominal P&ID Test Relief Tech.

Pump Tag Class Pump Type Driver Speed P&ID Coor. Category Test Type Freq. Request Pos.

3P9A 3 Vertical Motor 5613-M-3019-1 F2 Group A DPa M3 PR-O5 Oa M3 PR-O5 Va M3 PR-05 Pump Name: Intake Cooling Water Pump 3A 3P9B 3 Vertical Motor 5613-M-3019-1 D2 Group A DPa M3 PR-05 Qa M3 PR-05 Va M3 PR-05 Pump Name: Intake Cooling Water Pump 3B 3P9C 3 Vertical Motor 5613-M-3019-1 B2 Group A DPa M3 PR-05 Oa M3 PR-05 Va M3 PR-05 Pump Name: Intake Cooling Water Pump 3C 4P201A 2 Positive Displacement Motor 1745 5614-M-3047-2 G5 GroupA Na M3 PR-O5 PDa M3 PR-O5 Oa M3 PR-05 Va M3 PR-O5 Pump Name: 4A Charging Pump 4P201B 2 Positive Displacement Motor 1745 5614-M-3047-2 F5 Group A Na M3 PR-O5 PDa M3 PR-05 Qa M3 PR-O5 Va M3 PR-O5 Pump Name: 4B Charging Pump 4P201C 2 Positive Displacement Motor 1745 5614-M-3047-2 D5 Group A Na M3 PR-05 PDa M3 PR-05 Oa M3 PR-05 Va M3 PR-05 Pump Name: 4C Charging Pump 4P203A 2 Centrifugal Motor 1800 5610-M-3046-1 E5 Group A Dpa M3 PR-41,02 DPc Y2 PR-02 Oc Y2 Va M3 PR-01 Vc Y2 Pump Name: Boric Acid Transfer Pump 4A Revision Date: 2/11/2004 Page 160

Turkey Point Nudear Plant IST Program Plan Pump Table Safety Pump Nominal PSID Test Relief Tech.

Pump Tag Class Pump Type Driver Speed P&ID Coor. Category Test Type Freq. Request Pos.

4P203B 2 Centrifugal Motor 1800 5610-M-3046-1 F4 Group A Dpa M3 PR-01,02 DPc Y2 PR-02 Oc Y2 Va M3 PR-01 Vc Y2 Pump Name: Boric Acid Transfer Pump 4B 4P210A 2 Centrifugal Motor N/A 5614-M-3050-1 C3 GroupA DPa CS PR-04 DPb M3 PR-04,06 DPc Y2 PR-04 Oa CS Oc Y2 Va CS Vc Y2 Pump Name: 4A Residual Heat Removal Pump 4P210B 2 Centrifugal Motor NIA 5614-M-3050-1 E3 Group A DPa CS PR-04 DPb M3 PR-04,06 DPc Y2 PR-04 Oa CS Oc Y2 Va CS Vc Y2 Pump Name: 4B Residual Heat Removal Pump 4P211A 3 Centrifugal Motor 1800 5614-M-3030-1 F5 GroupA DPa M3 PR-02,05 Oa M3 PR-05 Va M3 PR-O5 Pump Name: Component Cooling Water Pump 4A 4P211B 3 Centrifugal Motor 1800 5614-M-3030-1 F3 Group A DPa M3 PR-02,05 Oa M3 PR-05 Va M3 PR-O5 Pump Name: Component Cooling Water Pump 4B 4P211C 3 Centrifugal Motor 1800 5614-M-3030-1 F2 Group A DPa M3 PR-02,05 Oa M3 PR-05 Va M3 PR-05 Pump Name: Component Cooling Water Pump 4C Revision Date: 2V11/2004 Page 161

Turkey Point Nuclear Plant IST Program Plan Pump Table Safety Pump Nominal P&ID Test Relief Tech.

Pump Tag Class Pump Type Driver Speed P&ID Coor. Category Test Type Freq. Request Pos.

4P214A 2 Centrifugal Motor 1800 5614-M-3068-1 C3 Group B DPa M3 PR-03 Oa M3 PR-03 TPp-01 Va M3 PR-03 Pump Name: Containment Spray Pump 4A 4P214B 2 Centrifugal Motor 1800 5614-M-3068-1 F3 Group B DPa M3 PR-03 Oa M3 PR-03 TPp-01 Va M3 PR-03 Pump Name: Containment Spray Pump 4B 4P215A 2 Centrifugal Motor 1800 5614M-3062-1 E3 Group B DPc Y2 PR-02 Ob M3 Oc Y2 Vc Y2 Pump Name: Safety Injection Pump 4A 4P215B 2 Centrifugal Motor 1800 5614-M-3062-1 G3 Group B DPc Y2 PR402 Ob M3 Oc Y2 Vc Y2 Pump Name: Safety Injection Pump 4B 4P9A 3 Vertical Motor 5614M-3019-1 F2 Group A DPa M3 PR-05 Oa M3 PR-05 Va M3 PR-05 Pump Name: Intake Cooling Water Pump 4A 4P9B 3 Vertical Motor 5614-M-3019-1 D2 Group A DPa M3 PR-05 Oa M3 PR-05 Va M3 PR-05 Pump Name: Intake Cooling Water Pump 4B 4P9C 3 Vertical Motor 5614-M-3019-1 B2 Group A DPa M3 PR&05 Oa M3 PR-05 Va M3 PR-05 Pump Name: Intake Cooling Water Pump 4C Revision Date: 2111/2004 Page 162

ISTProgramPlan FloridaPower and Light Company Turkey Point Nuclear Power Plant ATTACHMENT 13 INSERVICE TESTING VALVE TABLE Page 163 Revision Date: 02/11/04 Date: 02111104 Page 163

Turkey Point Nuclear Plant IST Program Plan Instrument Air/Service Air (013) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag I P81D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-40204 5610-M-3013-1 D6 2 A 2.0 GA MAN P LC C AT-01 App-J Valve Name: Serv Air to Cntmt Isol 3-40-205 5610-3013-1 C7 2 AIC 2.0 CK SA A SYS C AT-01 AppJ CC RR RJ-01 CO RR RJ-01 TPv-01 Valve Name: Service Air to Containment Check Valve 340.336 5613-W3013-7 B3 2 AIC 2.0 CK SA A SYS C AT-01 App-J CC RR VR-01 RJ-02 CO RR VR-41 RJ-02 TPv-01 Valve Name: Instrument Air to Containment Check Valve 3-40-340A 561343013-7 83 2 A/C 2.0 SCK SA A SYS C AT-01 App-J CC RR VR-01 RJ-03 CO RR VR-01 RJ-03 TPv-01 Valve Name: Instrument Air to Containment Check Valve HV-3-17 56104-3013-1 D7 2 A 2.0 GL MAN P LC C AT-01 App-J Valve Name: Hydrogen Recombiner Isolation Valve 440.204 5610-W3013-1 F6 2 A 2.0 GA MAN P LC C AT-01 App-J Valve Name: Serv Air to Cntmt Isol 440-205 5610.M-3013-1 F7 2 A 2.0 GA MAN P LC C AT-01 App-J Valve Name: Service Air to Containment Manual Iso Valve 440-336 5613-M3013-7 D3 2 AIC 2.0 CK SA A SYS C AT-01 App-J CC RR VR-01 RJ-02 CO RR VR41 RJ-02 TPv-01 Valve Name: Instrument Air to Containment Check Valve 440-340A 56134-3013-7 D3 2 ANC 2.0 CK SA A SYS C AT-01 App-J CC RR VR41 RJ-03 CO RR VR-01 RJ-03 TPv-01 Valve Name: Instrument Air to Containment Check Valve Revision Date: 2/1112004 Page 164

Turkey Point Nudear Plant IST Program Plan Condensate Storage (018) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-20-401 5613-M-3018-1 D3 3 C 8.0 CK SA A SYS 0 CCD CM TPv-01,02 COF CM TPv-02 Valve Name: Condensate Storage Tank Outlet Check Valve 4-20401 5614-M-3018-1 E6 3 C 8.0 CK SA A SYS 0 CCD CM TPv-01,02 COF CM TPv-02 Valve Name: Condensate Storage Tank Outlet Check Valve Page 165 Revision Date:

Revision Date: 2/11/2004 2111/2004 Page 165

Turkey Point Nuclear Plant IST Program Plan Intake Cooling Water (019) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&8D Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-50-311 5613-43019-1 F3 3 C 24.0 CK SA A SYS O/C CC M3 CO M3 Valve Name: ICS Pump 3A Disch Check Valve 3-50-315 561343019-1 B4 3 B 8.0 GA iMAN A C C BTC Y2 TPv-1I Valve Name: ICW/TPCW Basket Strainer Isolation Valve 3-50-321 561343019-1 D3 3 C 24.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: ICW Pump 3B Disch Check Valve 3-50-331 561343019-1 B3 3 C 24.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: ICW Pump 3C Disch Check Valve 3-50-335 5613-M-3019-1 F4 3 B 8.0 GA MAN A C C BTC Y2 TPv-11 Valve Name: ICW/TPCW Basket Strainer Isolation Valve POV-3-4882 5613-M-3019-1 B4 3 B 30.0 BTF AO A 0 C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: ICW/TPCW Isolation Valve to Hx 3A POV-3-4883 5613-M-3019-1 F4 3 B 30.0 BTF AO A 0 C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: ICWITPCW Isolation Valve to Hx 3B 4-50-311 561443019-1 F3 3 C 24.0 CK SA A SYS O/C CC M3 CO M3 Valve Name: ICW Pump 4A Disch Check Valve 4-50-315 5614-3019-1 F4 3 B 8.0 GA MAN A C C BTC Y2 TPv-11 Valve Name: ICWITPCW Basket Strainer Isolation Valve 4-50-321 5614M-3019-1 D3 3 C 24.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: ICW Pump 4B Disch Check Valve Revision Date: 2/11/2004 Page 166

Turkey Point Nuclear Plant IST Program Plan Intake Cooling Water (019) Valve Table P81D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&8D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

4.50-331 5614-M-3019-1 B3 3 C 24.0 CK SA A SYS O/C CC M3 CO M3 Valve Name: ICW Pump 4C Disch Check Valve 4.50-335 56144-30191 C4 3 B 8.0 GA MAN A C C BTC Y2 TPv-11 Valve Name: ICW/TPCW Basket Strainer Isolation Valve POV-4-4882 56144-3019-1 F4 3 B 30.0 BTF AO A 0 C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: ICWITPCW Isolation Valve to Hx 4A POV4-4883 561443019-1 B4 3 B 30.0 BTF AO A 0 C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: ICWITPCW Isolation Valve to Hx 4B Revision Date: 2/11/2004 Page 167

Turkey Point Nuclear Plant Primary Water Makeup (020) IST Program Plan Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-10-567 56134M-3020-2 C5 2 A/C 2.0 CK SA P C C AT-01 AppJ VR-01 TPv-47 Valve Name: Primary Water to Containment Line Check Valve 3-10-582 5613-M-3020-2 D6 2 A 2.0 GA MAN P LC C AT-01 App-J Valve Name: Primary Water to Containment Line Isolation Valve K - RV-3-302 5613-43020-2 D6 2 ANC 0.75 RV SA A C OIC AT-C1 App-J RT Y10 Valve Name: Primary Water to Containment Line Relief Valve 4-10-567 561443020-2 D5 2 AIC 2.0 CK SA P C C AT-C1 App-J VR-C1 TPv-47 Valve Name: Primary Water to Containment Line Check Valve 4-10-582 5614-M-3020-2 C6 2 A 2.0 GA MAN P LC C AT-01 App-J Valve Name: Primary Water to Containment Line Isolation Valve RV4-302 5614-M-3020-2 D6 2 ANC 0.75 RV SA A C O/C AT-01 App-J RT Y10 Valve Name: Primary Water to Containment Line Relief Valve Revision Date: 2V11/2004 Page 168

Turkey Point Nuclear Plant IST Program Plan Emergency Diesel Generator (022) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

3-70.274A 5613-M-3022-1 C2 SR C 1.5 CK SA A SYS C CC M3 CO OP TPv-01 Valve Name: 3A EDG Air Receiver Tanks C & D Inlet Check Valves 3-70-2748 56134-3022-2 C2 SR C 1.5 CK SA A SYS C CC M3 CO OP TPv-01 Valve Name: 3B EDG Air Receiver Tanks C & D Inlet Check Valves 3-70.276A 5613-M-3022-1 D2 SR C 1.5 CK SA A SYS C CC M3 CO OP TPv.01 Valve Name: 3A EDG Air Receiver Tanks A & B Inlet Check Valves 3-70-276B 5613-M-3022-2 D2 SR C 1.5 CK SA A SYS C CC M3 CO OP TPv-01 Valve Name: 3B EDG Air Receiver Tanks A & B Inlet Check Valves RV-3-210A 5613-M-3022-1 B4 SR C RV SA A C O/C RT Y10 Valve Name: 3A EDG Air Receiver Tank A Relief Valve RV-3-210B 5613-M-3022-2 B4 SR C RV SA A C O/C RT Y10 Valve Name: 3B EDG Air Receiver Tank A Relief Valve RV-3-211A 5613-M-3022-1 B4 SR C RV SA A C O/C RT Y10 Valve Name: 3A EDG Air Receiver Tank B Relief Valve RV43-211B 56134-3022-2 B4 SR C RV SA A C O/C RT Y10 Valve Name: 3B EDG Air Receiver Tank B Relief Valve RV-3-212A 5613-M3022-1 83 SR C RV SA A C O/C RT Y1O Valve Name: 3A EDG Air Receiver Tank C Relief Valve RV-3-212B 5613-3022-2 B3 SR C RV SA A C OIC RT Y10 Valve Name: 3B EDG Air Receiver Tank C Relief Valve RV-3-213A 5613M3022-1 B3 SR C RV SA A C O/C RT Y10 Valve Name: 3A EDG Air Receiver Tank D Relief Valve RV-3-213B 5613-M-3022-2 B3 SR C RV SA A C O/C RT Y10 Valve Name: 3B EDG Air Receiver Tank D Relief Valve Revision Date: 2/1112004 Page 169

Turkey Point Nudear Plant IST Program Plan Emergency Diesel Generator (022) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV-3-214A 5613-M-3022-5 B6 SR C RV SA A C O/C RT Y10 Valve Name: 3A EDG Main Lube Oil Pump Disch Relief Valve RV-3-214B 5613M-3022-6 B6 SR C RV SA A C 01C RT Y10 Valve Name: 3B EDG Main Lube Oil Pump Disch Relief Valve K' 4.70.530A 56144M-3022-1 D2 SR C 1.5 CK SA A SYS C CC M3 CO OP TPv41 Valve Name: 4A EDG Air Receiver Tanks A & B Inlet Check Valves 4-70.530B 5614-M-3022-2 D2 SR C 1.5 CK SA A SYS C CC M3 CO OP TPVO01 Valve Name: 4B EDG Air Receiver Tanks A & B Inlet Check Valves 4-70.531A 5614-M3022-1 D3 SR C 1.5 CK SA A SYS C CC M3 CO OP TPv-01 Valve Name: 4A EDG Air Receiver Tanks C & D Inlet Check Valves 4.70.531B 5614-M-3022-2 D3 SR C 1.5 CK SA A SYS C CC M3 CO OP TPv-01 Valve Name: 4B EDG Air Receiver Tanks C & D Inlet Check Valves RV-4*1451A 5614-M-3022-5 E4 SR C 1.0 RV SA A C O/C RT Y10 Valve Name: 4A EDG Cooling Water Expansion Tank Relief Valve RV4.1451B 5614.M-3022-5 E4 SR C 1.0 RV SA A C O/C RT Y10 Valve Name: 4A EDG Cooling Water Expansion Tank Relief Valve RV-4.1452A 5614M-3022-5 B5 SR C RV SA A C OIC RT Y10 Valve Name: 4A EDG Main Lube Oil Pump Disch Relief Valve RV4-1452B 5614M-3022-6 B6 SR C RV SA A C OIC RT Y10 Valve Name: 4B EDG Main Lube Oil Pump Disch Relief Valve RV-4.1456A 5614-M-3022-1 B2 SR C RV SA A C 0OC RT Y10 Valve Name: 4A EDG Air Receiver Tank A Relief Valve RV-4.1456B 5614-M-3022-2 B2 SR C RV SA A C O/C RT Y10 Valve Name: 4B EDG Air Receiver Tank A Relief Valve Revision Date: 2/11/2004 Page 170

Turkey Point Nuclear Plant IST Program Plan Emergency Diesel Generator (022) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

