Text

Inservice Test Program Update and Associated Relief Requests for Second Ten-Year Interval
	ML061870144
Person / Time
Site:	Watts Bar
Issue date:	06/30/2006
From:	Pace P; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML061870144 (76)
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4 Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 JUN 30 2OD 10 CFR 50.50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

In the Matter of ) Docket No. 50-390 Tennessee Valley Authority )

WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - INSERVICE TEST (IST)

PROGRAM UPDATE AND ASSOCIATED RELIEF REQUESTS FOR SECOND TEN-YEAR INTERVAL The purpose of this letter is to provide WBN's updated IST Program and the associated Requests for Relief, PV-01, PV-02, PV-03, and PV-04 for WBN's Second 10-Year Inspection Interval for pumps and valves. The requests for relief are being submitted to NRC for review and approval in accordance with 10 CFR 50.55a.

The IST Program is provided in the Enclosure. The pump test program contains two requests for relief:

PV Reference Values for Vibration Points on Pumps PV Measuring Pump Flow Rates of the Screen Wash Pumps.

Both of these Requests for Relief were approved in WBN's First Ten Year Testing Interval in WBN's Supplemental Safety Evaluation Report (SSER) 14, (NUREG-0847) as PV-01 and PV-04, respectively.

The valve test program also contains two requests for relief:

PV Reactor Coolant System Head Vent Stroke Time PV Essential Raw Cooling Water Isolation Valves Stroke Times.

Both of these Requests for Relief were approved in WBN's First Ten Year Testing Interval. PV-03 was originally designated as PntdonrecycWe pape

U.S. Nuclear Regulatory Commission Page 2 JUN 30 20flS PV-15, Revision 1, in the First Ten Year Testing Interval.

PV-04 as originally designated as PV-16 in the First Ten Year Testing Interval. Both of these request were approved by NRC letter dated March 22, 2000.

The updated IST Program has been developed to the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance (OM) Code 2001 Edition, through the 2003 Addenda with the Errata provided in the enclosed Program. Several errors, primarily editorial, have been identified in the 2003 Addenda which have since been corrected in the ASME 2005 Addenda. However, the 2005 Addenda has not been endorsed by NRC. Therefore, TVA's program for WBN was developed to the ASME OM Code 2001 Edition through the 2003 Addenda as corrected by the list in Appendix E of the enclosed Program.

The Updated IST Program also conflicts with the WBN Technical Specifications Section 5.7.2.11. TVA has requested a License Amendment, WBN-TS-06-04, to update the technical specifications to the ASME OM Code. This License Amendment Request was submitted June 16, 2006.

There are no regulatory commitments associated with this submittal. If you have any questions concerning this matter, please call me at (423) 365-1824.

Sincerely, P. L. Pace Manager, Site Licensing and Industry Affairs Enclosure Cc: See Page 3

U.S. Nuclear Regulatory Commission Page 3 "JUN 3 0 200O Enclosures cc (Enclosures):

NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. D. V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08G9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303

TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT PO Box 2000 Spring City, Tennessee 37381 SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Unit 1 Commercial Service -- May 27,1996

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 2 of 73 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES TABLE OF CONTENTS Section Subject Page

1.0 INTRODUCTION

................................................................................................................... 3 2.0 PUMP INSERVICE TESTING PROGRAM ....................................................................... 3 2.1 Pump Groups ......................................................................................................................... 3 2.2 Test Frequency ...................................................................................................................... 4 3.0 VALVE INSERVICE TESTING PROGRAM ....................................................................... 5 3.1 Containment Isolation Valves ............................................................................................. 5 3.2 Pressure Isolation Valves ................................................................................................. 5 3.3 Fail Safe Actuators ................................................................................................................. 6 3.4 Passive Valves ....................................................................................................................... 6 3.5 Category C-Active and AC-Active Check Valves ............................................................... 7 3.6 Check Valve Condition Monitoring Program ..................................................................... 7 3.7 Thermal Expansion Check Valves .................................................................................... 8 3.8 Safety and Relief Valves .................................................................................................. 8 3.9 Thermal Relief Valves ................................................................................................... 8 3.10 Testing of Solenoid Actuated Pilot Valves ......................................................................... 9 3.11 Testing of Diesel Air Start and Fuel Oil System Valves ...................................................... 9 3.12 Testing In Conjunction with Cold Shutdowns .................................................................... 9 4.0 ABBREVIATIONS AND SYSTEM NUMBERS ................................................................ 10 4.1 Abbreviations ....................................................................................................................... 10 4.2 System Identification Num bers ......................................................................................... 11 TABLES 1 Summary Listing of Pum ps .............................................................................................. 12 2 Summ ary Listing of Valves ............................................................................................. 14 APPENDICES A Alternative Frequency Justifications ............................................................................... 45 B Relief Requests ................................................................................................................... 58 C Relief Valve G roups ...................................................................................................... 67 D Pressure Isolation Valve Listing ...................................................................................... 69 E Editorial Errors in the 2003 Addenda ............................................................................. 70

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 3 of 73 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES

1.0 INTRODUCTION

The rules for the Inservice Testing of pumps and valves for the Second Ten Year Interval, are contained in the ASME OM Code 2001 Edition, through the 2003 Addenda with corrections. The 2003 Addenda included several editorial errors that were corrected in the 2005 Addenda. These are tabulated in Appendix E. The Second Ten Year Interval for the Watts Bar Nuclear Plant (WBN) starts on December 27, 2006 and will end on December 26, 2016. Title 10, Part 50, Section 55a of the Code of Federal Regulations (10CFR50.55a) and the Watts Bar Technical Specifications (TS) require that Inservice Testing be met throughout the service life of the nuclear power plant and updated at each 10 year interval. This program provides the technical requirements for implementing the Inservice Testing (IST) Program for WBN. The intent of this program is to identify pump and valve degradation and ensure that the proper corrective action is taken such that operational readiness is maintained at all times.