ValveTag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV-4-1457A 5614-M-3022-1 B3 SR C RV SA A C OIC RT Y10 Valve Name: 4A EDG Air Receiver Tank B Relief Valve RV-4.1457B 561443022-2 B3 SR C RV SA A C OIC RT Y10 Valve Name: 4B EDG Air Receiver Tank B Relief Valve y,' RV-4*1458A 5614-43022-1 84 SR C RV SA A C O/C RT Y10 Valve Name: 4A EDG Air Receiver Tank C Relief Valve RV4-1458B 561443022-2 84 SR C RV SA A C O/C RT YIO Valve Name: 4B EDG Air Receiver Tank C Relief Valve RV-4.1459A 56144-3022-1 B4 SR C RV SA A C O/C RT Y1O Valve Name: 4A EDG Air Receiver Tank D Relief Valve RV4-1459B 56144-3022-2 B4 SR C RV SA A C O/C RT Y1O Valve Name: 4B EDG Air Receiver Tank D Relief Valve Revision Date: 2/11/2004 Page 171

Turkey Point Nuclear Plant IST Program Plan Component Cooling Water (030) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-702A 5613M-3030-1 E4 3 C 16.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: CCW Pump 3A Discharge Check Valve 3-7028 5613-M3030-1 E3 3 C -16.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: CCW Pump 38 Discharge Check Valve 3-702C 56134-3030-1 E2 3 C 16.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: CCW Pump 3C Discharge Check Valve 3-721A 5613-M3030-5 E6 3 C 1.5 CK SA A SYS C CC RR RJ-13 CO M3 TPv-01 Valve Name: CCW Supply to Thermal Barrier Cooler Valve 3-721B 5613-M-3030-5 B6 3 C 1.5 CK SA A SYS C CC RR RJ-13 CO M3 TPv-01 Valve Name: CCW Supply to Thermal Barrier Cooler Valve 3-721C 5613-M-3030-5 C6 3 C 1.5 CK SA A SYS C CC RR RJ-13 CO M3 TPv-01 Valve Name: CCW Supply to Thermal Barrier Cooler Valve 3-738 5613-M-3030-5 D3 2 C 3.0 CK SA A SYS C CC CS CSJ-09 CO M3 TPv-01 Valve Name: CCW Check Valve to Excess Letdown Heat Exchanger CV-3-2903 5613-M-3030-4 D3 2 B 10.0 BTF AO P 0 0 PIT Y2 Valve Name: 3B Emergency Containment Cooler Inlet CV-3-2904 5613-M-3030-4 C3 2 B 10.0 BTF AO P 0 0 PIT Y2 Valve Name: 3C Emergency Containment Cooler Inlet CV-342905 5613-M-3030-4 B3 2 B 10.0 BTF AO P 0 0 PIT Y2 Valve Name: 3A Emergency Containment Cooler Inlet CV-3-2906 5613-M-3030-4 G3 2 B 10.0 BTF AO A C 0 BTO M3 FO M3 TPv.04 PIT Y2 Valve Name: 3B Emergency Containment Cooler Outlet Revision Date: 2/11/2004 Page 172

Turkey Point Nuclear Plant IST Program Plan Component Cooling Water (030) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV-3-2907 5613-MW30304 F3 2 B 10.0 BTF AO A C 0 BTO M3 FO M3 TPv-04 PIT Y2 Valve Name: 3C Emergency Containment Cooler Outlet CV-3-2908 5613-M-3030-4 E3 2 B 10.0 BTF AO A C 0 BTO M3 FO M3 TPv-04 PIT Y2 Valve Name: 3A Emergency Containment Cooler Outlet CV-3-739 5613-3030-5 C2 2 B 3.0 GL AO A 0 C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Excess Letdown Heat Exchanger Outlet MOV.3-1417 5613-M3030-5 B2 2 B 10.0 GA MO A 0 C BTC CS CSJ-10 PIT Y2 Valve Name: CCW to Normal Containment Cooler MOV.3.1418 561343030-5 F2 2 B 10.0 GA MO A 0 C BTC CS CSJ-10 PIT Y2 Valve Name: CCW to Normal Containment Cooler MOV-3-626 561343030-5 H3 2 B 3.0 GA MO A 0 C BTC CS CSi-11 PIT Y2 Valve Name: RCP Seal Cooling Water Outlet MOV.3-716A 5613-3030-5 E2 3 B 6.0 GA MO A 0 C BTC CS CSJ-11 PIT Y2 Valve Name: RCP CCW Inlet MOV-3-716B 5613-M-3030-5 E2 2 B 6.0 GA MO A 0 C BTC CS CSJ-11 PIT Y2 Valve Name: RCP CCW Inlet MOV-3-730 561343030-5 G3 2 B 6.0 GA MO A 0 C BTC CS CSJ-11 PIT Y2 Valve Name: RCP Bearing CCW Outlet Revision Date: 2/11/2004 Page 173

Turkey Point Nuclear Plant IST Program Plan Component Cooling Water (030) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

MOV.3-749A 5613-M-3030-2 F7 3 B 16.0 GA MO A C 0 BTO M3 TPv-09 PIT Y2 Valve Name: 3A RHR Heat Exchanger Component Cooling Outlet MOV.3-749B 56134-3030-2 F7 3 B 16.0 GA MO A C 0 BTO M3 TPv-09 PIT Y2 Valve Name: 3B RHR Heat Exchanger Component Cooling Outlet RV-3-1423 5613-M-30304 D5 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: ECC Relief Valve RV-3-1424 5613-M-3030-4 C5 3 C 0.75 RV SA A C OIC RT Y1O Valve Name: ECC Relief Valve RV-3-1425 5613-M-3030-4 B5 3 C 0.75 RV SA A C 0/C RT Y10 Valve Name: ECC Relief Valve RV-3-1426 5613-3030-5 E4 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: NCC Thermal Relief Valve RV-3-1427 5613-3030-5 E4 3 C 0.75 RV SA A C OC RT Y10 Valve Name: NCC Thermal Relief Valve RV-3-1428 5613-M-3030-5 C4 3 C 0.75 RV SA A C O/C RT Y10 Valve Name: NCC Thermal Relief Valve RV-3-1429 5613-M-3030-5 A4 3 C 0.75 RV SA A C O/C RT Y10 Valve Name: NCC Thermal Relief Valve RV-3-1430 5613-M-3030-5 W4 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: Rod Drive Cooler Thermal Relief Valve RV-3.1431 5613-M-3030-5 B4 3 C 0.75 RV SA A C O/C RT YIO Valve Name: Rod Drive Cooler Thermal Relief Valve RV-3-707 5613-M-3030-1 C7 3 C 3.0 RV SA A C O/C RT Y10 Valve Name: Surge Tank Relief Valve RV-3-715 5613-M-3030-5 C3 3 C 3.0 RV SA A C OIC RT Y1O Valve Name: Excess Letdown Heat Exchanger Relief Valve Revislon Date: 2/1112004 Page 174

Turkey Point Nuclear Plant IST Program Plan Component Cooling Water (030) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV-3-722A 5613-M3030-5 E7 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: RCP Thermal Barrier Cooler Thermal Relief Valve RV-3-722B 5613-M-3030-5 87 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: RCP Thermal Barrier Cooler Thermal Relief Valve K- RV.3.722C 5613-3030.5 C7 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: RCP Thermal Barrier Cooler Thermal Relief Valve RV-3-729 5613-M-3030-5 F7 3 C 3.0 RV SA A C OIC RT Y10 Valve Name: RCP Oil Coolers Relief Valve RV-3-747A 5613-3030-2 E7 3 C 1.0 RV SA A C OIC RT Y10 Valve Name: RHR Hx Thermal Relief Valve RV-3-7478 56134-3030-2 E8 3 C 1.0 RV SA A C OIC RT YIO Valve Name: RHR Hx Thermal Relief Valve 4-702A 5614-M-3030-1 E4 3 C 16.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: CCW Pump 4A Discharge Check Valve 4-702B 5614A4-3030-1 E3 3 C 16.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: CCW Pump 4B Discharge Check Valve 4-702C 56144-3030-1 E2 3 C 16.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: CCW Pump 4C Discharge Check Valve 4-721A 5614-M3030-4 E6 3 C 1.5 CK SA A SYS C CC RR RJ-13 CO M3 TPv-01 Valve Name: CCW Supply to Thermal Barrier Cooler Valve 4-721B 56144M-3030-4 B6 3 C 1.5 CK SA A SYS C CC RR RJ-13 CO M3 TPv-01 Valve Name: CCW Supply to Thermal Barrier Cooler Valve 4-721C 5614-M-3030-4 D6 3 C 1.5 CK SA A SYS C CC RR RJ-13 CO M3 TPv401 Valve Name: CCW Supply to Thermal Barrier Cooler Valve Revision Date: 2/11/2004 Page 175

Turkey Point Nuclear Plant IST Program Plan Component Cooling Water (030) Valve Table P8iD Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

4-738 5614-M-3030-4 D3 2 C 3.0 CK SA A SYS C CC CS CSJ-09 CO M3 TPv-01 Valve Name: CCW Check Valve to Excess Letdown Heat Exchanger CV4-2903 5614-M-3030-3 03 2 B 10.0 BTF AO P 0 0 PIT Y2 Valve Name: 4B Emergency Containment Cooler Inlet CV4-2904 5614-M-3030-3 C3 2 B 10.0 BTF AO P 0 0 PIT Y2 Valve Name: 4A Emergency Containment Cooler Inlet CV-4-2905 5614-M030-3 B3 2 B 10.0 BTF AO P 0 0 PIT Y2 Valve Name: 4C Emergency Containment Cooler Inlet CV4-2906 5614-M-3030-3 G3 2 B 10.0 BTF AO A C 0 BTO M3 FO M3 TPv-04 PIT Y2 Valve Name: 4B Emergency Containment Cooler Outlet CV4-2907 561443030-3 F3 2 B 10.0 BTF AO A C 0 BTO M3 FO M3 TPv-04 PIT Y2 Valve Name: 4A Emergency Containment Cooler Outlet CV4-2908 5614-M-3030-3 E3 2 B 10.0 BTF AO A C 0 BTO M3 FO M3 TPv-04 PIT Y2 Valve Name: 4C Emergency Containment Cooler Outlet CV4-739 5614-M-3030-4 C2 2 B 3.0 GL AO A 0 C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Excess Letdown Heat Exchanger Outlet MOV.4.1417 5614-M-3030-4 B2 2 B 10.0 GA MO A 0 C BTC CS CSJ-10 PIT Y2 Valve Name: CCW to Normal Containment Cooler MOV4.1418 561443030-4 F2 2 B 10.0 GA MO A 0 C BTC CS CSJ-10 PIT Y2 Valve Name: CCW to Normal Containment Cooler Revision Date: 2/11/2004 Page 176

Turkey Point Nuclear Plant IST Program Plan Component Cooling Water (030) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

ValveTag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

MOV-626 5614-M-3030-4 H3 2 B 3.0 GA MO A 0 C BTC CS CSJ-11 PIT Y2 Valve Name: RCP Seal Cooling Water Outlet MOV4-716A 5614-M-3030-4 E2 3 B 6.0 GA MO A 0 C BTC CS CSJ-11 PIT Y2 Valve Name: RCP CCW Inlet MOV4-716B 5614-M-3030D4 E2 2 B 6.0 GA MO A 0 C BTC CS CSJ-11 PIT Y2 Valve Name: RCP CCW Inlet MOV4-730 5614M-3030-4 G3 2 B 6.0 GA MO A 0 C BTC CS CSJ-11 PIT Y2 Valve Name: RCP Bearing CCW Outlet MOV4-749A 561443030-2 F6 3 B 16.0 GA MO A C 0 BTO M3 TPv-09 PIT Y2 Valve Name: 3A RHR Heat Exchanger Component Cooling Outlet MOV4-749B 5614M-3030-2 F7 3 B 16.0 GA MO A C 0 BTO M3 TPv49 PIT Y2 Valve Name: 3B RHR Heat Exchanger Component Cooling Outlet RV4-1423 5614-M43030-3 D5 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: ECC Relief Valve RV4-1424 5614-M3030-3 C5 3 C 0.75 RV SA A C O/C RT Y10 Valve Name: ECC Relief Valve RV4.1425 5614-M-3030-3 B5 3 C 0.75 RV SA A C O/C RT Y10 Valve Name: ECC Relief Valve RV4.1426 5614-M-3030-4 E4 3 C 0.75 RV SA A C O/C RT Y10 Valve Name: NCC Thermal Relief Valve RV4.1427 561443030-4 D4 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: NCC Thermal Relief Valve RV4.1428 561443030-4 B4 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: NCC Thermal Relief Valve Revision Date: 2/11/2004 Page 177

Turkey Point Nuclear Plant IST Program Plan Component Cooling Water (030) Valve Table P&ID Safety Valve AcL Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV-4-1429 561443030-4 A4 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: NCC Thermal Relief Valve RV.4.1430 5614-M-3030-4 D4 3 C 0.75 RV SA A C O/C RT Y10 Valve Name: Rod Drive Cooler Thermal Relief Valve K-' RV.4-1431 5614-43030-4 C4 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: Rod Drive Cooler Thermal Relief Valve RV-4-707 5614-M-3030-1 C7 3 C 3.0 RV SA A C OIC RT Y10 Valve Name: Surge Tank Relief Valve RV4-715 561440-304 C3 3 C 3.0 RV SA A C O/C RT Y10 Valve Name: Excess Letdown Heat Exchanger Relief Valve RV4-722A 5614-M-3030-4 E7 3 C 0.75 RV SA A C 0/C RT Y10 Valve Name: RCP Thermal Barrier Cooler Thermal Relief Valve RV.4-722B 5614M4030-4 B7 3 C 0.75 RV SA A C O/C RT YIO Valve Name: RCP Thermal Barrier Cooler Thermal Relief Valve RV4-722C 5614-3030-4 C7 3 C 0.75 RV SA A C OIC RT Y10 Valve Name: RCP Thermal Barrier Cooler Thermal Relief Valve RV4-729 5614-M-3030-4 F7 3 C 3.0 RV SA A C OIC RT Y10 Valve Name: RCP Oil Coolers Relief Valve RV4-747A 5614M4030-2 E6 3 C 1.0 RV SA A C O/C RT Y10 Valve Name: RHR Hx Thermal Relief Valve RV4-747B 561443030-2 E8 3 C 1.0 RV SA A C OIC RT Y10 Valve Name: RHR Hx Thermal Relief Valve Revision Date: 2/11/2004 Page 178

Turkey Point Nuclear Plant IST Program Plan Sampling (036) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV-3.951 5613-M-3036-1 A2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv.04 PIT Y2 Valve Name: Pressurizer Steam Space Sample Isolation Valve K.> CV.3-953 5613-M-3036-1 B2 2 A 0.375 GL AO A C C AT-1 App-J BTC M3 FC M3 TPv044 PIT Y2 Valve Name: Pressurizer Liquid Space Sample Isolation Valve CV-3.955C 5613-M3036-1 D2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPvO4 PIT Y2 Valve Name: 3A Accumulator Sample Valve CV-3-955D 5613-M-3036-1 E2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 3B Accumulator Sample Valve CV-3-955E 5613-M3036-1 E2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-G4 PIT Y2 Valve Name: 3C Accumulator Sample Valve CV-3-956A 5613-M-3036-1 A3 2 A 0.375 GL AO A C C AT-41 App-J BTC M3 FC M3 TPv44 PIT Y2 Valve Name: Pressurizer Steam Space Sample Isolation Valve Revision Date: 2/11/2004 Page 179

Turkey Point Nuclear Plant IST Program Plan Sampling (036) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

CV-3-956B 5613-M-3036-1 B3 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Pressurizer Liquid Space Sample Isolation Valve K. CV-3-956D 5613M3036-1 E3 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Accumulator Sample Isolation Valve RV-3-300 5613-M-3036-1 i3 2 A/C 0.375 RV SA A C O/C AT-01 App-J RT Y10 Valve Name: Pressurizer Liquid Space Sample Line Relief Valve RV-3-301 561343036-1 D3 2 A/C 0.75 RV SA A C O/C AT-01 App-J RT Y10 Valve Name: Accumulator Sample Line Relief Valve SV-3-6427A 5613M3036-1 C2 2 A 0.375 GL SO A C C AT-01 App-J BTC M3 FC M3 TPv.04 PIT App-J VR-02 Valve Name: RCS Loop A Hot Leg Sample Isolation Valve SV-3-64278 5613-M-3036-1 C2 2 A 0.375 GL SO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT App-J VR-02 Valve Name: RCS Loop B Hot Leg Sample Isolation Valve SV-3-6428 5613-M-3036-1 C3 2 A 0.375 GL SO A C C AT-01 App4 BTC M3 FC M3 TPv.04 PIT AppJ VR-02 Valve Name: RCS Hot Leg Sample Isolation Valve Revision Date: 2/11/2004 Page 180

Turkey Point Nuclear Plant IST Program Plan Sampling (036) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV4-951 5614-U3036-1 A2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Pressurizer Steam Space Sample Isolation Valve CV4.953 5614-M-3036-1 B2 2 A 0.375 GL AO A C C AT-01 AppO BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Pressurizer Liquid Space Sample Isolation Valve CV-4.955C 5614-U3037-1 D2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 4A Accumulator Sample Valve CV4-955D 5614.M-3036-1 E2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 4B Accumulator Sample Valve CV-4-955E 5614-M-3036-1 E2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 4C Accumulator Sample Valve CV-4-956A 5614-M3036-1 A3 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Pressurizer Steam Space Sample Isolation Valve Revision Date: 2/1112004 Page 181

Turkey Point Nuclear Plant IST Program Plan Sampling (036) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV4-956B 5614-M-3036-1 B3 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv.04 PIT Y2 Valve Name: Pressurizer Liquid Space Sample Isolation Valve KJ CV4-956D 5614-M-3036-1 E3 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv4 PIT Y2 Valve Name: Accumulator Sample Isolation Valve RV4-300 56144-3036-1 B3 2 A/C 0.375 RV SA A C OIC AT-01 App-J RT Y10 Valve Name: Pressurizer Liquid Space Sample Line Relief Valve RV4-301 5614-M-3036-1 D3 2 A/C 0.75 RV SA A C O/C AT-01 App-J RT Y10 Valve Name: Accumulator Sample Line Relief Valve SV4-6427A 5614-M-3036-i C2 2 A 0.375 GL SO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT App-J VR-02 Valve Name: RCS Loop A Hot Leg Sample Isolation Valve SV4-6427B 5614-M-3036-1 C2 2 A 0.375 GL SO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT App-J VR-02 Valve Name: RCS Loop B Hot Leg Sample Isolation Valve SV-4-6428 5614-M-3036-1 C3 2 A 0.375 GL SO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT App-J VR402 Valve Name: RCS Hot Leg Sample Isolation Valve Revision Date: 2/11/2004 Page 182

Turkey Point Nudear Plant IST Program Plan Reactor Coolant System (041 ) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV-3-516 5613-M-3041-2 G2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Cont Iso VIv PRT to GA CV.3-519A 561343041-3 A8 2 A 3.00 DIA AO A C C AT-1 AppP BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: PW Supply to Containment CV-3-519B 5613-M-3041-3 A2 2 A 3.00 DIA AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: PRT Makeup Valve CV.3-522A 561343041-3 B7 2 A 0.75 DIA AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 3A RCP Stand Pipe Fill CV-3-522B 5613-M-3041-3 B7 2 A 0.75 DIA AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 3B RCP Stand Pipe Fill CV-3-522C 5613M43041-3 C7 2 A 0.75 DIA AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 3C RCP Stand Pipe Fill MOV-3-535 5613-M-3041-2 B6 1 B 3.00 GA MO A 0 OIC BTC M3 TPv-09 PIT Y2 Valve Name: Pressurizer PORV Stop Valve Revision Date: 2/11/2004 Page 183

Turkey Point Nuclear Plant IST Program Plan Reactor Coolant System (041) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

MOV-3-536 5613-W3041-2 C6 1 B 3.00 GA MO A 0 OIC BTC M3 TPv-09 PIT Y2 Valve Name: Pressurizer PORV Stop Valve PCV-3-455C 5613-M-3041-2 C7 1 B 3.00 GL AO A C 0OC BTC CS CSJ-23 BtO CS CSJ-23 FC CS CSJ-23 TPv-04 PIT Y2 Valve Name: Pressurizer PORV PCV-3-456 5613-MW3041-2 B7 1 B 3.00 GL AO A C 0/C BTC CS CSJ-23 BTO CS CSJ-23 FC CS CSJ-23 TPv.04 PIT Y2 Valve Name: Pressurizer PORV RV-3-551A 5613-M3041-2 B5 1 C 4.00 RV SA A C OIC RT Y5 Valve Name: Pressurizer Safety Valve A RV-3-551B 5613-M-3041-2 B4 1 C 4.00 RV SA A C O/C RT Y5 Valve Name: Pressurizer Safety Valve B RV-3-551C 5613-M-3041-2 B3 1 C 4.00 RV SA A C 0/C RT Y5 Valve Name: Pressurizer Safety Valve C RV-3-6587 5613430414 C4 SR C 0.50 RV SA A C O/C RT Y10 Valve Name: N2 Supply Relief RV-3-6588 5613-M-30414 F4 SR C 0.50 RV SA A C OIC RT Y10 Valve Name: N2 Supply Relief SV-34318A 5613-M-3041-2 D7 2 B 1.00 GA SO A C O/C- BTO CS CSJ-24 TPv-09 PIT Y2 Valve Name: Reactor Vessel Head Vent SV-3-6318B 5613-M-3041-2 E7 2 B 1.00 GA SO A C O/C BTO CS CSJ-24 TPv49 PIT Y2 Valve Name: Reactor Vessel Head Vent Revision Date: 2/11/2004 Page 184

Turkey Point Nuclear Plant IST Program Plan Reactor Coolant System (041) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

SV-3-6385 5613-M3041-2 G2 2 A 0.375 GA SO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT App-J VR402 Valve Name: PRT to Gas Analyzer SV.3-66111 5613-M-3041-2 F7 2 B 1.00 GA SO A C 0 BTO CS CSJ-24 TPv-09 FO CS CSJ-24 TPv-04 PIT Y2 Valve Name: RCS Vent to Atmosphere SV-34612 5613-M-3041-2 F6 2 B 1.00 DAM SO A C 0 BTO CS CSJ-24 TPv09 FO CS CSJ-24 TPv-04 PIT Y2 Valve Name: Vent to PRT CV-4-516 5614-M-3041-2 G2 2 A 0.375 GL AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Cont Iso Vlv PRT to Gar CV-4-519A 56144-3041-3 A8 2 A 3.00 DIA AO A C C AT-01 App-J BTC M3 FC TPv-04 PIT Y2 Valve Name: PW Supply to Containment K> CV-4-519B 5614-M-3041-3 A2 2 A 3.00 DIA AO A C C AT01 App-J BTC M3 FC M3 TPv044 PIT Y2 Valve Name: PRT Makeup Valve CV-4-522A 5614-M3041-3 87 2 A 0.75 DIA AO A C C AT-41 App-J BTC M3 FC M3 TPv.04 PIT Y2 Valve Name: 4A RCP Stand Pipe Fill Revision Date: 2/11/2004 Page 185

Turkey Point Nuclear Plant IST Program Plan Reactor Coolant System (041 ) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

l CV4-4522B 5614-M-3041-3 67 2 A 0.75 DIA AO A C C AT-01 App-4 BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 4B RCP Stand Pipe Fill K..-; CV.4-522C 5614-M-3041-3 C7 2 A 0.75 DIA AO A C C AT-1 App-J BTC M3 FC M3 TPv044 PIT Y2 Vaive Name: 4C RCP Stand Pipe Fill MOV.4-535 5614-M-3041-2 B6 1 B 3.00 GA MO A 0 O/C BTC M3 TPv-09 PIT Y2 Valve Name: Pressurizer PORV Stop Valve MOV4-536 5613-M-3041-2 C6 1 B 3.00 GA MO A 0 OIC BTC M3 TPv-09 PIT Y2 Valve Name: Pressurizer PORV Stop Valve PCV-4455C 5614-M-3041-2 C7 1 B 3.00 GL AO A C OC BTC CS CSJ-23 BTO CS CSJ-23 FC CS CSJ-23 TPv-04 PIT Y2 Valve Name: Pressurizer PORV PCV4456 5614-M-3041-2 B7 1 B 3.00 GL AO A C OIC BTC CS CSJ-23 BTO CS CSJ-23 FC CS CSJ-23 TPv-04 PIT Y2 Valve Name: Pressurizer PORV RV4-551A 561443041-2 B5 1 C 4.00 RV SA A C OC RT Y5 Valve Name: Pressurizer Safety Valve A RV4-551B 5614-M-3041-2 B4 1 C 4.00 RV SA A C O/C RT Y5 Valve Name: Pressurizer Safety Valve B RV-4-551C 5614.M-3041-2 B3 1 C 4.00 RV SA A C OC RT Y5 Valve Name: Pressurizer Safety Valve C Revision Date: 211112004 Page 186

Turkey Point Nuclear Plant IST Program Plan Reactor Coolant System (041 ) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

ValveTag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV4-6587 5614430414 C4 SR C 0.50 RV SA A C O/C RT Y10 Valve Name: N2 Supply Relief RV4-6588 5614M-30414 F4 SR C 0.50 RV SA A C O/C RT Y10 Valve Name: N2 Supply Relief K SV4-6318A 561443041-2 D7 2 B 1.00 GA SO A C O/C BTO CS CSJ-24 TPv-09 PIT Y2 Valve Name: Reactor Vessel Head Vent SV446318B 561443041-2 E7 2 B 1.00 GA SO A C OIC BTO CS CSJ-24 TPv-09 PIT Y2 Valve Name: Reactor Vessel Head Vent SV446385 5614M-3041-2 G2 2 A 0.375 GA SO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT App-J VR-02 Valve Name: PRT to Gas Analyzer SV644611 5613-MW3041-2 F7 2 8 1.00 GA SO A C 0 BTO CS CSJ-24 TPv-09 FO CS CSJ-24 TPv-04 PIT Y2 Valve Name: RCS Vent to Atmosphere SV4-6612 5613-M041-2 F6 2 B 1.00 DAM SO A C 0 BTO CS CSJ-24 TPv.09 FO CS CSJ-24 TPv-04 PIT Y2 Valve Name: Vent to PRT Revision Date: 2/11/2004 Page 187

Turkey Point Nuclear Plant IST Program Plan Boric Acid (046) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&SD Coor. Class CaL Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-397A 5610-M3046-1 D7 2 C 2.0 CK SA A SYS OIC CC RR RJ-04 CO RR RJ-04 Valve Name: Boric Acid Pump Discharge Check Valve 3-397B 5610-M-3046-1 E6 2 C 2.0 CK SA A SYS O/C CC RR RJ-04 CO RR RJ-04 Valve Name: Boric Acid Pump Discharge Check Valve HCV.105 5610M-3046-1 C5 2 B 2.0 GL AO A C C BTC M3 FC M3 TPv-04 Valve Name: Boric Acid Storage Tank Recirculatlon Control Valv HCV-110 5610-M-3046-1 C7 2 B 2.0 GL AO A C C BTC M3 FC M3 TPv04 Valve Name: Boric Acid Storage Tank Recirculation Control Valv 4-397C 5610-M3046-1 E5 2 C 2.0 CK SA A SYS O/C CC RR RJ-04 CO RR RJ.04 Valve Name: Boric Acid Pump Discharge Check Valve 4-397D 5610-M-3046-1 F4 2 C 2.0 CK SA A SYS O/C CC RR RJ-04 CO RR RJ-04 Valve Name: Boric Acid Pump Discharge Check Valve HCV-104 5610-M-3046-1 C4 2 B 2.0 GL AO A C C BTC M3 FC M3 TPv.04 Valve Name: Boric Acid Storage Tank Recirculation Control Valv Revision Date: 2/11/2004 Page 188

Turkey Point Nuclear Plant IST Program Plan Chemical and Volume Control (047) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive PosItion Position Type Freq. Request Just Pos.

3-298A 5613-M-3047-3 F4 1 A/C 2.0 CK SA A SYS C AT401 App-J CC RR VR-01 RJ-16 TPv-08 CO RR VR-01 RJ-16 TPv-01 Valve Name: 3A RCP Seal Injection Check Valve 3-298B 5613-M-3047-3 B4 1 A/C 2.0 CK SA A SYS C AT-01 App-J CC RR VR-01 RJ-16 TPv48 CO RR VR-01 RJ-16 TPv41 Valve Name: 3B RCP Seal Injection Check Valve 3-298C 5613-M-3047-3 D4 1 AtC 2.0 CK SA A SYS C AT-01 App-J CC RR VR-01 RJ-16 TPvM CO RR VR-01 RJ-16 TPv-01 Valve Name: 3C RCP Seal Injection Check Valve 3-312A 5613-M-3047-2 C8 1 C 3.0 CK SA A SYS 0 CCF CM TPv-01,02 COF CM TPv402 Valve Name: Charging Line Check Valve 3-3128 5613-M-3047-2 AB 1 C 3.0 CK SA A SYS 0 CCF CM TPv-01.02 COF CM TPv-02 Valve Name: Loop C Charging Line Check Valve 3-312C 56134-3047-2 E7 1 ANC 3.0 CK SA A SYS OIC AT-01 App-J CC RR RJ-14 TPv408 CO M3 Valve Name: Charging Line Check Valve 3-351 5613-M-3047-2 F1 2 C 2.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM RJ-15 TPv.02 Valve Name: Emergency Boration Check Valve 3-357 5613-M-3047-2 F3 2 C 4.0 CK SA A SYS 0 CCR CM TPv401,02 COF CM CSJ-22 TPv-02 Valve Name: Emergency Makeup to Charging Pumps Check Valve CV-3-200A 5613-M-3047-1 A2 I A 2.0 GL AO A 0 C AT-01 App4J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Letdown Orifice Stop Valve Revision Date: 2/11/2004 Page 189

Turkey Point Nuclear Plant IST Program Plan Chemical and Volume Control (047) Valve Table P&iD Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

ValveTag P81D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV-3-200B 561343047-1 B2 1 A 2.0 GL AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Letdown Orifice Stop Valve CV-3-200C 5613-M-3047-1 C2 1 A 2.0 GL AO A 0 C AT-1 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Letdown Orifice Stop Valve CV-3-204 5613-M-3047-1 C4 2 A 2.0 GL AO A 0 C AT-01 App-J BTC CS CSJ-16 FC CS CSJ-16 TPv-04 PIT Y2 Valve Name: Letdown Line Isolation Valve CV-3-310A 5613-M-3047-2 C7 1 B 2.0 GL AO A 0 0 BTO M3 FO M3 TPv.04 PIT Y2 Valve Name: Loop A Charging Isolation Valve CV-3-310B 561343047-2 A7 1 B 2.0 GL AO A C 0 BTO M3 FO M3 TPv-04 PIT Y2 Valve Name: Charging Line Stop Valve Loop C CV.3-311 5613-M-3047-2 B7 1 B 2.0 GA AO P C C PIT Y2 Valve Name: Auxiliary Spray Isolation Valve CV-3-387 561343047-3 38 1 B 0.75 GL AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Excess Letdown Isolation Valve FCV-3-1138 5613-M3047-2 D3 2 B 2.0 PLG AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Blender Flow to Charging Pump Revision Date: 2/11/2004 Page 190

Turkey Point Nuclear Plant IST Program Plan Chemical and Volume Control (047) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

FCV-3-114B 5614-M-3047-2 B2 SR B 2.0 PLG AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Blender Flow to VCT HCV-3-121 5613-M-3047-2 F7 2 B 3.0 GL AO A 0 0 BTO CS CSJ-19 FO CS CSJ-19 TPv-04 Valve Name: Charging Flow to Regenerative Heat Exchanger LCV-3-115B 5613-M-3047-2 F4 2 B 4.0 BTF AO A C O/C BTO CS CSJ-20 TPv-09 FC CS CSJ-20 TPv-04 PIT Y2 Valve Name: Emergency Makeup to Charging Pumps LCV-3-115C 5613-M-3047-2 C4 2 B 4.0 GL MO A 0 C BTC CS CSJ-21 PIT Y2 Valve Name: VCT Outlet Isolation Valve MOV.3-350 5613-M-3047-2 F1 2 B 2.0 GA MO A C O/C BTO M3 TPv-09 PIT Y2 Valve Name: Emergency Boration Valve MOV-3-381 5613-M-3047-3 H3 2 A 3.0 GA MO A 0 C AT-01 App4 BTC CS CSJ-25 PIT Y2 Valve Name: RCP Seal Water Return and Excess Letdown Isol MOV-3-6386 5613-W047-3 H5 2 A 3.0 GA MO A 0 C AT-01 AppJ BTC CS CSJ-25 PIT Y2 Valve Name: RCP Seal Return Isol RV-3-203 5613-M-3047-1 A3 2 A/C 2.0 RV SA A C OIC AT-01 App-J RT Y10 Valve Name: Letddown Line Relief Valve RV-3-283A 5613-M-3047-2 G5 2 C 0.75 RV SA A C OIC RT Y10 Valve Name: Charging Pump 3A Discharge Relief Valve RV-3-283B 5613-M3047-2 E5 2 C 0.75 RV SA A C O/C RT Y10 Valve Name: Charging Pump 3B Discharge Relief Valve Revision Date: 2/111/2004 Page 191