This Summary Description identifies the pumps and valves for which IST will be performed at WBN Unit 1 to comply with the requirements of 10CFR50.55a. The testing required by this program will be accomplished through the WBN Surveillance Testing Program.

2.0 PUMP INSERVICE TESTING PROGRAM Except for relief requested under the provisions of 10CFR50.55a, the IST Program for pumps shall be conducted in accordance with ASME OM Code, ISTB, 2001 Edition with Addenda through 2003.

Table 1 summarizes the IST Program for pumps at WBN. Each Inservice Test Quantity to be measured and reference to related relief requests is listed. Specific details of the relief requests are provided in Appendix B.

2.1 Pump Groups A. Group A Pumps - The OM Code defines Group A pumps as those pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations. Watts Bar considers the following pumps to be Group A pumps along with the basis for grouping:

1. Charging Pumps - The CCPs are utilized during plant operation for normal charging and letdown activities.

2. Motor Driven Auxiliary Feedwater Pumps - The MD AFW pumps are utilized during startup from refueling outages to fill the steam generators and to maintain steam generator level prior to initiation of normal feedwater.

3. Boric Acid Transfer Pumps - The BAT pumps are in service for recirculation of the boric acid tanks during normal operation.

4. Component Cooling System Pumps - The CCS pumps operate continuously during normal plant operation to supply cooling water to essential and non-essential heat loads as well as cooling water to the RCP motor bearings and thermal barriers.

5. Chilled Water Pumps - The Chilled Water pumps are in service during normal operation to supply cooling to various loads.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 4 of 73 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES

6. Residual Heat Removal Pumps - The RHR pumps are required to operate when maintaining the plant in a cold shutdown condition.

7. ERCW Pumps - The ERCW pumps are vertical line shaft pumps that operate continuously during normal plant operation and during shutdown conditions to supply cooling water to essential and non-essential heat loads.

8. ERCW Screen Wash Pumps - The ERCW Screen Wash Pumps are vertical line shaft pumps that operate intermittently during normal plant operation and during shutdown conditions to maintain the ERCW Traveling Water Screens clean.

B. Group B Pumps - The OM Code defines Group B pumps as those pumps in standby systems that are not operated routinely except for testing. WBN considers the following pumps Group B pumps:

1. Turbine Driven Auxiliary Feedwater Pump - This pump is not utilized during any plant operating evolution. The pump remains in standby during all operating Modes and is required to operate only during accident or transient conditions in which it is credited for accident mitigation.

2. Containment Spray Pumps - The Containment Spray pumps are not utilized during any plant operating evolution. The pumps remain in standby during all operating Modes. The pumps are required to operate only during a loss-of-coolant accident (LOCA) or main steam line break (MSLB) inside containment for containment heat removal and pressure suppression.

3. Safety Injection System (SIS) Pumps - The SIS pumps remain in standby during all operating Modes, except during testing. These pumps are required to operate only during a loss-of-coolant accident (LOCA) to provide cooling to the reactor.

2.2 Test Frequency A. Tech Spec frequency shall not be superseded by ASME frequency. The provisions of Tech Spec 3.0.2 allowing the use of a +/-25% tolerance to specified test frequencies of 2 years or less listed in the Tech Spec may be applied.

B. When plant conditions restrict the availability of some components for testing, testing may be delayed until plant conditions are made available.

C. Components tested during power ascension due to maintenance performed during the outage shall be considered inoperable until the post maintenance tests are completed.

D. ASME Inservice pump testing (in the as found condition where practical) shall be conducted quarterly (at least once every 92 days).

E. A comprehensive pump test is performed every 2 years.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 5 of 73 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES F. ASME pumps lacking required fluid inventory shall be tested at least once every two years (at least once every 24 months).

G. Pump testing shall continue through shutdown periods on operable equipment.

H. Pump performance may require increasing the test frequency to twice per quarter.

1. Pumps in systems out of service for an extended period of time are not required to be tested but will be tested within the last 92 days of the outage or prior to being returned to service or entry into an operational mode which requires the pump to be OPERABLE unless technical specifications allow otherwise.

K. Pump testing is required prior to returning to service following maintenance activities which could affect pump performance.

L. Pumps that are discovered to be out of frequency shall be subject to the requirements of TS Surveillance Requirement 3.0.3 and Regulatory Issue Summary (RIS) 2005-020.

3.0 VALVE INSERVICE TESTING PROGRAM Except for relief requested under the provisions of 10CFR50.55a, the IST Program for valves shall be conducted in accordance with ASME OM Code, ISTC, 2001 Edition with Addenda through 2003. Valves in WBN's safety related systems were reviewed and categorized. Valves which were categorized as active in any category and passive valves categorized in Category A or B are listed in Table 2. Justifications for testing at a frequency other than quarterly are listed numerically in Appendix A. Relief Requests are listed numerically in Appendix B.