Turkey Point Nuclear Plant IST Program Plan Chemical and Volume Control (047) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&8D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV-3-283C 5613-M-3047-2 C5 2 C 0.75 RV SA A C 0/C RT Y10 Valve Name: Charging Pump 3C Discharge Relief Valve RV-3-303 5613-M-3047-3 G4 2 A/C 0.75 RV SA A C OIC AT-01 App-J RT Y10 Valve Name: RCP Seal Return Relief Valve RV-3-304 561343047-3 D8 1 C 0.75 RV SA A C O/C RT Y5 Valve Name: Excess Letdown Heat Exchanger Relief Valve 4-298A 5614M-3047-3 F4 1 A/C 2.0 CK SA A SYS C AT-01 App-J CC RR VR-01 RJ-16 TPv-08 CO RR VR-01 RJ-16 TPv401 Valve Name: 4A RCP Seal Injection Check Valve 4-298B 5614M-3047-3 B4 1 A/C 2.0 CK SA A SYS C AT-01 App-J CC RR VR-01 RJ-16 TPv-08 CO RR VR-01 RJ-16 TPv-01 Valve Name: 4B RCP Seal Injection Check Valve 4-298C 5614M-3047-3 D4 1 A/C 2.0 CK SA A SYS C AT401 App-J CC RR VR-01 RJ-16 TPv408 CO RR VR-01 RJ-16 TPv-01 Valve Name: 4C RCP Seal Injection Check Valve 4-312A 561443047-2 CU 1 C 3.0 CK SA A SYS 0 CCF CM TPv-01,02 COF CM TPv-02 Valve Name: Charging Line Check Valve 4-312B 561443047-2 A7 1 C 3.0 CK SA A SYS 0 CCF CM TPv401.02 COF CM TPv402 Valve Name: Loop C Charging Line Check Valve 4-312C 5614.M-3047-2 E7 1 A/C 3.0 CK SA A SYS O/C AT-01 App-J CC RR RJ-14 TPv408 CO M3 Valve Name: Charging Line Check Valve 4-351 5614-M-3047-2 F1 2 C 2.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM RJ-15 TPv402 Valve Name: Emergency Boration Check Valve Revis/on Date: 2/11/2004 Page 192

Turkey Point Nuclear Plant IST Program Plan Chemical and Volume Control (047) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive PosItion Position Type Freq. Request Just. Pos.

4-357 5614-M-3047-2 F3 2 C 4.0 CK SA A SYS 0 CCR CM TPv-01.02 COF CM CSJ-22 TPv-02 Valve Name: Emergency Makeup to Charging Pumps Check Valve CV4-200A 5614-M-3047-1 A2 1 A 2.0 GL AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Letdown Orifice Stop Valve CV-4-200B 5614-M-3047-1 B2 1 A 2.0 GL AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Letdown Orifice Stop Valve CV4-200C 5614M3047-1 C2 1 A 2.0 GL AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Letdown Orifice Stop Valve CV41204 5614-M43047-1 C4 2 A 2.0 GL AO A 0 C AT-01 App-J BTC CS CSJ-16 FC CS CSJ-16 TPv-04 PIT Y2 Valve Name: Letdown Line Isolation Valve CV4.310A 5614M3047-2 C7 1 B 2.0 GL AO A 0 0 BTO M3 FO M3 TPv-04 PIT Y2 Valve Name: Loop A Charging Isolation Valve CV4-310B 5614-M3047-2 A7 I B 2.0 GL AO A C 0 BTO M3 FO M3 TPv-04 PIT Y2 Valve Name: Charging Line Stop Valve Loop C K.." CV4-311 5614M-3047-2 B7 1 B 2.0 GA AO P C C PIT Y2 Valve Name: Auxiliary Spray Isolation Valve 211112004 Page 193 Revision Dafe:

Revision Date: 2/11/2004 Page 193

Turkey Point Nuclear Plant IST Program Plan Chemical and Volume Control (047) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&8D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV-4-387 5614-M-3047-3 B8 1 B 0.75 GL AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Excess Letdown Isolation Valve FCV-4-113B 5614-M-3047-2 D3 2 B 2.0 PLG AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Blender Flow to Charging Pump FCV-4-114B 5613V-3047-2 B2 SR B 2.0 PLG AO A C C BTC M3 FC M3 TPvO04 PIT Y2 Valve Name: Blender Flow to VCT HCV4121 5614-3047-2 F7 2 B 3.0 GL AO A 0 0 BTO CS CSJ-19 FO CS CSJ-19 TPv-04 Valve Name: Charging Flow to Regenerative Heat Exchanger LCV4-115B 5614-M-3047-2 F4 2 B 4.0 BTF AO A C O/C BTO CS CSJ-20 TPv-09 FC CS CSJ-20 TPv-04 PIT Y2 Valve Name: Emergency Makeup to Charging Pumps LCV-4-115C 5614-3047-2 C4 2 B 4.0 GL MO A 0 C BTC CS CSJ-21 PIT Y2 Valve Name: VCT Outlet Isolation Valve MOV.4.350 5614-M-3047-2 F1 2 B 2.0 GA MO A C 0WC BTO M3 TPvO09 PIT Y2 Valve Name: Emergency Boration Valve MOV4-381 5614-M-3047-3 H3 2 A 3.0 GA MO A 0 C AT-01 App-J BTC CS CSJ-25 PIT Y2 Valve Name: RCP Seal Water Return and Excess Letdown Isol MOV4-6386 5614-M-3047-3 H5 2 A 3.0 GA MO A 0 C AT-01 App-J BTC CS CSJ-25 PIT Y2 Valve Name: RCP Seal Return Isol Revision Date: 2/1112004 Page 194

Turkey Point Nuclear Plant IST Program Plan Chemical and Volume Control (047) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV-4.203 5614M-3047-1 A3 2 A/C 2.0 RV SA A C O/C AT-01 App-J RT Y10 Valve Name: Letddown Line Relief Valve RV-4-283A 5614-M-3047-2 G5 2 C 0.75 RV SA A C O1C RT Y10 Valve Name: Charging Pump 4A Discharge Relief Valve RV-4-283B 5614.M-3047-2 E5 2 C 0.75 RV SA A C OIC RT Y10 Valve Name: Charging Pump 4B Discharge Relief Valve RV-4-283C 5614-3047-2 C5 2 C 0.75 RV SA A C O/C RT Y10 Valve Name: Charging Pump 4C Discharge Relief Valve RV4.303 5613-M-3047-3 G4 2 A/C 0.75 RV SA A C O/C AT-01 App-J RT Y10 Valve Name: RCP Seal Return Relief Valve K) RV.4.304 5614-M-3047-3 D8 1 C 0.75 RV SA A C OIC RT Y5 Valve Name: Excess Letdown Heat Exchanger Relief Valve Date:

Revision Date: 2111/2004 Page 195 Revislon 2t11/2004 Page 195

Turkey Point Nuclear Plant IST Program Plan Residual Heat Removal (050) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-2052 5613-M-3050-1 A7 2 C 1.0 CK SA A SYS 0/C CC RR RJ-17 CO RR RJ-17 Valve Name: Containment Spray Suction Relief Line Check Valve 3-741A 5613-M-3050-1 D7 2 8 2.0 GA MAN A LC O/C BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: RHR Recirc Line Isolation Valve 3-752A 5613-M-3050-1 C2 2 B 14.0 GA MAN A LO O/C STC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: RHR Pump 3A Manual Suction Stop Valve 3-752B 5613-M-3050-1 E2 2 B 14.0 GA MAN A LO O/C BTC Y2 TPv-11 BTO Y2 TPv-1I Valve Name: RHR Pump 3B Manual Suction Stop Valve 3-753A 5613-M-3050-1 C4 2 C 10.0 CK SA A SYS O/C CC CS CSJ-29 CO CS CSJ-29 Valve Name: RHR Pump 3A Discharge Check Valve 3-7538 5613-M-3050-1 E4 2 C 10.0 CK SA A SYS O/C CC CS CSJ-29 CO CS CSJ-29 Valve Name: RHR Pump 3B Discharge Check Valve HCV-3-758 5613-M-3050-1 C6 2 B 12.0 BTF AO P 0 0 PIT Y2 Valve Name: RHR Hx Outlet Flow Valve MOV-3-750 561343050-1 F8 1 A 14.0 GA MO A C O/C AT-02 Y2 BTC CS CSJ-27 BTO CS CSJ-27 PIT Y2 Valve Name: Loop 3C RHR Pump Suction Stop Valve MOV-3-751 5613-M-3050-1 F7 1 A 14.0 GA MO A C O/C AT-02 Y2 BTC CS CSJ-27 8TO CS CSJ-27 PIT Y2 Valve Name: Loop 3C RHR Pump Suction Stop Valve Revision Date: 2/11/2004 Page 196

Turkey Point Nudear Plant IST Program Plan Residual Heat Removal (050) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

MOV.3-860A 5613-M-3050-1 A6 2 B 14.0 GA MO A C O/C BTO M3 TPv-09 PIT Y2 Valve Name: Containment South Recirculation Sump Isol Valve MOV.3-860B 5613-M-3050-1 B6 2 B 14.0 GA MO A C O/C BTO M3 TPv-09 PIT Y2 Valve Name: Containment North Recirculation Sump Isol Valve MOV.3-861A 561343050-1 AS 2 B 14.0 GA MO A C 0/C BTO M3 TPv-09 PIT Y2 Valve Name: Containment South Recirculation Sump Isol Valve MOV-3-861B 5613-M-3050-1 B5 2 B 14.0 GA MO A C O/C BTO M3 TPv-09 PIT Y2 Valve Name: Containment North Recirculation Sump Isol Valve MOV-3-862A 561343050-1 El 2 B 14.0 GA MO A LO 0/C BTC CS CSJ-26 TPv-09 PIT Y2 Valve Name: RHR Suction from RWST MOV.3-862B 5613-M-3050-1 El 2 B 14.0 GA MO A LO O/C BTC CS CSJ-26 TPv-09 PIT Y2 Valve Name: RHR Suction from RWST MOV.3-863A 5613-M-3050-1 F5 2 B 8.0 GA MO A LC O/C BTO CS CSJ-28 TPv-09 PIT Y2 Valve Name: RHR Alternate Disch Isol MOV.3-863B 561343050-1 F5 2 B 8.0 GA MO A LC O/C BTO CS CSJ-28 TPv-09 PIT Y2 Valve Name: RHR Alternate Disch Isol MOV.3-872 5613-M-3050-1 G6 2 B 8.0 GA MO A C O/C BTO CS CSJ-31 TPv-09 PIT Y2 Valve Name: Alternate Low Head SI 4-2052 561443050-1 A7 2 C 1.0 CK SA A SYS O/C CC RR RJ-17 CO RR RJ-17 Valve Name: Containment Spray Suction Relief Line Check Valve Revislon Date: 2/11/2004 Page 197

Turkey Point Nuclear Plant IST Program Plan Residual Heat Removal (050) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

4-741A 5614-M-3050-1 D7 2 8 2.0 GA MAN A LC O/C BTC Y2 TPv-11 BTO Y2 TPv-1 Valve Name: RHR Recirc Line Isolation Valve 4-752A 5614-M-3050-1 C2 2 B 14.0 GA MAN A LO OC BTC Y2 TPv-1I BTO Y2 TPv-1 1 Valve Name: RHR Pump 4A Manual Suction Stop Valve 4-752B 5614M-3050-1 E2 2 B 14.0 GA MAN A LO O/C BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: RHR Pump 4B Manual Suction Stop Valve 4-753A 5614-M-3050-1 C4 2 C 10.0 CK SA A SYS OC CC CS CSJ-29 CO CS CSJ-29 Valve Name: RHR Pump 4A Discharge Check Valve 4-753B 5614-M-3050-1 E4 2 C 10.0 CK SA A SYS 0/C CC CS CSJ-29 CO CS CSJ-29 Valve Name: RHR Pump 4B Discharge Check Valve HCV-4-758 5614-M-3050-1 C6 2 B 12.0 BTF AO P 0 0 PIT Y2 Valve Name: RHR Hx Outlet Flow Valve MOV-4-750 56144M3050-1 F8 1 A 14.0 GA MO A C O/C AT.02 Y2 BTC CS CSJ-27 8TO CS CSJ-27 PIT Y2 Valve Name: Loop 4A RHR Pump Suction Stop Valve MOV14-751 5614-M-3050-1 F7 1 A 14.0 GA MO A C OC AT-02 Y2 BTC CS CSJ-27 TO CS CSJ-27 PIT Y2 Valve Name: Loop 4A RHR Pump Suction Stop Valve MOV4-860A 5614M-3050-1 A6 2 B 14.0 GA MO A C O/C BTO M3 TPv-09 PIT Y2 Valve Name: Containment North Recirculation Sump Isol Valve Revision Date: 2/11/2004 Page 198

Turkey Point Nuclear Plant IST Program Plan Residual Heat Removal (050) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

MOV-4-860B 5614-M-3050-1 B6 2 B 14.0 GA MO A C O/C BTO M3 TPv-09 PIT Y2 Valve Name: Containment South Recirculation Sump Isol Valve MOV.4-861A 5614-M-3050-1 A5 2 B 14.0 GA MO A C O/C BTO M3 TPv.09 PIT Y2 Valve Name: Containment North Recirculation Sump Isol Valve MOV.4-861B 5614-M-3050-1 B5 2 B 14.0 GA MO A C O/C BTO M3 TPV-09 PIT Y2 Valve Name: Containment South Recirculation Sump Isol Valve MOV4-862A 56144M-3050-1 El 2 B 14.0 GA MO A LO O/C BTC CS CSJ-26 TPv-09 PIT Y2 Valve Name: RHR Suction from RWST MOV-44862B 5614-M-3050-1 Di 2 B 14.0 GA MO A LO OIC BTC CS CSJ-26 TPv-09 PIT Y2 Valve Name: RHR Suction from RWST MOV4-63A 5614-M-3050-1 F5 2 B 8.0 GA MO A LC OIC BTO CS CSJ-28 TPv-09 PIT Y2 Valve Name: RHR Alternate Disch Isol MOV.4-863B 5614-M-3050-1 F5 2 B 8.0 GA MO A LC O/C STO CS CSJ-28 TPv-09 PIT Y2 Valve Name: RHR Alternate Disch Isol MOV.4-872 5614-M-3050-1 G6 2 B 8.0 GA MO A C OIC BTO CS CSJ-31 TPv-09 PIT Y2 Valve Name: Alternate Low Head SI Revision Date: 2/11/2004 Page 199

Turkey Point Nuclear Plant IST Program Plan Containment Purge (053) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve T;ag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-2025 5613-M3053-1 A6 2 A 0.75 GL MAN P LC C AT-01 App-J Valve Name: Isolation Valve for Penetration 65B 3-2026 5613-M-3053-1 B6 2 A 0.75 GL MAN P LC C AT-01 App-J Valve Name: Isolation Valve for Penetration 65C

& CV-3.28 19 5613-M3053-1 E7 2 A 2.00 GL AO A 0 C AT-01 ADD-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Containment Instrument Air Bleed Control Valve CV-3-2826 5613-3053-1 E6 2 A 2.00 GL AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Containment Instrument Air Bleed Control Valve POV.3-2600 5613-M-3053-1 C6 2 A 48.0 BTF AO A C C AT-01 App-J BTC CS CSJ-02 FC CS CSJ-02 TPv-04 PIT Y2 Valve Name: Containment Purge Supply Isolation POV-3-2601 5613-3053-1 C7 2 A 48.0 BTF AO A C C AT-01 App-J BTC CS CSJ-02 FC CS CSJ-02 TPv-A PIT Y2 Valve Name: Containment Purge Supply Isolation POV-3-2602 561343053-1 D6 2 A 54.0 BTF AO A C C AT-01 App4J BTC CS CSJ-02 FC CS CSJ-02 TPv-04 PIT Y2 Valve Name: Containment Purge Exhaust Isolation Revision Date: 2111/2004 Page 200

Turkey Point Nuclear Plant

[ST Program Plan Containment Purge (053) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

POV.3-2603 5613-M-3053-1 D7 2 A 54.0 BTF AO A C C AT-01 App-J BTC CS CSJ-02 FC CS CSJ-02 TPv-04 PIT Y2 Valve Name: Containment Purge Exhaust Isolation 4-2025 5614-M-3053-1 A3 2 A 0.75 GL MAN P LC C AT-01 App-J Valve Name: Isolation Valve for Penetration 65C 4-2026 5614-M4053-1 B3 2 A 0.75 GL MAN P LC C AT-01 App-J Valve Name: Isolation Valve for Penetration 65B CV-4-2819 5614-M053-1 E2 2 A 2.00 GL AO A 0 C AT-01 App-J 8TC M3 FC M3 TPv-4 PIT Y2 Valve Name: Containment Instrument Air Bleed Control Valve CV-4-2826 5614-M-3053-1 E3 2 A 2.00 GL AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Containment Instrument Air Bleed Control Valve POV.4-2600 5614-M-3053-1 83 2 A 48.0 BTF AO A C C AT-01 App-J BTC CS CSJ-02 FC CS CSJ-02 TPv-04 PIT Y2 Valve Name: Containment Purge Supply Isolation POV.4-2601 5614-M-3053-1 82 2 A 48.0 BTF AO A C C AT-01 Appo BTC CS CSJ402 FC CS CSJ-02 TPv-04 PIT Y2 Valve Name: Containment Purge Supply Isolation Revision Date: 2/11/2004 Page 201

Turkey Point Nuclear Plant IST Program Plan Containment Purge (053) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

POV4-2602 5614-M-3053-1 D-3 2 A 54.0 BTF AO A C C AT-01 App-J BTC CS CSJ-02 FC CS CSJ-02 TPv-04 PIT Y2 Valve Name: Containment Purge Exhaust Isolation POV4-2603 561443053-1 D-2 2 A 54.0 BTF AO A C C AT-1 App-J BTC CS CSJ-02 FC CS CSJ-02 TPv-04 PIT Y2 Valve Name: Containment Purge Exhaust Isolation 211112004 Page 202 Revision Date:

Revision Date: 2/11/2004 Page 202

Turkey Point Nuclear Plant IST Program Plan Liquid Waste Disposal System (061) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

CV3-2821 5613-M-3061-1 H6 2 A 3.0 GL AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Cntmt Sump Pump Disch Line Cntmnt Iso Valve CV-3-2822 5613-M3061-1 H5 2 A 3.0 GL AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Cntmt Sump Pump Disch Line Cntmnt Iso Valve CV-3-4658A 5613-M-3061-1 636 2 A 1.0 DIA AO A 0 C AT-01 App-J BTC M3 FC M3 TPv44 PIT Y2 Valve Name: RCDT to VH Line Cntmt Iso Vlv CV-3-4658B 5613-M-3061-1 B6 2 A 1.0 DIA AO A 0 C AT-01 App-J BTC M3 FC M3 TPv.04 PIT Y2 Valve Name: RCDT to VH Line Cntmt Iso Vlv CV-34659A 5613M-3061-1 D6 2 A 0.75 DIA AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: RCDT to Gas Analyzer Cntmnt Iso Viv CV-3-4659B 561343061-1 D6 2 A 0.75 DIA AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: RCDT to Gas Analyzer Cntmnt Iso Viv Revision Date: 2111/2004 Page 203

Turkey Point Nuclear Plant IST Program Plan Liquid Waste Disposal System (061) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV-34668A 5613-3061-1 G5 2 A 3.0 DIA AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: RCDT Pump Disch Cntmt Isolation Valve CV-3-4668B 5613-M-3061-1 G6 2 A 3.0 DIA AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: RCDT Pump Disch Cntmt Isolation Valve CV4-2821 5614-M-3061-1 H6 2 A 3.0 GL AO A 0 C AT-01 App-J BTC M3 FC B TPv-04 PIT Y2 Valve Name: Cntmt Sump Pump Disch Line Cntmnt Iso Valve CV4-2822 56144-3061-1 H5 2 A 3.0 GL AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: Cntmt Sump Pump Disch Line Cntmnt Iso Valve CV44658A 5614-M-3061-1 B6 2 A 1.0 DIA AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2

> Valve Name: RCDT to VH Line Cntmt Iso VIv CV4-4658B 561443061-1 B6 2 A 1.0 DIA AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: RCDT to VH Line Cntmt Iso Vlv Revision Date: 2111/2004 Page 204

Turkey Point Nuclear Plant IST Program Plan Liquid Waste Disposal System (061) Valve Table PSID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV44659A 5614-M-3061-1 D6 2 A 0.75 DIA AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: RCDT to Gas Analyzer Cntmnt Iso Vlv CCV44659B 56144-3061-1 D6 2 A 0.75 DIA AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: RCDT to Gas Analyzer Cntmnt Iso VIv CV.44668A 5614-M-3061-1 G5 2 A 3.0 DIA AO A 0 C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: RCDT Pump Disch Cntmt Isolation Valve CV44668B 5614-M-3061-1 G6 2 A 3.0 DIA AO A 0 C AT-01 App-J BTC M3 FC M3 TPv.04 PIT Y2 Valve Name: RCDT Pump Disch Cntmt Isolation Valve Revision Date: 2/1112004 Page 205

Turkey Point Nuclear Plant IST Program Plan Safety Injection (062) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-874A 56134-3062-1 C7 1 A/C 2.0 CK SA A SYS O/C AT-02 Y2 CC RR RJ-06 TPv-08 CO RR RJ-06 Valve Name: SI Hot Leg Injection Loop A Check Valve 3-8748 5613-M-3062-1 F7 1 A/C 2.0 CK SA A SYS O/C AT402 Y2 CC RR RJ406 TPv-08 CO RR RJ-06 Valve Name: SI Hot Leg Injection Loop B Check Valve 3-874C 5613-M-3062-1 F2 2 C 2.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: SI Pump Minimum Flow/Test Return Check Valve 3-879A 561343062-1 G5 2 C 3.0 CK SA A SYS O/C CC M3 CO RR RJ-07 Valve Name: Safety Injection Pump 3B Discharge Check Valve 3-8798 5613-M3062-1 E4 2 C 3.0 CK SA A SYS O/C CC M3 CO RR RJ-07 Valve Name: Safety Injection Pump 3A Discharge Check Valve 3-893A 5613-M-3062-1 F4 2 C 0.75 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: Safety Injection Pump 3B Minimum Flow Check Valve 3-893B 5613-M-3062-1 E4 2 C 0.75 CK SA A SYS 0 CCR CM TPv401,02 COF CM TPv-02 Valve Name: Safety Injection Pump 3A Minimum Flow Check Valve MOV.3-843A 561343062-2 B6 2 B 4.0 GA MO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: SI Cold Leg Injection Valve MOV-3-843B 5613-M3062-2 C6 2 B 4.0 GA MO A C OIC BTC M3 BTO M3 PIT Y2 Valve Name: SI Cold Leg Injection Valve Revision Date: 2/11/2004 Page 206

Turkey Point Nuclear Plant IST Program Plan Safety Injection (062) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

MOV.3-856A 5613-M-3062-1 B1 2 B 2.0 GL MO A 0 OIC BTC CS CSJ-05 TPv-09 PIT Y2 Valve Name: HSSI Pump Recirculatlon to RWST MOV.3-856B 5613-M43062-1 B1 2 B 2.0 GL MO A 0 O/C BTC CS CSJ-05 TPv-09 PIT Y2 Valve Name: HSSI Pump Recirculation to RWST MOV-3-864A 5613-M43062-1 C4 2 B 16.0 GA MO A 0 OIC STC CS CSJ-06 TPv-09 PIT Y2 Valve Name: RWST Outlet Isolation Valve MOV.3-864B 561343062-1 C4 2 B 16.0 GA MO A 0 O/C BTC CS CSJ-06 TPv-09 PIT Y2 Valve Name: RWST Outlet Isolation Valve MOV-3-866A 5613-M3062-1 D7 1 A 2.0 GA MO A C O/C BTC CS CSJ403 STO CS CSJ-03 PIT Y2 Valve Name: Loop A Hot Leg Safety Injection Isolation Valve MOV.3-866B 5613-M-3062-1 F7 1 A 2.0 GA MO A C O/C BTC CS CSJ-03 BTO CS CSJ-03 PIT Y2 Valve Name: Loop B Hot Leg Safety Injection Isolation Valve MOV.3-869 5613-M-3062-1 E6 2 B 3.0 GA MO A C OIC BTC M3 BTO M3 PIT Y2 Valve Name: Loop A & B Hot Leg Safety Injection Valve MOV-878A 5613-M43062-1 D5 2 B 4.0 GA MO A 0 OIC BTC CS CSJ-04 TPv09 PIT Y2 Valve Name: SI Pump Discharge Header Unit Cross Tie Viave MOV-878B 5613-M-062-1 D5 2 B 4.0 GA MO A 0 OC BTC CS CSJ-04 TPv49 PIT Y2 Valve Name: SI Pump Discharge Header Unit Cross Tie Vlave RV.3-6511 561343062-1 F8 2 C 0.25 RV SA A C OIC RT Y10 Valve Name: Safety Injection Hot Leg Relief Valve Revision Date: 2/11/2004 Page 207

Turkey Point Nuclear Plant IST Program Plan Safety Injection (062) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag I P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV3-857 5613-M-3062-2 C5 2 C 0.75 RV SA A C O/C RT Y10 Valve Name: Safety Injection Cold Leg Header Relief Valve 4-874A 5614.M-3062-1 C7 1 A/C 2.0 CK SA A SYS O/C AT-02 Y2 CC RR RJ-06 TPv48 CO RR RJ-06 Valve Name: Si Hot Leg Injection Loop A Check Valve 4-874B 5614-M-3062-1 F7 1 A/C 2.0 CK SA A SYS O/C AT402 Y2 CC RR RJ-06 TPv-08 CO RR RJ-06 Valve Name: Si Hot Leg Injection Loop B Check Valve 4-874C 5614-M-3062-1 F2 2 C 2.0 CK SA A SYS 0 CCR CM TPv41,02 COF CM TPv-02 Valve Name: SI Pump Minimum Flow/Test Return Check Valve 4-879C 5614-M-3062-1 E4 2 C 3.0 CK SA A SYS O/C CC M3 CO RR RJ-07 Valve Name: Safety Injection Pump 4A Discharge Check Valve 4-879D 5614-M-3062-1 G5 2 C 3.0 CK SA A SYS O/C CC M3 CO RR RJ-07 Valve Name: Safety Injection Pump 4B Discharge Check Valve 4-893C 5614-M-3062-1 E4 2 C 0.75 CK SA A SYS 0 CCR CM TPv-01.02 COF CM TPv42 Valve Name: Safety Injection Pump 4A Minimum Flow Check Valve 4-893D 5614-M-3062-1 F4 2 C 0.75 CK SA A SYS 0 CCR CM TPv401,02 COF CM TPv-02 Valve Name: Safety Injection Pump 4B Minimum Flow Check Valve MOV.4-843A 5614-M-3062-2 C6 2 B 4.0 GA MO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: SI Cold Leg Injection Valve Revision Date: 2/11/2004 Page 208

Turkey Point Nuclear Plant IST Program Plan Safety Injection (062) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

MOV44843B 5614-M-3062-2 D6 2 B 4.0 GA MO A C OC BTC M3 BTO M3 PIT Y2 Valve Name: Si Cold Leg Injection Valve MOV44856A 5614-M-3062-1 B1 2 B 2.0 GL MO A 0 OIC BTC CS CSJ-05 TPv-09 PIT Y2 Valve Name: HSSI Pump Recirculation to RWST MOV4-856B 561443062-1 81 2 B 2.0 GL MO A 0 OIC BTC CS CSJ-05 TPv-09 PIT Y2 Valve Name: HSSI Pump Recirculation to RWST MOV4-864A 5614-4062-1 C4 2 B 16.0 GA MO A 0 O/C BTC CS CSJ-06 TPv-09 PIT Y2 Valve Name: RWST Outlet Isolation Valve K MOV4.864B 561443062-1 C4 2 B 16.0 GA MO A 0 OC BTC CS CSJ-06 TPv-09 PIT Y2 Valve Name: RWST Outlet Isolation Valve MOV.4466A 561443062-1 D7 1 A 2.0 GA MO A C OIC BTC CS CSJ-03 BTO CS CSJ-03 PIT Y2 Valve Name: Loop A Hot Leg Safety Injection Isolation Valve MOV.4-866B 561443062-1 F7 1 A 2.0 GA MO A C OIC BTC CS CSJ-03 BTO CS CSJ-03 K PIT Y2 Valve Name: Loop B Hot Leg Safety Injection Isolation Valve MOV.469 5614-M-3062-1 E6 2 B 3.0 GA MO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Loop A & B Hot Leg Safety Injection Valve RV-44511 561443062-1 F7 2 C 0.25 RV SA A C OIC RT Y10 Valve Name: Safety Injection Hot Leg Relief Valve K> RV84457 5614-M-3062-2 C4 2 C 0.75 RV SA A C OIC RT Y10 Valve Name: Safety Injection Cold Leg Header Relief Valve Revision Date: 2/11/2004 Page 209

Turkey Point Nudear Plant IST Program Plan Safety Injection Accumulators (064) Valve Table P&D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-873A 56134-3064-1 82 1 AIC 2.0 CK SA A SYS OIC AT-02 Y2 CC RR RJ-08 TPv-48 CO RR RJ-08 Valve Name: Loop A Cold Leg Branch Line Check Valve 3-873B 5613-M-3064-1 82 1 A/C 2.0 CK SA A SYS OIC AT-02 Y2 CC RR RJ48 TPv4O8 CO RR RJ-08 Valve Name: Loop B Cold Leg Branch Line Check Valve 3-873C 56134-3064-1 82 1 A/C 2.0 CK SA A SYS O1C AT-02 Y2 CC RR RJ-08 TPv-08 CO RR RJ-08 Valve Name: Loop C Cold Leg Branch Une Check Valve 3-875A 5613-M-3064-1 D8 1 A/C 10.0 CK SA A SYS OIC AT402 Y2 CCF CM CSJ-07 TPv-0802 COA CM RJ-09 TPv-02 COF CM RJ409 TPv-02 Valve Name: Loop A Cold Leg Injection Check Valve 3-875B 5613-M-3064-1 E8 1 A/C 10.0 CK SA A SYS O/C AT-02 Y2 CCF CM CSJ-07 TPv-08 COA CM RJ-09 TPv-02 COF CM RJ4-9 TPv-02 Valve Name: Loop B Cold Leg Injection Check Valve 3-875C 5613-M630S4-1 E8 1 A/C 10.0 CK SA A SYS oiC AT-02 Y2 CCF CM CSJ407 TPv-08 COA CM RJ-09 TPv-02 COF CM RJ409 TPv-02 Valve Name: Loop C Cold Leg Injection Check Valve 3-875D 5613-M-3064-1 C7 1 C 10.0 CK SA A SYS OIC CCF CM RJ-10 TPv-08,02 COA CM TPv-08,02 COF CM RJ-10 TPv-08,02 Valve Name: Si Accumulator 3A Check Valve Revision Date: 2/1112004 Page 210

Turkey Point Nuclear Plant IST Program Plan Safety Injection Accumulators (064) Valve Table P&WD Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&lD Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-875E 5613-M-3064-1 G5 I C 10.0 CK SA A SYS O/C CCF CM RJ-10 TPv-08,02 COA CM TPv-08,02 COF CM RJ-10 TPv-08,02 Valve Name: SI Accumulator 3B Check Valve 3-875F 5613-M-3064-1 G3 1 C 10.0 CK SA A SYS O/C CCF CM RJ-10 TPv-08,02 COA CM TPv-08,02 COF CM RJ-10 TPv-08,02 Valve Name: SI Accumulator 3C Check Valve 3-876A 56134-3064-1 H7 1 A/C 8.0 CK SA A SYS O/C AT-02 Y2 CC CS CSJ-08 TPv408 CO RR RJ-19 Valve Name: RHR Cold Leg Injection Check Valve 3-876B 5613-M-3064-1 G5 1 A/C 8.0 CK SA A SYS O/C AT-02 Y2 CC CS CSJ408 TPv48 CO RR RJ-19 Valve Name: RHR Cold Leg Injection Check Valve 3-876C 5613-M-3064-1 G3 1 A/C 8.0 CK SA A SYS O/C AT402 Y2 CC CS CSJ-08 TPv48 CO RR RJ-19 Valve Name: RHR Cold Leg Injection Check Valve 3-876D 5613-3064-1 G5 1 AIC 8.0 CK SA A SYS O/C AT-02 Y2 CC RR RJ-12 TPv48 CO RR RJ-12 Valve Name: Alternate Low Head Injection Line Check Valve 3-876E 5613-M-3064-1 G3 1 A/C 8.0 CK SA A SYS O/C AT-02 Y2 CC RR RJ-12 TPv408 CO RR RJ-12 Valve Name: Alternate Low Head Injection Line Check Valve 3-945E 5613-M-3064-1 B2 2 A/C 1.0 SCK SA A SYS C AT-01 App-J CC RR VR-01 RJ-18 TPv-08 CO RR VR-01 RJ-18 TPv-01 Valve Name: N2 Supply to Accumulators Check Valve Revision Date: 2/11/2004 Page 211