3.1 Containment Isolation Valves (CIV)

Valve leakage rates shall be subject to the analysis and corrective action of OM Code (ISTC-3600). This is also required by 10CFR50.55a(b)(2)(vii) for Containment Isolation Valves. Category A valves or valve combinations shall have a permissible leakage rate specified by the owner. Valves or valve combinations with leakage rates exceeding the permissible rate shall be declared inoperable and either repaired or replaced. A retest demonstrating satisfactory performance shall be performed prior to declaring the valve operable. This requirement is satisfied within the Appendix J program for containment isolation valves.

All Appendix J valves are also included in the IST Program. Frequency of testing will be based on performance since WBN is an Option B plant.

3.2 Pressure Isolation Valves (PIV)

A. These valves must be tested at least once per 18 months.

B. Testing must be performed prior to entering MODE 2 whenever the plant has been in MODE 5 for 7 days or more and if leakage testing has not been performed in the previous 9 months.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 6 of 73 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES C. Testing must be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock will start after the flow through the valve(s) has been stopped. Surveillance Requirements and the associated bases allow delay when plant conditions needed for testing are not available in MODES 3 or 4.

D. Testing should be performed during startup after coming off RHR to eliminate multiple performances due to RHR flow through Cold Leg Primary and Secondary check valves.

E. Testing at low RCS pressure will minimize personnel hazard and provide a conservative leak rate which provides early indication of potential problems.

F. Testing must be performed prior to returning to MODE 2 following maintenance, repair, or replacement work that could affect valve seating.

A listing of PIVs is provided in Appendix D.

3.3 Fail Safe Actuators Valves which have a fail safe actuator are exercised using that actuator. In most cases, the nature of the control circuitry used to stroke the valve is such that normal testing causes the fail safe actuator to operate the valve. Thus, the fail safe actuator is regularly tested when the valve is tested. In those cases where the fail safe actuator is not the normal source for operation of the valve, valve testing is performed using both the normal means of operation and the fail safe actuator.

3.4 Passive Valves As specified in ISTC Table ISTC-3500-1, passive valves have no testing requirements other than verification of the accuracy of remote position indicators for valves so equipped and/or seat leakage testing if categorized as A-Passive. The attached testing program provides for verification of the accuracy of the remote position indicators of passive valves which are in a flow path which is required to perform a safety function in order to mitigate the consequences of an accident, achieve the cold shutdown condition, or maintain the cold shutdown condition. Provisions are also included for seat leakage testing of Category A-Passive valves. Passive valves which are within a non-safety related flow path are considered to be outside the scope the IST program and are not tested as part of this program.

WBN also has valves in the Essential Raw Cooling Water and Component Cooling System that were originally equipped with remote position indicators and which are within or provide a flow boundary for a safety related flow path. These valves have been placed in their required safety position and administratively locked in place with the power supply breaker locked open. This action was taken to mitigate potential non-conservative action by the valves in the event of a fire (10CFR50 Appendix R). None of these locked valves are required to change position to achieve or maintain the cold shutdown condition or to mitigate the consequences of an accident. Since locking open the power breaker for these valves also disables the remote position indication, these valves are considered to be passive manual valves not equipped with remote position indicators. Consequently the disabled indicators are not tested for accuracy of position indication.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 7 of 73 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 3.5 Testing of Category C-Active and AC-Active Check Valves A. Each check valve shall be exercise tested to both the open and closed position, regardless of safety direction.

B. Open and closed tests need only be performed at an interval when it is practicable to perform both tests.

C. Test order shall be determined by the Owner.

D. Open and closed tests are not required to be performed at the same time if they are performed in the same interval. However, if a check valve is exercised more often in one direction than may occur in the opposite direction, the more frequent testing may continue to be performed. For example, pump discharge checks may be tested open quarterly in conjunction with the pump test, while the closure test may be performed during refueling.

E. If two check valves are in a series configuration without provisions to verify individual reverse flow closure and the plant safety analysis assumes closure of either valve but not both, the valve pair may be tested as a unit. If the plant safety analysis assumes that a specific valve or both valves of the pair close to perform the safety function(s), the valve(s) shall be tested to demonstrate individual valve closure.

F. The use of a mechanical exerciser to move the obturator is also an acceptable test.

G. Disassembly inspection or Non-intrusive testing (NIT) may be used to document acceptable valve performance.

3.6 Check Valve Condition Monitoring Program (CMP)

A. As an alternative to the testing methods listed in Section 3.5 above, the owner may establish a Check Valve Condition Monitoring Program per ISTC-5222 of the OM Code. The WBN Condition Monitoring Program will be contained in WBN Technical Instruction TI-1 00.013.

B. The purpose of this program is to both (a) improve check valve performance and (b) optimize testing, examination, and preventive maintenance activities in order to maintain the continued acceptable performance of a select group of check valves.

WBN may implement this program on a valve or a group of similar valves.

C. In general, valves that are grouped for disassembly inspection or NIT are included in the Condition Monitoring Program. Also, valves that credit Appendix J leak tests for the closure test are included to document and justify the extended frequency of testing. The CMP group is identified in the Alternate Frequency Justification column of the valve test table.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 8 of 73 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 3.7 Thermal Expansion Check Valves Several containment penetrations have been fitted with normally closed check valves designed to open to pass flow created by thermal expansion of fluid in the penetration. The quantity of thermal expansion flow is so small that any opening of the check valve will allow it to pass its maximum required accident flow. Open testing will be performed by verifying the ability to pass any amount of flow. Flow will not be quantified.

3.8 Safety and Relief Valves Requirements are developed from OMb-2003 Appendix I of the OM Code.

A. Set point verification is determined from test actuation using as the test median the fluid to which the valve is subject under operating conditions. Specific acceptance values are identified in implementing instructions.

B. Seat leakage verification is determined by measuring actual leakage through the valve seat during testing. Specific acceptance values are identified in implementing instructions.

The relief valves are grouped for testing. At least 20 percent of each group must be tested within any 48 month period for Class 2 and 3 relief valves. Class 1 valves and Class 2 valve that are tested to Class 1 requirements [MSSVs] must have at least 20 percent tested within any 24 month period. Failures result in additional testing of other valves within the group. Relief valve groups are identified in Appendix C.

3.9 Thermal Relief Valves Some safety related systems, particularly those containing heat exchangers, have been provided with thermal relief valves (TRV). These TRVs are small capacity relief valves intended to relieve pressure due to thermal expansion of fluid in an isolated component.

The function of these valves is to protect equipment that is in a standby mode, that is, the equipment is not actively in service for accident mitigation or shutdown.

A. Tests shall be performed on all Class 2 and 3 relief devices used in a thermal relief application every 10 years, unless performance data indicate more frequent testing is necessary.

B. In lieu of setpoint testing, the relief devices may be replaced at a frequency of every 10 years, unless performance data indicate more frequent replacements are necessary.

C. The group percentage requirements do not apply to pressure relief devices that are used in a thermal relief application. All may be tested or replaced during the same outage.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 9 of 73 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 3.10 Testing of Solenoid Actuated Pilot Valves Many WBN diaphragm actuated line valves are operated by a solenoid actuated pilot valve that cycles either to supply air to or to vent air from the diaphragm actuator. Such pilot valves are considered part of the actuator and their function is adequately demonstrated when the line valve is exercised. Such pilot valves are not individually exercised or stroke timed independent of the diaphragm actuated line valve. Where multiple trains of actuation exist [i.e., multiple solenoid actuated pilot valves performing redundant operation of a single line valve] the line valve is tested using each train of actuation independently. This ensures that each solenoid actuated pilot valve is challenged by the line valve test.

3.11 Emergency Diesel Generator Air Start and Fuel Oil Systems The inservice operability testing of pumps and valves associated with the emergency diesel generator air start and fuel oil systems are excluded from the ASME Inservice Testing Program since they are not Code Class components. These components are an integral part of the emergency diesel generator system and are functionally tested monthly. Thus, the functional operability testing of most of these components is performed at a frequency greater than that required by ISTB or ISTC for either pumps or valves. Additionally, those diesel generator air start system valves whose function is not adequately challenged by the diesel generator testing program are included in an Augmented Inservice Testing (AIST)

Program which utilizes requirements similar to those contained in ISTC. Failure of these components to perform their intended function will be identified either by the failure of the associated emergency diesel generator to meet its operability testing requirements or by the testing performed as part of the AIST Program.

3.12 Testing in Conjunction with Cold Shutdowns For valves in which testing is deferred to cold shutdown, testing will commence within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after cold shutdown is achieved and will continue until all tests are complete or the plant is ready to return to power. The unit will not be kept in cold shutdown solely to complete cold shutdown testing. Any testing not completed at one shutdown will be performed at subsequent cold shutdowns. For planned shutdowns in which sufficient time exists to complete the testing of all the valves identified to be tested at cold shutdown, exception may be taken to the 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months rule, provided all of the valves are tested prior to startup. As a minimum, all cold shutdown valves will be tested each refueling outage. For outages greater than 92 days, all cold shutdown testing shall be completed in the last 92 days of the outage. For valves that fail their associated acceptance criteria during cold shutdown testing and which can only be tested at cold shutdown, corrective action shall be performed prior to restart.

Additionally, some tests identified to be performed in conjunction with cold shutdowns can not be performed during MODE 5 operation. These tests are performed in operational MODE 3 or 4 either while shutting the unit down or while returning the unit to power operation. Although these tests are not performed in MODE 5 (cold shutdown), they are considered to be tests performed in conjunction with cold shutdown because they cannot be performed unless the unit is removed from MODE 1, power operation.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 10 of 73 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 4.0 ABBREVIATIONS AND SYSTEM NUMBERS 4.1 Abbreviations Pump Table Abbreviations DP Differential Pressure Q Quarterly Group A or Group B test CPT Comprehensive Pump Test Valve Table Abbreviations SYS TVA system identification number. See 4.2 following for system numbers and corresponding names.

CLASS ASME Code Class COORD Drawing coordinates where valve/pump is located CAT Valve category; A, B, C, active or passive SIZE Nominal valve diameter in inches TYPE Valve type ANG Angle body valve BTFY Butterfly valve BYV Bypass Valve CKV Check valve FCV Flow Control Valve FSV Flow Solenoid Valve GATE Gate valve GLOBE Globe valve ISV Isolation Valve SFV Safety or relief valve ACTR Valve Actuator DIAPH Diaphragm CYL Air, hydraulic or other high pressure fluid cylinder actuator MAN Manual MOV Motor operated actuator SELF Self actuating (check or relief)

SOL Solenoid actuator NPOSI Position in which a valve is assumed to be prior to being called upon to perform its function.