Turkey Point Nuclear Plant IST Program Plan Safety Injection Accumulators (064) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV-3-851A 5613-M-3064-1 C7 2 B 1.0 GL AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 3A Accumulator Makeup Valve CV-3-851B 56134-3064-1 C5 2 B 1.0 GL AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 3B Accumulator Makeup Valve CV-3-851C 5613-M-3064-1 C3 2 B 1.0 GL AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 3C Accumulator Makeup Valve MOV.3-744A 5613-M-3064-1 H3 2 B 10.0 GA MO A C O/C BTC CS CSJ-14 BTO CS CSJ-14 PIT Y2 Valve Name: RHR Discharge to Cold Leg Isolation Valve MOV3-744B 5613-M-3064-1 G3 2 B 10.0 GA MO A C O/C BTC CS CSJ-14 BTO CS CSJ-14 PIT Y2 Valve Name: RHR Discharge to Cold Leg Isolation Valve MOV.3-865A 5613-M-3064-1 F6 2 B 10.0 GA MO A 0 OC BTC CS CSJ-15 TPv49 PIT Y2 Valve Name: SI 3A Accumulator Discharge Isolation Valve MOV.3-865B 5613-M-3064-1 F4 2 B 10.0 GA MO A 0 O/C BTC CS CSJ-15 TPv-09 PIT Y2 Valve Name: SI 3B Accumulator Discharge Isolation Valve MOV-3-865C 5613-M-3064-1 F2 2 B 10.0 GA MO A 0 0/C BTC CS CSJ-15 TPv-09 PIT Y2 Valve Name: SI 3C Accumulator Discharge Isolation Valve RV-3.706 5613-M-3064-1 G2 2 C 2.0 RV SA A C O/C RT Y10 Valve Name: RHR to SI Cold Leg Relief Valve Revision Date: 2/1112004 Page 212

Turkey Point Nuclear Plant IST Program Plan Safety Injection Accumulators (064) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&8D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV-3-858A 5613-M-3064-1 D6 2 C 2.0 RV SA A C OIC RT Y10 Valve Name: Si 3A Accumulator Relief Valve RV-3-858B 561343064-1 D4 2 C 2.0 RV SA A C OC RT Y10 Valve Name: Si 3B Accumulator Relief Valve RV-34%5C 561343064-1 D2 2 C 2.0 RV SA A C OIC RT Y10 Valve Name: Si 3C Accumulator Relief Valve 4-873A 5614-M-3064-1 82 1 A/C 2.0 CK SA A SYS O/C AT-02 Y2 CC RR RJ-08 TPv-08 CO RR RJ408 Valve Name: Loop A Cold Leg Branch Line Check Valve 4-873B 56144.-3064-1 B2 1 A/C 2.0 CK SA A SYS O/C AT402 Y2 CC RR RJ-08 TPv408 CO RR RJ-0 Valve Name: Loop B Cold Leg Branch Line Check Valve 4-873C 5614-M-3064-1 B2 1 A/C 2.0 CK SA A SYS OIC AT-02 Y2 CC RR RJ-08 TPv-08 CO RR RJ-08 Valve Name: Loop C Cold Leg Branch Line Check Valve 4-875A 56144-3064-1 D8 1 A/C 10.0 CK SA A SYS O/C AT402 Y2 CCF CM CSJ407 TPv-08 COA CM RJ-09 TPv402 COF CM RJ-09 TPv-02 Valve Name: Loop A Cold Leg Injection Check Valve 44875B 5614-M-3064-1 E8 1 A/C 10.0 CK SA A SYS OIC AT-02 Y2 CCF CS CSJ407 TPv48 COA CM RJ-09 TPv42 COF CM RJ-09 TPv402 Valve Name: Loop B Cold Leg Injection Check Valve 4-875C 56144-3064-1 E8 1 A/C 10.0 CK SA A SYS O/C AT-02 Y2 CCF CS CSJ.07 TPv408 COA CM RJ-09 TPv402 COF CM RJ-09 TPv-02 Valve Name: Loop C Cold Leg Injection Check Valve Revision Date: 2/11/2004 Page 213

Turkey Point Nuclear Plant IST Program Plan Safety Injection Accumulators (064) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

4-875D 5614-M-3064-1 G7 1 C 10.0 CK SA A SYS O/C CCF CM RJ-10 TPv-08,02 COA CM TPv-08,02 COF CM RJ-10 TPv408,02 Valve Name: Si Accumulator 4A Check Valve 4-875E 56144M-3064-1 G5 I C 10.0 CK SA A SYS O/C CCF CM RJ-10 TPv-08,02 COA CM TPv-08,02 COF CM RJ-10 TPv-08,02 Valve Name: SI Accumulator 4B Check Valve 4-875F 56144-3064-1 G3 1 C 10.0 CK SA A SYS OIC CCF CM RJ-10 TPv-08,02 COA CM TPv-08,02 COF CM RJ-10 TPv-08,02 Valve Name: Si Accumulator 4C Check Valve 4-876A 56144-3064-1 H7 1 A/C 8.0 CK SA A SYS OIC AT402 Y2 CC CS CSJ-08 TPv-08 CO RR RJ-19 Valve Name: RHR Cold Leg Injection Check Valve 4-876B 56144M3064-1 G5 1 A/C 8.0 CK SA A SYS O/C AT402 Y2 CC CS CSJ-08 TPv48 CO RR RJ-19 Valve Name: RHR Cold Leg Injection Check Valve 4-876C 5614-M-3064-1 G3 1 A/C 8.0 CK SA A SYS OIC AT-02 Y2 CC CS CSJ-08 TPv-08 CO RR RJ-19 Valve Name: RHR Cold Leg Injection Check Valve 4-876D 56144vM3064-1 G5 1 A/C 8.0 CK SA A SYS OIC AT-02 Y2 CC RR RJ-12 TPv48 CO RR RJ-12 Valve Name: Alternate Low Head Injection Llne Check Valve 4-876E 5614-M-3064-1 G5 1 A/C 8.0 CK SA A SYS O/C AT-02 Y2 CC RR RJ-12 TPv-08 CO RR RJ-12 Valve Name: Alternate Low Head Injection Line Check Valve Revision Date: 2/11/2004 Page 214

Turkey Point Nuclear Plant Safey Acumuatos Inecton (04)1ST Program Plan Safey ccumIjecton latrs (64)Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag PaID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

4-945E 5614-M-3064-1 C2 2 A/C 1.0 CK SA A SYS C AT-01 App-J CC RR VR-0l RJ-18 TPv-O8 CO RR VR-01 RJ-18 TPv-01 Valve Name: N2 Supply to Accumulators Check Valve CV.4-851A 56144-3064-1 C5 2 B 1.0 GL AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 48 Accumulator Makeup Valve CV-4-851B 5614-M-364-1 C7 2 B 1.0 GL AO A C C BTC M3 FC M3 TPv-C4 PIT Y2 Valve Name: 4A Accumulator Makeup Valve CV.4-51C 5614-M-3064-1 C3 2 B 1.0 GL AO A C C BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: 4C Accumulator Makeup Valve MOV-4-744A 56144-3064-1 H3 2 B 10.0 GA MO A C 0/C BTC Cs CSJ-14 STO Cs CSJ-14 PIT Y2 Valve Name: RHR Discharge to Cold Leg Isolation Valve MOV.4-744B 5614-M-3064-1 G3 2 B 10.0 GA MO A C 0/C BTC CS CSJ-14 BTO Cs CSJ.14 PIT Y2 Valve Name: RHR Discharge to Cold Leg Isolation Valve MOV-4-865A 5614-M-3064-1 F6 2 B 10.0 GA MO A 0 0/C BTC CS CSJ-15 TPv-09 PIT Y2 Valve Name: SI 4A Accumulator Discharge Isolation Valve MOV-4-65B 5614-M-3064-1 F4 2 B 10.0 GA MO A 0 0/C BTC CS CSJ-15 TPv-09 PIT Y2 Valve Name: SI 48 Accumulator Discharge Isolation Valve K>MOV-4-865C 5614-M-3064-1 F2 2 B 10.0 GA MO A 0 0/C BTC CS CSJ-15 TPv-09 PIT Y2 Valve Name: SI 4C Accumulator Discharge Isolation Valve Revision Date: 2/11112004 Pg 215 Page 1

Turkey Point Nuclear Plant IST Program Plan Safety Injection Accumulators (064) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV4-706 5614-M-3064-1 G2 2 C 2.0 RV SA A C OC RT Y10 Valve Name: RHR to SI Cold Leg Relief Valve RV-4-858A 56144-3064-1 D6 2 C 2.0 RV SA A C OIC RT Y10 Valve Name: SI 4A Accumulator Relief Valve RV4458B 5614-43064-1 W4 2 C 2.0 RV SA A C O/C RT Y10 Valve Name: SI 4B Accumulator Relief Valve RV-4458C 5614-M-3064-1 D2 2 C 2.0 RV SA A C OIC RT Y10 Valve Name: SI 4C Accumulator Relief Valve Revision Date: 2t1112004 Page 216

Turkey Point Nuclear Plant IST Program Plan Nitrogen and Hydrogen (065) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

3-3449 5610-M-3065-1 C6 2 A 0.375 GL MAN P LC C AT-01 App-J Valve Name: N2 to RCDT PCV--1 014 Sensing Line Isolation Valve 3.4639 5610-M-3065-1 C6 2 A 0.75 DIA MAN P LC C AT-01 App-J Valve Name: N2 Supply to RCDT Isolation Valve 3-4656 5610-M-3065-1 C7 2 A 1.0 DIA MAN P LC C AT-01 App4J Valve Name: N2 Supply to RCDT Isolation Valve 3.518 5610-M-3065-1 D7 2 A/C 0.75 CK SA A SYS C AT-01 App-J CC RR VR-01 RJ-05 CO RR VR-01 RJ-05 TPv-01 Valve Name: N2 Supply to Pressurizer Relief Tank Check Valve 3-519 5610-M-3065-1 D6 2 A/C 0.75 SCK SA A SYS C AT-01 App-J CC RR VR-01 RJ-05 CO RR VR-01 RJ-05 TPv-01 Valve Name: N2 Supply to PRT Stop Check Valve CV-3-855 5610-M-306S1 E6 2 A 1.0 GA AO A C C AT-01 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: N2 Supply to SI Accumulators Isolation Valve 4-3449 5610M-3065-1 A6 2 A 0.375 GL MAN P LC C AT-01 App-J Valve Name: N2 to RCDT PCV-^.-1014 Sensing Line Isolation Valve 44639 5610-M-3065-1 B6 2 A 0.75 DIA MAN P LC C AT-01 App-J Valve Name: N2 Supply to RCDT Isolation Valve 44656 5610-M065-1 B7 2 A 1.0 DIA MAN P LC C AT-01 App-J Valve Name: N2 Supply to RCDT Isolation Valve 4.518 5610M-3065-1 A7 2 A/C 0.75 CK SA A SYS C AT-01 App-J CC RR VR-01 RJ-05 CO RR VR-01 RJ-05 TPv-01 Valve Name: N2 Supply to Pressurizer Relief Tank Check Valve Revision Date: 2/11/2004 Page 217

Turkey Point Nuclear Plant IST Program Plan Nitrogenand Hydrogen(065) Valve Table P&8D Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

4-519 5610-M-3065-1 A6 2 A/C 0.75 CK SA A SYS C AT-01 App-J CC RR VR-01 RJ-05 CO RR VR-01 RJi- TPv-41 Valve Name: N2 Supply to PRT Stop Check Valve CV4-855 5610-M-3065-1 E3 2 A 1.0 GA AO A C C AT-1 App-J BTC M3 FC M3 TPv-04 PIT Y2 Valve Name: N2 Supply to Si Accumulators Isolation Valve Revision Date: 2/111/2004 i DPage 218

Turkey Point Nuclear Plant IST Program Plan Containment Spray (068) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

ag Valve Ta P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-883M 5613-M-3068-1 C5 2 A 1.0 GL MAN P LC C AT-01 App-J Valve Name: Containment Spray Pump 3A Test Line Isol 3-883N 5613-M-3068-1 E5 2 A 1.0 GL MAN P IC C AT-01 App-J Valve Name: Containment Spray Pump 3B Test Line Isol K> 3-890A 5613-M-3068-1 D6 2 A/C 6.0 CK SA A C OC AT-01 App-J CCD CM TPv-02 COD CM TPv-02 Valve Name: Containment Spray Pump Diacharge Check Valve 3-890B 5613-M3068-1 G6 2 A/C 6.0 CK SA A C OC AT-01 App-J CCD CM TPv-02 COD CM TPv-02 Valve Name: Containment Spray Pump Diacharge Check Valve MOV-3-80A 5613-3068-1 D5 2 A 6.0 GA MO A C OIC AT-01 App-J BTC M3 BTO M3 PIT Y2 Valve Name: Containment Spray Pump Discharge Isolation Valve MOV.3-880B 5613-M-3068-1 G5 2 A 6.0 GA MO A C O/C AT-01 App-J BTC M3 BTO M3 PiT Y2 Valve Name: Containment Spray Pump Discharge Isolation Valve

_> - RV.3-871 56134-3068-1 C2 2 C 0.75 RV SA A C OIC RT Y10 Valve Name: Containment Spray Pump Suction Relief Valve 4-883M 561443068-1 C5 2 A 1.0 GL MAN P IC C AT-41 App-J Valve Name: Containment Spray Pump Test Line Isolation Valve 4-883N 5614-M 30681 D5 2 A 1.0 GL MAN P LC C AT-01 App-J Valve Name: Containment Spray Pump Test Line Isolation Valve 4-890A 5614-M-3068-1 C6 2 A/C 6.0 CK SA A C OC AT-01 App-J CCD CM TPv-02 COD CM TPv-02 Valve Name: Containment Spray Pump Diacharge Check Valve Revision Date: 2/1112004 Page 219

Turkey Point Nuclear Plant IST Program Plan Containment Spray (068) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

4-8908 5614-M-3068-1 F6 2 A/C 6.0 CK SA A C O/C AT-01 App-J CCD CM TPv-02 COD CM TPv-02 Valve Name: Containment Spray Pump Diacharge Check Valve MOV4-880A 5614-M-3068-1 C5 2 A 6.0 GA MO A C O/C AT-01 App-J BTC M3 BTO M3 PIT Y2 Valve Name: Containment Spray Pump Discharge Isolation Valve MOV-4880B 5614-M-3068-1 F5 2 A 6.0 GA MO A C O/C AT-01 App-J BTC M3 BTO M3 PIT Y2 Valve Name: Containment Spray Pump Discharge Isolation Valve

\ ~~RV.4-711 5014-M-3068-1 G2 2 C 0.75 RV SA A C O/C RT Y10 Valve Name: Containment Spray Pump Suction Relief Valve 211 1i2004 Page 220 Revision Date:

Revision Date: 2/11/2004 Page 220

Turkey Point Nuclear Plant IST Program Plan Main Steam System (072) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-10-004 5613-M-3072-1 G7 SR C 26.0 CK SA A SYS C CC CS CSJ-12 CO M3 TPv-01 Valve Name: Main Steam Header A Check Valve 3-10-005 5613-M-3072-1 D7 SR C 26.0 CK SA A SYS C CC CS CSJ-12 CO M3 TPv-01 Valve Name: Main Steam Header B Check Valve 3-10-006 5613-M-3072-1 87 SR C 26.0 CK SA A SYS C CC CS CSJ-12 CO M3 TPv-01 Valve Name: Main Steam Header C Check Valve CV-3-1606 5613-M4072-1 F4 2 B 6.00 GL AO A C OC BTC CS CSJ-13 BTO CS CSJ-13 FC CS CSJ-13 TPv-04 Valve Name: Atmosheric Steam Dump A CV-3A1607 5613-M072-1 D4 2 B 6.00 GL AO A C O/C BTC CS CSJ-13 BTO CS CSJ-1 3 FC CS CSJ-13 TPvO04 Valve Name: Atmosheric Steam Dump B CV-3-1608 5613-M-3072-1 B4 2 B 6.00 GL AO A C O/C BTC CS CSJ-13 BTO CS CSJ-13 FC CS CSJ-13 TPv-04 Valve Name: Atmosheric Steam Dump C MOV-3t1400 561343072-1 F6 2 B 2.00 GL MO A C C BTC M3 PIT M3 Valve Name: MSIV A Bypass Isolation Valve MOV-3-1401 5613-M43072-1 D6 2 B 2.00 GL MO A C C BTC M3 PIT M3 Valve Name: MSIV B Bypass Isolation Valve MOV-3-1402 5613-M-3072-1 86 2 B 2.00 GL MO A C C BTC M3 PIT M3 Valve Name: MSIV C Bypass Isolation Valve Revision Date: 2111/2004 Page 221

Turkey Point Nuclear Plant IST Program Plan Main Steam System (072) Valve Table P&iD Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

POV.3-2604 56134M-3072-1 G6 2 B 26.0 CK AO A 0 C BTC CS CSJ-30 PIT Y2 Valve Name: Main Steam Header A Isolation Valve POV.3-2605 5613-M3072-1 D6 2 B 26.0 CK AO A 0 C BTC CS CSJ-30 PIT Y2 Valve Name: Main Steam Header B Isolation Valve POV.3-2606 5613-M072-1 B6 2 B 26.0 CK AO A 0 C BTC CS CSJ-30 PIT Y2 Valve Name: Main Steam Header C Isolation Valve RV-3-1400 5613-M072-1 G5 2 B 6.00 RV SA A C OC RT Y5 Valve Name: Main Steam Header A - Safety Valve RV-3.1401 5613-M-3072-1 G5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header A - Safety Valve RV-3-1402 5613-M-3072-1 H5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header A - Safety Valve RV.3*1403 5613M4072-1 F5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header A - Safety Valve RV-3-1405 5613-M-3072-1 E5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header B - Safety Valve RV-3-1406 5613-M072-1 D5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header B - Safety Valve RV-3-1407 5613-M072-1 E5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header B - Safety Valve RV-3-1408 5613-M-3072-1 D5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header B - Safety Valve RV-3-1410 5613-M072-1 B5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header C - Safety Valve RV-31411 5613-M-3072-1 B5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header C - Safety Valve Revision Date: 2/11/2004 Page 222

Turkey Point Nuclear Plant IST Program Plan Main Steam System (072) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV-3-1412 5613-M-3072-1 C5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header C - Safety Valve RV-3-1413 5613-M-3072-1 A5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header C - Safety Valve 4-10-004 5614-M-3072-1 G6 SR C 26.0 CK SA A SYS C CC CS CSJ-12 CO M3 TPv-01 Valve Name: Main Steam Header A Check Valve 4.10-005 561443072-1 D6 SR C 26.0 CK SA A SYS C CC CS CSJ-12 CO M3 TPv-01 Valve Name: Main Steam Header B Check Valve 4-10-006 5614-3072-1 B6 SR C 26.0 CK SA A SYS C CC CS CSJ-12 CO M3 TPv-01 Valve Name: Main Steam Header C Check Valve CV-4.1606 561443072-1 F4 2 B 6.00 GL AO A C O/C BTC CS CSJ-13 BTO CS CSJ-13 FC CS CSJ-13 TPv-04 Valve Name: Atmosheric Steam Dump A CV-4.1607 5614-3072-1 D4 2 B 6.00 GL AO A C O/C BTC CS CSJ-13 BTO CS CSJ-13 FC CS CSJ-13 TPv-04 Valve Name: Atmosheric Steam Dump B CV4.11608 5614-M-3072-1 B4 2 B 6.00 GL AO A C OIC BTC CS CSJ-13 BTO CS CSJ-13 FC CS CSJ-13 TPv-04 Valve Name: Atmosheric Steam Dump C MOV4-1400 561443072-1 F6 2 B 2.00 GL MO A C C BTC M3 PIT M3 Valve Name: MSIV A Bypass Isolation Valve MOV-4-1401 5614-3072-1 D6 2 B 2.00 GL MO A C C BTC M3 PIT M3 Valve Name: MSIV B Bypass Isolation Valve Revision Date: 2/11/2004 Page 223

Turkey Point Nuclear Plant IST Program Plan Main Steam System (072) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

MOV4-1402 5614-M43072-1 A6 2 B 2.00 GL MO A C C BTC M3 PIT M3 Valve Name: MSIV C Bypass Isolation Valve POV4-2604 561443072-1 G6 2 B 26.0 CK AO A 0 C BTC CS CSJ-30 PIT Y2 Valve Name: Main Steam Header A Isolation Valve POV4-2605 5614-M-3072-1 D6 2 B 26.0 CK AO A 0 C BTC CS CSJ-30 PIT Y2 Valve Name: Main Steam Header B Isolation Valve POV4-2606 561443072-1 B6 2 B 26.0 CK AO A 0 C BTC CS CSJ-30 PIT Y2 Valve Name: Main Steam Header C Isolation Valve RV4.1400 5614-M-3072-1 G5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header A - Safety Valve RV4-1401 5614-M43072-1 G5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header A - Safety Valve RV4-1402 5614-M072-1 H5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header A - Safety Valve RV4.1403 561443072-1 F5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header A - Safety Valve RV4-1405 5614-M-3072-1 E5 2 B 6.00 RV SA A C 0/C RT Y5 Valve Name: Main Steam Header B - Safety Valve RV4.1406 561443072-1 D5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header B - Safety Valve RV441407 5614-M-3072-1 E5 2 B 6.00 RV SA A C O/C RT Y5 Valve Name: Main Steam Header B - Safety Valve RV441408 5614-M-3072-1 D5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header B - Safety Valve Revision Date: 2/11/2004 Page 224

Turkey Point Nuclear Plant IST Program Plan Main Steam System (072) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

RV-4 1410 5614-M-3072-1 B5 2 B 6.00 RV SA A C OC RT Y5 Valve Name: Main Steam Header C - Safety Valve RV-4-1411 56144-3072-1 B5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header C - Safety Valve RV-4-1412 5614-M-3072-1 C5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header C - Safety Valve RV-4.1413 5614-M-3072-1 A5 2 B 6.00 RV SA A C OIC RT Y5 Valve Name: Main Steam Header C - Safety Valve Page 225 Revision Date:

Revision Date: 2/11/2004 2/11/2004 Page 225

Turkey Point Nuclear Plant IST Program Plan Blowdown (074) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV-346275A 5613-M-30744 G2 2 B 6.0 GL AO A 0 C BTC M3 PIT Y2 Valve Name: 3A Steam Generator Blowdown Stop Valve CV-3-6275B 5613-M-30744 E2 2 B 6.0 GL AO A 0 C BTC M3 PIT Y2 Valve Name: 3B Steam Generator Blowdown Stop Valve CV-346275C 56134-30744 C2 2 B 6.0 GL AO A 0 C BTC M3 PIT Y2 Valve Name: 3C Steam Generator Blowdown Stop Valve MOV.3-1425 5613-M4032-1 D2 2 B 1.0 GA MO A 0 C BTC M3 PIT Y2 Valve Name: 3C Steam Generator.Liquid Sample Valve MOV-3-1426 5613-M43032-1 C2 2 B 1.0 GA MO A 0 C BTC M3 PIT Y2 Valve Name: 3B Steam Generator Liquid Sample Valve MOV.3.1427 561343032-1 A2 2 B 1.0 GA MO A 0 C BTC M3 PIT Y2 Valve Name: 3A Steam Generator Liquid Sample Valve CV4-6275A 5614-M0744 G2 2 B 6.0 GL AO A 0 C BTC M3 PIT Y2 Valve Name: 4A Steam Generator Blowdown Stop Valve CV-4-6275B 5614-M-30744 E2 2 B 6.0 GL AO A 0 C BTC M3 PIT Y2 Valve Name: 4B Steam Generator Blowdown Stop Valve CV46275C 5614-M-3074-4 C2 2 B 6.0 GL AO A 0 C BTC M3 PIT Y2 Valve Name: 4C Steam Generator Blowdown Stop Valve MOV-4-1425 561443032-1 D2 2 B 1.0 GA MO A 0 C BTC M3 PIT Y2 Valve Name: 4C Steam Generator Liquid Sample Valve Revision Date: 2V1112004 Page 226

Turkey Point Nuclear Plant IST Program Plan B lowdown (074) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

MOV4*1426 5614-M-3032-1 C3 2 B 1.0 GA MO A 0 C BTC M3 PIT Y2 Valve Name: 4B Steam Generator Liquid Sample Valve MOV.4-1427 5614-M-3032-1 A2 2 B 1.0 GA MO A 0 C BTC M3 PIT Y2 Valve Name: 4A Steam Generator Liquid Sample Valve Revision Date: 2/11/2004 Page 227

Turkey Point Nuclear Plant IST Program Plan Main Feedwater (074a) -Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-20-137 5613-M-3074-3 G6 2 C 0.50 CK SA A SYS C CC M3 CO M3 TPv41 Valve Name: A SIG FW chem Injection Check Valve 3-20.237 5613-M-3074-3 E6 2 C 0.50 CK SA A SYS C CC M3 CO M3 TPv-01 Valve Name: B SIG FW chem Injection Check Valve 3-20.337 5613-M3074-3 B6 2 C 0.50 CK SA A SYS C CC M3 CO M3 TPv-01 Valve Name: C SIG FW chem Injection Check Valve FCV-3-478 561341-3074-3 G4 2 B 12.0 GL AO A 0 C BTC CS CSJ-17 FC CS CSJ-17 PIT Y2 Valve Name: A SIG FW Control Valve FCV-3-479 5613-M3074-3 H3 2 B 4.0 GA AO A C C BTC CS CSJ-18 FC CS CSJ-18 TPv-04 PIT Y2 Valve Name: A SIG FW FCV Bypass Valve FCV-3-488 5613-M-3074-3 D4 2 B 12.0 GL AO A 0 C BTC CS CSJ-17 FC CS CSJ-17 PIT Y2 Valve Name: B SIG FW Control Valve FCV-3-489 561343074-3 E3 2 B 4.0 GA AO A C C BTC CS CSJ-18 FC CS CSJ-18 TPv.04 PIT Y2 Valve Name: B SIG FW FCV Bypass Valve FCV-3-498 5613.M-3074-3 64 2 B 12.0 GL AO A 0 C BTC CS CSJ-17 FC CS CSJ-17 PIT Y2 Valve Name: C SIG FW Control Valve FCV-3-499 5613-M-3074-3 C3 2 B 4.0 GA AO A C C BTC CS CSJ-18 FC CS CSJ-18 TPv-04 PIT Y2 Valve Name: C SIG FW FCV Bypass Valve Revision Date: 2/1112004 Page 228

Turkey Point Nuclear Plant IST Program Plan Main Feedwater (074a) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

4-20-137 5614-M-3074-3 G6 2 C 0.50 CK SA A SYS C CC M3 CO M3 TPv-01 Valve Name: A SIG FW chem Injection Check Valve 4-20-237 5614-M-3074-3 D6 2 C 0.50 CK SA A SYS C CC M3 CO M3 TPv-01 Valve Name: B SIG FW chem Injection Check Valve 4-20-337 5614M-3074-3 B6 2 C 0.50 CK SA A SYS C CC M3 CO M3 TPv-01 Valve Name: C SIG FW chem Injection Check Valve FCV4478 5614-M-3074-3 G4 2 B 12.0 GL AO A 0 C BTC CS CSJ-17 FC CS CSJ-17 PIT Y2 Valve Name: A SIG FW Control Valve K. FCV-4-479 56144M-3074-3 H3 2 B 4.0 GA AO A C C BTC CS CSJ-18 FC CS CSJ-18 TPv-04 PIT Y2 Valve Name: A SIG FW FCV Bypass Valve FCV-4488 5614-M-3074-3 D4 2 B 12.0 GL AO A 0 C BTC CS CSJ-17 FC CS CSJ-17 PIT Y2 Valve Name: B SIG FW Control Valve FCV.4489 56144M-3074-3 E3 2 B 4.0 GA AO A C C BTC CS CSJ-18 FC CS CSJ-18 TPv-04 PIT Y2 Valve Name: B SIG FW FCV Bypass Valve FCV4.498 5614-M-3074-3 B4 2 B 12.0 GL AO A 0 C BTC CS CSJ-17 FC CS CSJ-17 PIT Y2 Valve Name: C SIG FW Control Valve FCV-4499 5614-M-3074-3 C3 2 B 4.0 GA AO A C C BTC CS CSJ-18 FC CS CSJ-18 TPv-04 PIT Y2 Valve Name: C SIG FW FCV Bypass Valve Revislon Date: 2/11/2004 Page 229

Turkey Point Nuclear Plant IST Program Plan Auxiliary Feedwater (075) Valve Table P&iD Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.20-143 5610-M-3075-2 B7 3 C 6.0 CK SA A SYS O/C CC M3 VR-03 TPv-01 CO M3 Valve Name: AFW Pump A Discharge Check Valve 20-243 5610-M-3075-2 D7 3 C 6.0 CK SA A SYS O/C CC M3 CO M3 Valve Name: AFW Pump B Discharge Check Valve 20-343 5610-3075-2 F7 3 C 6.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: AFW Pump C Discharge Check Valve AFSS-003B 5610-M-3075-1 D4 3 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: AFW Pump B Turbine Steam Supply Check Valve AFSS-003C 5610-M-3075-1 F4 3 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: AFW Pump C Turbine Steam Supply Check Valve RV-6401A 561043075-2 A4 3 C 1.0 RV SA A C O/C RT Y10 Valve Name: AFW Pump A LO Cooler Cooling Water Relief Valve RV-6401B 561D-M-3075-2 C4 3 C 1.0 RV SA A C OIC RT Y10 Valve Name: AFW Pump B LO Cooler Cooling Water Relief Valve RV-6401C 5610-M3075-2 F4 3 C 1.0 RV SA A C OIC RT Y10 Valve Name: AFW Pump C LO Cooler Cooling Water Relief Valve 3-10-083 5613-M-3075-1 C7 3 C 4.0 CK SA A SYS 0 CCD CM TPv-0102 COF CM TPv-02 Valve Name: AFW A Train I Steam Supply Check Valve 3-10-087 561343075-1 F7 3 C 4.0 CK SA A C 0 CCD CM TPv-41,02 COD CM TPv-02 Valve Name: AFW Train I Steam Supply Check Valve 3-10-375 561343075-1 G3 2 C 3.0 CK SA A SYS 0 CCD CM TPv-01,02 COF CM TPv-02 Valve Name: AFW Train 2 Steam Supply Check Valve Revision Date: 2/11/2004 Page 230

Turkey Point Nuclear Plant IST Program Plan Auxiliary Feedwater (075) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-10-376 5613-M-3075-1 E3 2 C 3.0 CK SA A SYS 0 CCD CM TPv-01,02 COF CM TPv-02 Valve Name: AFW Train 2 Steam Supply Check Valve I

3-10-377 5613 3075-1 C3 2 C 3.0 CK SA A SYS 0 CCD CM TPv-01,02 COF CM TPv42 Valve Name: AFW Train 1 Steam Supply Check Valve I

3-10-381 5613-M-3075-1 G4 3 C 4.0 CK SA A SYS O/C CCF CM CSJ-01 TPv-02 COF CM TPv-02 Valve Name: AFW Steam Supply Check Valve I

3-10-382 5613M3075-1 E4 3 C 4.0 CK SA A SYS OIC CCF CM CSJ-01 TPv-02 COF CM TPv-02 Valve Name: AFW Steam Supply Check Valve I

3-10-383 5613-M-3075-1 C4 3 C 4.0 CK SA A SYS O/C CCF CM CSJ-01 TPv-02 COF CM TPv-02 Valve Name: AFW Steam Supply Check Valve I

3-20-140 5613-M-3075-2 F7 2 C 4.0 CK SA A SYS 0 CCR CM TPv-01.02 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve I