This may not be the position in which a valve is shown on the TVA Flow Diagrams (47W800 series drawings). O-Open, C-Closed, B-Both, E-Either APOSI The position to which a valve must travel to fulfill its specific function. This is the position to which valves are exercised during their exercising test. O-Open, C-Closed, B-Both TESTS BDC Check Valve Bi-directional Closed (not a safety function)

BDO Check Valve Bi-directional Open (not a safety function)

CMP Check Valve Condition Monitoring Program CVC Check Valve Closure CVO Check Valve Open ET Exercise test (no timing)

FSC Fail Safe Closed (same frequency as the exercise)

FSO Fail Safe Open (same frequency as the exercise)

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL Page 11 of 73 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES TESTS (Continued)

LK Leak Test other than App J or PIV MS Manual Stroke (frequency is 2 YR)

RPI Remote Position Indication (frequency is 2 YR)

SLTJ Seat Leakage Test in accordance with Appendix J SLTP Seat Leakage Test for pressure isolation (Tech Spec frequency) includes CVC STC Exercise and stroke time closed STO Exercise and stroke time open RV Relief Valve Test TRV Thermal Relief Valve Test Frequency Q Quarterly CSD Cold Shutdown RO Refuel Outage DIF Disassemble Inspection Frequency by Group NO JNormal Operations - at least once during the cycle 4.2 System Identification Numbers System Number System Name 01 Main Steam 03 Feedwater 26 High Pressure Fire Protection 30 Ventilation 31 Chilled Water 32 Control Air 33 Service Air 43 Sampling 52 System Test Facility 59 Demineralized Water 61 Ice Condenser Containment 62 Chemical and Volume Control 63 Safety Injection 67 Essential Raw Cooling Water 68 Reactor Coolant 70 Component Cooling 72 Containment Spray 74 Residual Heat Removal 77 Waste Disposal 78 Spent Fuel Cooling 81 Primary Water 84 Flood Mode Boration 90 Radiation Monitoring

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 12 of 73 Table 1, Summary Listing of Pumps Page 1 of 2 ASME Diff Press Pump Pump Code Dp Flow Rate Vib (Vel) Speed Relief Pump UNID Group Drawing Class Pump Type Q CPT Q CPT Q OPT (Note 1) Requests Auxiliary Feed Water (Motor) 1-PMP-3-118-A A 1-47W803-2 3 Centrifugal Q 2Y Q 2Y Q 2Y NR 1 1-PMP-3-128-B Auxiliary Feed Water (Steam) 1-PMP-3-1 A-S B 1-47W803-2 3 Centrifugal Q 2Y Q 2Y NR 2Y Q 1 Chilled Water O-PMP-31-80-A 1-47W865-3 O-PMP-31-96A-B 0-PMP-31-128/1-A A 1-47W865-7 N Centrifugal Q 2Y Q 2Y Q 2Y NR 1 O-PMP-31-129/1-B 0-PMP-31-36/1 -A 1-47W865-8 0-PMP-31-49/1 -B1 Centrifugal Charging 1-PMP-62-108-A A 1-47W809-1 2 Centrifugal Q 2Y Q 2Y Q 2Y NR 1 1-PMP-62-104-B Boric Acid Transfer 1-PMP-62-230-A A 1-47W809-5 3 Centrifugal Q 2Y Q 2Y Q 2Y NR 1 1-PMP-62-232-B Safety Injection 1-PMP-63-10-A B 1-47W811-1 2 Centrifugal Q 2Y Q 2Y NR 2Y NR 1 1 -PMP-63-15-B I I I I I

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 13 of 73 Table 1, Summary Listing of Pumps Page 2 of 2 ASME Diff Pump Pump Code Press Dp Flow Rate Vib (Vel) Speed Relief Pump UNID Group Drawing Class Pump Type Q CPT Q CPT Q CPT (Note 1) Requests Essential Raw Cooling Water 0-PMP-67-28-A 0-PMP-67-32-A 0-PMP-67-36-A O-PMP-67-40-A A 1-47W845-1 3 Vertical Line Q 2Y Q 2Y Q 2Y NR O-PMP-67-47-B Shaft 0-PMP-67-51 -B 0-PMP-67-55-B 0-PMP-67-59-B ERCW Screen Wash 1-PMP-67-431 -A 1-PMP-67-440-B A 1-47W845-1 N Vertical Line Q 2Y Q 2Y Q 2Y NR 1,2 2-PMP-67-437-A Shaft 2-PMP-67-447-B Component Cooling 1-PMP-70-46-A 1-PMP-70-38-A A 1-47W859-1 3 Centrifugal Q 2Y Q 2Y Q 2Y NR 0-PMP-70-51 -S Containment Spray 1-PMP-72-27-A B 1-47W812-1 2 Centrifugal Q 2Y Q 2Y NR 2Y NR 1 -PMP-72-1 0-B1 Residual Heat Removal 1-PMP-74-10-A A 1-47W810-1 2 Centrifugal Q 2Y Q 2Y Q 2Y NR 1-PMP-74-20-B I I I II _L Notes:

(1) Per ISTB-3530 and Table ISTB-3000-1, rotational speed measurements are only required for variable speed pumps. Pumps marked NR are powered by synchronous or induction motors.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 14 of 73 Table 2, Summary Listing of Valves Pag e 1 of 31 C C NA L 0 P P S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W801-1 ,,

1-FCV-1-4-T 1 2 C-3 B-Act 32 GLOBE CYL 0 C STC/RO FSC RPI AF-01 None 1-FCV-1-11-T 1 2 E-3 B-Act 32 GLOBE CYL 0 C STC/RO FSC RPI AF-01 None 1-FCV-1-22-T 1 2 F-3 B-Act 32 GLOBE CYL 0 C STC/RO FSC RPI AF-01 None 1-FCV-1-29-T 1 2 C-3 B-Act 32 GLOBE CYL 0 C STC/RO FSC RPI AF-01 None 1-FCV-1 -147-A 1 1 2- C-3 B-Act m1 2 GLOBE DIAPH 04 C STC/CSD FSC RPI AF-03 None 1-FCV-1 -148-B 1 2 E-3 B-Act 2 GLOBE DIAPH 0 C STC/CSD FSC RPI AF-03 None 1-FCV-1 -149-A 1 2 F-3 B-Act 2 GLOBE DIAPH 0 C STC/CSD FSC RPI AF-03 None 1-FCV-1-150-B 1 2 A-3 B-Act 2 GLOBE DIAPH 0 C STO/CSD ESC RPI AF-03 None 1-PCV-1-5-T 1 2 0-2 B-Act 6 GLOBE DIAPH C B STO/RO STC/RO FSC RPI None None 1-PCV-1-12-T 1 2 D-2 B-Act 6 GLOBE DIAPH C B STO/RO STC/RO FSC RPI None None 1-PCV-1-23-T 1 2 F-2 B-Act 6 GLOBE DIAPH C B STO/RO STC/RO FSC RPI None None 1-PCV-1-30-T 1 2 A-2 B-Act 6 GLOBE DIAPH0 B STO/RO STC/RO FSC RPI None None 1-ISV-1-619 1 2 0-2 B-Act 6 GATE MAN 0 C MS None None 1-ISV-1 -620 1 2 D-2 B-Act 6 GATE MAN 0 C MS None None 1-ISV-1-621 1 2 F-2 B-Act 6 GATE MAN 0 C MS None None 1-1SV-1-622 1 2 A-2 B-Act 6 GATE MAN 0 C MS None None 1-SFV-1-512 1 2 F-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-513 1 2 F-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-514 1 2 F-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-515 11 2 F-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-517 2 D-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-518 1 2 D-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-519 1 2 D-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-519 1 2 D-2 C-Act 6x10 SFV SELF 0 O RV None None 1-SFV-1-520 1 2 D-2 0-Act 6x10 SFV SELF 0 0 RV None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 15 of 73 Table 2, Summary Listing of Valves Page 2 of 31 C C NA L 0 PP S A 00 ALT. REL.

Y S R SS FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W801-1 (continued)

I-SFV-1-521 1 2 D-2 C-Act 6x1 0 SFV SELF C 0JRV None None 1-SFV-1-522 1 2 B-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-523 1 2 B-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-524 1 2 B-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-525 1 2 B-2 C-Act 6x10 SFV SELF C O RV None None 1-SFV-1-526 1 2 B-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-527 1 2 A-2 C-Act 6x101 SFV SELF C 0 RV None None 1-SFV-1-528 1 2 A-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-529 1 2 A-2 C-Act 6x10 SFV SELF C 0 RV None None 1-SFV-1-530 1 2 A-2 C-Act 6x10 I SFV SELF C 0 RV None None I1-SFV-1-5312 1 2 A-2 C-Act j6x10 SFV SELF C 0 RV None ,None Drawing Number 1-47W801-2 1-FCV-1 B 1 2 D-4 B-Act 4 GATE SOL 0 C STC/Q FSC RPI None None 1-FCV-1 A 1 2 E-4 B-Act 4 GATE SOL 0 C STC/Q FSC RPI None None 1-FCV-1 B 1 2 G-4 B-Act 4 GATE SOL 0 C STC/Q FSC RPI None None 1-FCV-1 A 1 2 B-4 B-Act 4 GATE SOL 0 C STC/Q FSC RPI None None 1-FCV-1-181-A 11 22 D-2 B-Act 44 GATE SOL 0 C STC/Q FSC RPI None None 1-FCV-1-182-B F-2 B-Act GATE SOL 0 STC/Q FSC RPI None None 1-FCV-1 -183-A 1 2 H-2 B-Act 4 GATE SOL 0 C STC/Q FSC RPI None None 1-FCV-1 -184-B 1 2 B-2 B-Act 4 GATE SOL 0 C STC/Q FSC RPI None None 4B 1 12 - -c IIC- 4 GAESL0CICQ P oe Nn Drawing Number 1-47W803-1, 1-CKV-3-508 3 2 F-2 C-Act 16 CKV SELF 0 C CVc/CSD BDO/NO AF-O5 None 1-CKV-3-509 3 2 E-2 C-Act 16 CKV SELF 0 C CVC/CSD BDO/NO AF-05 None 1-CKV-3-510 3 2 C-2 C-Act 16 CKV SELF 0 C CVC/CSD BDO/NO AF-05 None 1-CKV-3-51:1 3 2 B-2 C-Act 16 CKV SELF 0 C CVC/CSD BDO/NO IAF-05 1None