3-20-142 5613-M-3075-2 C2 3 B 6.0 GA MAN A LO O/C BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: AFW Pmp A Train I Disch Isol I

3-20-240 5613-3075-2 D7 2 C 4.0 CK SA A SYS 0 CCR CM TPv-01.02 COF CM TPv02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve I

3-20-340 5613-M-3075-2 B7 2 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve I

3-20-456 5610M3075-2 A6 3 C 2.0 CK SA A SYS O/C CC M3 CO M3 Valve Name: AFW Pump Recirculatlon to CST Check Valve Revision Date: 2/11/2004 Page 231

Turkey Point Nuclear Plant IST Program Plan Auxiliary Feedwater (075) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

AFPD-3-010 5613-M-3075-2 H3 3 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve AFPD-3-012 5613-M-3075-2 E3 3 C 4.0 CK SA A SYS 0 CCR CM TPv-0102 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve AFPD-3-014 561343075-2 C3 3 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve AFSS-3-005 561343075-1 B6 3 C 4.0 CK SA A SYS 0 CC M3 TPv-01 CO M3 Valve Name: AFW Pump Turbine Steam Supply Check Valve AFWU-3-017 5610-M-3075-2 A6 3 C 2.0 CK SA A SYS O/C CCD CM TPv-06,02 COD CM TPv-06,02 Valve Name: AFW Pump LO Cooling Water Return Check Valve CV-3-2816 5613-M-3075-2 F7 2 8 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train I SIG A Feed Flow Control Valve CV-3-2817 5613-M-3075-2 D7 2 B 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train 1 SIG B Feed Flow Control Valve CV-3-2818 5613-M-3075-2 B7 2 B 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train I SIG C Feed Flow Control Valve CV-3-2831 561343075-2 G7 2 B 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train 2 AFW Flow to 3A SIG Revision Date: 2/11/2004 Page 232

Turkey Point Nuclear Plant IST Program Plan Auxiliary Feedwater (075) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

CV-3-2832 5613-M-3075-2 E7 2 B 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train 2 AFW Flow to 3B SIG CV-3-2833 5613-M-3075-2 C7 2 B 4.0 GL AO A C OIC BTC M3 BTO M3 PIT Y2 Valve Name: Train 2 AFW Flow to 3C SIG MOV-3-1403 5613-M-3075-1 G3 2 B 4.0 GL MO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: SIG A Stm Supply to Aux Fd Pumps MOV-3-1404 5613-M-3075-1 E3 2 B 4.0 GL MO A C OIC BTC M3 BTO M3 PIT Y2 Valve Name: SIG B Stm Supply to Aux Fd Pumps MOV-3-1405 5613-M-3075-1 C3 2 B 4.0 GL MO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: SIG C Stm Supply to Aux Fd Pumps RVD-3-001 561343075-3 A7 SR D RPD SA A C 0 RT Y5 Valve Name: N2 Supply Header Rupture Disk RVD-3-002 5613-M-3075-3 F7 SR D RPD SA A C 0 RT Y5 Valve Name: N2 Supply Header Rupture Disk 4-10-083 561443075-1 A7 3 C 4.0 CK SA A SYS 0 CCD CM TPv-01,02 COF CM TPv-02 Valve Name: AFW A Train I Steam Supply Check Valve 4-10-087 561443075-1 D7 3 C 4.0 CK SA A C 0 CCD CM TPv-01,02 COD CM TPv42 Valve Name: AFW Train 1 Steam Supply Check Valve Revision Date: 2/11/2004 Page 233

Turkey Point Nuclear Plant IST Program Plan Auxiliary Feedwater (075) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&8D Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

4-10-375 5614-M-3075-1 F4 2 C 3.0 CK SA A SYS 0 CCD CM TPv41,02 COF CM TPv-02 Valve Name: AFW Train 2 Steam Supply Check Valve 4-10-376 5614-M-3075-1 D3 2 C 3.0 CK SA A SYS 0 CCD CM TPv-01,02 COF CM TPv-02 Valve Name: AFW Train 2 Steam Supply Check Valve 4-10-377 5614-M-3075-1 B3 2 C 3.0 CK SA A SYS 0 CCD CM TPv-01,02 COF CM TPv-02 Valve Name: AFW Train 2 Steam Supply Check Valve 4-10-381 5614-M-3075-1 F4 3 C 4.0 CK SA A SYS O/C CCF CM CSJ-01 TPv-02 COF CM TPv-02 Valve Name: AFW Steam Supply Check Valve 4-10-382 5614-M-3075-1 D4 3 C 4.0 CK SA A SYS OC CCF CM CSJ-01 TPv402 COF CM TPv-02 Valve Name: AFW Steam Supply Check Valve 4.10-383 5614-M-3075-1 B4 3 C 4.0 CK SA A SYS O/C CCF CM CSJ-01 TPv-02 COF CM TPv-02 Valve Name: AFW Steam Supply Check Valve 4-20-140 5614-M3075-2 F7 2 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv402 Valve Name: Auxiliary Feedwater Pump S/G Supply Check Valve 4.20-142 5614-M-3075-2 B2 3 B 6.0 GA MAN A LO O/C BTC Y2 TPv-1 BTO Y2 TPv-11 Valve Name: AFW Pmp A Train I Disch Isol 4-20-240 5614-M-3075-2 D7 2 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve 4-20-340 5614M-3075-2 B7 2 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve Revision Date: 2/11/2004 Page 234

Turkey Point Nuclear Plant

[ST Program Plan Auxiliary Feedwater (075) Valve Table PUdD Safety Valve Act. Active / Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

4-20-458 5610M3075-2 G6 3 C 2.0 CK SA A SYS OIC CC M3 CO M3 Valve Name: AFW Pump Recirculation to CST Check Valve AFPD4-009 5614-M-3075-2 H3 3 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve AFPD-4-011 5614M-3075-2 E3 3 C 4.0 CK SA A SYS 0 CCR CM TPv-01,02 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve AFPD4-013 5614-M-3075-2 C3 3 C 4.0 CK SA A SYS 0 CCR CM TPv41,02 COF CM TPv-02 Valve Name: Auxiliary Feedwater Pump SIG Supply Check Valve AFSS-4-005 5613-M-3075-1 F5 3 C 4.0 CK SA A SYS 0 CC M3 Tpv-01 CO M3 Valve Name: AFW Pump Turbine Steam Supply Check Valve AFWU44016 5610-M-3075-2 G6 3 C 2.0 CK SA A SYS OIC CCD CM TPv-06,02 COD CM TPv-06,02 Valve Name: AFW Pump LO Cooling Water Return Check Valve CV4-2816 5614-M-3075-2 F7 2 B 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train I SiG A Feed Flow Control Valve CV4-2817 5614-M-3075-2 D7 2 B 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train I SIG B Feed Flow Control Valve CV4-2818 5614-M-3075-2 B7 2 B 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train I SIG C Feed Flow Control Valve Revision Date: 2/1112004 Page 235

Turkey Point Nuclear Plant

[ST Program Plan Auxiliary Feedwater (075) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

CV412831 5614-M-3075-2 G7 2 B 4.0 GL AO A C OIC BTC M3 BTO M3 PIT Y2 Valve Name: Train 2 AFW Flow to 4A SIG CV-4.2832 5614-M3075-2 E7 2 B 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train 2 AFW Flow to 4B SIG CV-4-2833 5614M-3075-2 C7 2 B 4.0 GL AO A C O/C BTC M3 BTO M3 PIT Y2 Valve Name: Train 2 AFW Flow to 4C S/G MOV4-1403 5614-M-3075-1 F3 2 B 4.0 GL MO A C OIC BTC M3 BTO M3 PIT Y2 Valve Name: SIG A Stm Supply to Aux Fd Pumps MOV-4.1404 5614-M-3075-1 D3 2 B 4.0 GL MO A C OIC BTC M3 BTO M3 PIT Y2 Valve Name: SIG B Stm Supply to Aux Fd Pumps MOV.4.1405 5614-M-3075-1 B3 2 B 4.0 GL MO A C OIC BTC M3 BTO M3 PIT Y2 Valve Name: SIG C Stm Supply to Aux Fd Pumps RVD4001 5614-M3075-3 A7 SR D RPD SA A C 0 RT Y5 Valve Name: N2 Supply Header Rupture Disk RVD-4-002 5614-M-3075-3 F7 SR D RPD SA A C 0 RT Y5 Valve Name: N2 Supply Header Rupture Disk Revision Date: 2111/2004 Page 236

Turkey Point Nuclear Plant IST Program Plan Post Accident Hydrogen Monitors (094a) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&8D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

PAHM-3-401A 5613-M-3094-1 B3 2 A 0.75 GL MAN A LC O/C AT-01 App4J BTC Y2 TPv-11 BTO Y2 TPv-1 1 Valve Name: Hydrogen Monitor Outlet Isolation PAHM-34001B 5613M-3094-1 B2 2 A 0.75 GL MAN A LC O/C AT.01 App-J BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: Hydrogen Monitor Outlet Isolation PAHM-3-002A 5613-M3094-1 D4 2 A 0.75 GL MAN A LC O/C AT-01 App-J BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: Hydrogen Monitor Inlet Isolation PAHM-3-002B 5613-M-3094-1 C3 2 A 0.75 GL MAN A LC 0/C AT-01 App-J BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: Hydrogen Monitor Outlet Isolation PAHM-401A 5613-M-3094-1 B2 2 A 0.75 GL MAN A LC O/C AT-01 App-J BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: Hydrogen Monitor Outlet Isolation PAHM4001B 5613-M-3094-1 B3 2 A 0.75 GL MAN A LC OC AT-01 App-J BTC Y2 TPv-11 BT0 Y2 TPv-1 1 Valve Name: Hydrogen Monitor Outlet Isolation PAHM44002A 5614-M-3094-1 D5 2 A 0.75 GL MAN A LC O/C AT-01 App4J BTC Y2 TPv.11 BTO Y2 TPv-11 Valve Name: Hydrogen Monitor Inlet Isolation PAHM-4-002B 5614-4-3094-1 C3 2 A 0.75 GL MAN A LC 0/C AT-01 App4 BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: Hydrogen Monitor Outlet Isolation Revision Date: 2/11/2004 Page 237

Turkey Point Nuclear Plant IST Program Plan Post Accident Sampling (094c) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

3-11-003 5613-M-3094-1 B2 2 A/C 1.00 CK SA A SYS O/C AT-01 App-J CC RR RJ-11 TPv-08 CO RR RJ-1 1 Valve Name: Cont. Air Monitor Exhaust Check Valve HV.3-001 5613-M-3094-1 H3 2 A 2.00 DIA MAN A LC OC AT-01 App-J BTC Y2 TPv-1 1 BTO Y2 TPv-11 Valve Name: PACV Penetration 16 - Upstream Isolation HV-3-002 5613-M-3094-1 H4 2 A 2.00 DIA MAN A LC OC AT-01 Appo BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: PACV Penetration 16 - Downstream Isolation HV3-003 5613-M-3094-1 G2 2 A 2.00 DIA MAN A LC OC AT-01 AppJ BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: PACV Penetration 53 - Upstream Isolation HV-34004 5613M3094-1 G4 2 A 2.00 DIA MAN A LC 01C AT-C1 App-J BTC Y2 TPv- 1I BTO Y2 TPv-11 Valve Name: PACV Penetration 63 - Downstream Isolation SV-3-2911 5613-M3094-1 A3 2 A 1.00 GL SO A 0 O/C AT-01 App-J BTC M3 BTO M3 FC M3 TPv-04 PIT App-J VR-02 Valve Name: Solenoid Valve for Cont. Air Monitor Inlet SV-3-2912 5613-M-3094-1 83 2 A 1.00 GL SO A 0 O/C AT-C1 App-J BTC M3 BTO M3 FC M3 TPv-04 PIT App-J VR.02 Valve Name: Solenoid Valve for Cont. Air Monitor Outlet Revision Date: 2/11/2004 Page 238

Turkey Point Nuclear Plant IST Program Plan Post Accident Sampling (094c) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

SV-3-2913 5613-M3094-1 A3 2 A 1.00 GL SO A 0 OC AT-01 App-J BTC M3 BTO M3 FC M3 TPv-04 PIT App-J VR402 Valve Name: Solenoid Valve for Cont. Air Monitor Inlet 4-11-003 561443094-1 B2 2 A/C 1.00 CK SA A SYS OIC AT-01 App-J CC RR RJ-1 I TPv-08 CO RR RJ-11 Valve Name: Cont Air Monitor Exhaust Check Valve HV4-001 5614M-3094-1 H2 2 A 2.00 DIA MAN A LC OIC AT-01 App-J BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: PACV Penetration 16 - Upstream Isolation HV4-002 561443094-1 H4 2 A 2.00 DIA MAN A LC OC AT-01 App-J BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: PACV Penetration 16 - Downstream Isolation HV-4003 5614-M3094-1 G2 2 A 2.00 DIA MAN A LC O/C AT-01 App-J BTC Y2 TPv-11 BTO Y2 TPv-1 I Valve Name: PACV Penetration 51 - Upstream Isolation HV4-004 5614-M-3094-1 G4 2 A 2.00 DIA MAN A LC OIC AT-01 App-J BTC Y2 TPv-11 BTO Y2 TPv-11 Valve Name: PACV Penetration 51 - Downstream Isolation SV-4-2911 561443094-1 A3 2 A 1.00 GL SO A 0 OC AT-01 App-J BTC M3 BTO M3 FC M3 TPv-04 PIT App-J VR-02 Valve Name: Solenoid Valve for Cont. Air Monitor Inlet Revision Date: 2/11/2004 Page 239

Turkey Point Nuclear Plant IST Program Plan Post Accident Sampling (094c) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&8D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

SV-4-2912 5614-M-3094-1 B3 2 A 1.00 GL SO A 0 O/C AT-4 App-J BTC M3 BTO M3 FC M3 TPvO4 PIT App-J VR-02 Valve Name: Solenoid Valve for Cont. Air Monitor Outlet SV-4-2913 5614-M-3094-1 A3 2 A 1.00 GL SO A 0 01C AT-01 App-J BTC M3 BTO M3 FC M3 TPv-04 PIT App-J VR-02 Valve Name: Solenoid Valve for Cont. Air Monitor Inlet Riso Date:Dae .1120 Pa_ 240 __,_

Revision 2/1112004 Page 240

Turkey Point Nuclear Plant IST Program Plan Post Accident Hydrogen Control (094d) VTaive Table P&D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&8D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

4678 5613M3094-1 F7 NS B 2.00 DIA MAN A LC 0 STO Y2 TPv-11 Valve Name: PACV Filter Train to Waste Gas Release Hdr. Isol HV-3-18 56134M3094-1 G5 NS B 2.00 GA MAN A LC 0 BTO Y2 TPv-11 Valve Name: Hydrogen Recombiner Inlet Isol.

HV7 5613-M-3094-1 F5 NS B 3.00 DIA MAN A C 0 BTO Y2 TPv-11 Valve Name: PACV Filter Inlet Isol.

HV-77 5613M3094-1 F7 NS B 3.00 DIA MAN A C 0 BTO Y2 TPv-11 Valve Name: PACV Filter Outlet Isol.

HV8 5613-3094-1 F7 NS B 2.00 DIA MAN A LC 0 BTO Y2 TPv-11 Valve Name: PACV Filter to Waste Gas Comp.

HV-4.18 5614M4094-1 G5 NS B 2.00 GA MAN A LC 0 BTO Y2 TPv-11 Valve Name: Hydrogen Recombiner Inlet Isol.

Revision Date: 2J11/2004 Page 241

Turkey Point Nuclear Plant IST Program Plan Breathing Air (101) -Valve Table P81D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Tag P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BA-3.201 5613M3101-1 D3 2 A/C 2.5 CK SA P C C AT-01 AppJ VR-01 TPv-10 Valve Name: Containment Breathing Air Isolation Check Valve CV-3-6165 5613-MW3101-1 D2 2 A 2.5 GA AO P LC C AT-01 App-J PIT Y2 Valve Name: Containment Breathing Air Isolation Valve BA4-201 561443101-1 03 2 A/C 2.5 CK SA P C C AT-01 App-J VR-01 TPv-10 Valve Name: Containment Breathing Air Isolation Check Valve CV-46165 5614-M-3101-1 D2 2 A 2.5 GA AO P LC C AT-01 App-J PIT Y2 Valve Name: Containment Breathing Air Isolation Valve Date:

Revision Date: 2/11/2004 Page 242 Revision 2111/2004 Page 242

ATTACHMENT 2 L-2004-043