I I

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 16 of 73 T

Table 2, Summary Listing of Valves Page 3 of 31 C C NA L 0 PP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBERI S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W803-1 (continued) 1--CKV-3-638 3 2 A-3 C-Act 6 ICKV SELF 0 C CVC/ROBDO/NO CKV-CMP None 1-CKV-3-644 3 2 A-1 C-Act 6 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-3-645 3 2 A-1 C-Act 6 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-3-652 3 2 C-2 C-Act 6 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-3-655 3 2 C-1 C-Act 6 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-3-656 3 2 C-1 C-Act 6 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1 -CKV-3-669 3 2 D-2 C-Act 6 ICKV SELF 0 C CVC/ROBDO/NO CKV-CMP None 1-CKV-3-670 3 2 D-1 C-Act 6 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-3-678 3 2 E-2 C-Act 6 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None I1-CKV-3-679 3 2 F-1 IC-Act 6 CKV SELF 0 C CVO/RO BDO/NO CKV-CMP None 1-FCV-3-33-A 3 2 C-3 B-Act 16 KGATE MOV 0 C STC/ROB RPI AF-06 None 1-FCV-3-35 3

C-4 B-Act 16 ANG DIAPH 0 C STC/RO FSC RPI AF-06 None 1-FCV-3-35A 3 N C-4 B-Act 6 DIAPH 0 C STC/ROFSCRPI AF-06mGLOBENone 1-FCV-3-47-B 3 2 E-3 B-Act 16 GATE MOV 0 C STC/RO RPI AF-06 None 1-FCV-3-48 3

E-4 B-Act 16 ANG DIAPH 0 C STC/RO FSC RPI AF-06 None I-FCV-3-48A 3 N D-4 B-Act 6 GLOBE DIAPH 0 C STC/RO FSC RPI AF-06 None 1-FCV-3-87-A 3 2 F-3 B-Act 16 GATE MOV 0 C STC/RO RPI AF-06 None 1-FCV-3-90 3

F-4 B-Act 16 ANG DIAPH 0 C STC/RO FSC RPI AF-06 None 1-FCV-3-90A 3 N F-4 B-Act 6 GLOBE DIAPH 0 C STC/RO FSC RPI AF-06 None 1-FCV-3-100-B 3 2 B-3 B-Act 16 GATE MOV 0 C STC/RO RPI AF-06 None I-FCV-3-03 33 F-4 B-Act 16 ANG DIAPH 0 0 0 STO/RO STC/RO ESO FSC RPI AF-06

None 1-FCV-3-103A N F-4 B-Act 6 GLOBE DIAPH C RPI AF-06 None 1-FCV-3-236 3 2 C-3 B-Act 6 GATE DIAPH 0 C STC/RO FSC RPI AF-06 None 1-FCV-3-239 3 2 D-3 B-Act 6 GATE DIAPH 0 C STC/RO FSC RPI AF-06 None 1-FCV-3-242 3 2 E-3 B-Act 6 GATE DIAPH 0 C STC/RO FSC RPI AF-06 None

ASME Section III, Class 3 valve installed in a non-ASME Code Class piping system.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 17 of 73 Table 2, Summary Listing of Valves C C Pa N 4 of 31 A

L 0 pPP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W803-1 (continued) 1-FCV-3-245 7 3 Drawing Number 1-47W803-2 2 A-3 JB-Act GATE D APH_ Jo 1G,6 jSTC/ROFSCRPI AF-06 None 1-CKV-1-891-S 1 2 C-8 C-Act 4 CKV SELF C B CVC/DIFCVO/RO CKV-CMP None 1-CKV-1 -892-S 1 2 A-8 C-Act 4 CKV SELF C B CVC/DIF CVO/RO CKV-CMP None 1-FCV-1 A 1 2 C-8 B-Act 4 GATE MOV 0 C STC/Q RPI None None 1-FCV-1 A 1 2 A-8 B-Act 4 GATE MOV C 0 STO/Q RPI None None 1-FCV-1 A 1 3 C-7 B-Act 4 GATE MOV 0 C STC/CSD RPI AF-02 None GATE MOV 0 C STC/CSD RPI AF-02 1-FCV-1 B 1 3 C-7 B-Act 4 1-FCV-1 S 1 N H-6 B-Act 4 GATE Note 1 B B STO/Q STC/Q RPI None None 1-CKV-3-805-A 3 3 F-5 C-Act 8 CKV SELF B B CVO/RO CVC/Q AF-07 None 1-CKV-3-806-B 3 3 F-6 C-Act 8 CKV SELF B B CVO/RO CVC/Q AF-07 None 1-CKV-3-81 0-S 1-CKV-3-814-A 33 33 G-3 G-5 C-Act 10 CKV SELF BB B CVO/ROCVC/Q CVC/Q AF-07 None C-Act 1.5 CKV SELF None -BCVO/Q None 1-CKV-3-815-B 3 3 G-6 C-Act 1.5 CKV SELF B B CVO/Q CVC/Q None None 1-CKV-3-818-S 3 3 G-6 C-Act 1.5 CKV SELF B B CVO/Q CVC/Q None None 1-CKV-3-830-B 3 2 G-8 C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-831-A 3 2 G-8 C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-831-A 3 2 E-8 C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-833-B 3 2 B-8 C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-861-B 3 2 BG-10C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-862-A 3 2 E-10 C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-864-S 3 3 H-6 C-Act 6 CKV SELF 0C OCVO/RO BDC/RO AF-07 None Note 1: This valve has a motor operator for normal open/close functions and a spring actuator for trip closure.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Paqe 18 of 73 I Table 2, Summary Listing of Valves Page5 of 31 c c NA L 0 PP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBERI S S D I CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W803-2 continued_

11-CKV-3-871 -S 3 I2 F-8 C-Act 4 CKV SELF B B CVC/ROCVO/RO CKV-CMP None 1-CKV-3-872-S 3 2 E-8 C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-873-S 3 2 C-8 C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-874-S 3 2 A-8 C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-921-B 3 2 G-10C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-CKV-3-922-A 3 2 F-1 0 C-Act 4 CKV SELF B B CVC/RO CVO/RO CKV-CMP None 1-FCV-3-355 3 3 E-5 B-Act 2 GLOBE DIAPH 0 C STC/Q FSC RPI None None 1-FCV-3-359 3 3 E-6 B-Act 2 GLOBE DIAPH 0 C STC/Q FSC RPI None None 1-FCV-3-116A-A 3 3 F-5 B-Act 4 GATE MOV C 0 STO/Q RPI None None 1-FCV-3-116B-A 3 3 F-5 B-Act 4 GATE MOV C 0 STO/Q RPI None None 1G 1-FCV-3-126A-B 3 3 F-7 B-Act 4 GATE MOV C 0 STO/Q RPI None None 1-FCV-3-126B-B 3 3 F-7 B-Act 4 GATE MOV C 0 STO/Q RPI None None 1-FCV-3-136A-A 3 3 H-4 B-Act 6 GATE MOV C 0 STO/Q RPI None None 1-FCV-3-136B-A 3 3 H-4 B-Act 6 GATE MOV C 0 STO/Q RPI None None 1-FCV-3-179A-B 3 3 H-4 B-Act 6 GATE MOV C 0 STO/Q RPI None None 1-FCV-3-1798-B 3 3 H-4 B-Act 6 GATE MOV C 0 STO/Q RPI None None 1-LCV-3-148-B 3 3 G-8 B-Act 4 GLOBE DIAPH C 0 STO/Q STC/Q FSO RPI None None 1-LCV-3-148A-B 3 3 G-8 B-Act 2 ANG DIAPH C 0 STO/Q STC/Q FSO RPI None None 1-LCV-3-156-A 3 3 E-8 B-Act 4 GLOBE DIAPH C 0 STO/Q STC/Q FSO RPI None None 1-LCV-3-156A-A 3 3 E-8 B-Act 2 ANG DIAPH C 0 STO/Q STC/Q FSC RPI None None 1-LCV-3-164-A 3 3 C-8 B-Act 2 GL DIAPH C 0 STO/Q STC/Q FSO RPI None None 1-LCV-3-1 64-A 3 3 B-8 B-Act 4 GLOBE DIAPH C 0 STO/Q STC/Q FSO RPI None None 1-LCV-3-171A-B 3 3 B-8 B-Act 2 ANG DIAPH C 0 STO/Q STC/Q FSC RPI None None 1-LCV-3-171-B 3 3 1B-8 B-Act 4 GLOBE DIAPH C 0 STO/Q STC/Q FSC RPI None None 1-LCV-3-1 72-A 3 3 F-8 B-Act 3 GLOBE DIAPH C 0 STO/Q STC/Q FSC RPI None None

- - - -I

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES I Paqe 19 of 73 Table 2, Summary Listing of Valves Page 6 of 31 C C NA L 0 PP S A 0 00 ALT. REL.

Y S R S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR III TESTS JUST. NUM.

Drawing Number 1-47W803-2 1-LCV-3-173-B 3 3 E-8 (continued)

B-Act 3 iGLOBE DJAPH ,,_,,

IC0sTO/Q STC/Q FSC RPI None None 1-LCV-3-174-B 3 3 C-8 B-Act 3 GLOBE DIAPH C 0 STO/Q STC/Q FSC RPI None None 1-LCV-3-175-A 3 3 B-8 B-Act 3 GLOBE DIAPH C 0 STO/Q STC/Q FSC RPI None None 1-PCV-3-122 3 3 F-5 B-Act 4 GLOBE DIAPH C 0 STO/Q None None 1-PCV-3-132 3 3 F-6 B-Act 4 IGLOBE DIAPH COISTO/Q None INone Drawing Number 1-47W850-9 1-CKV-26-1260 126 2 B-9 AC-Act 4 CKV SELF CIC CVC/CSD BDO/RO SLTJ ICKV-OMP None 1-CKV-26-1296 26 2 B-3 AC-Act 4 CKV SELF C C CVC/CSD BDO/RO SLTJ CKV-CMP None 1-FCV-26-240-A 26 2 B-9 A-Act 4 GATE MOV 0 C STC/Q RPI SLTJ None JNone 1-FCV-26-243-A 26 2 B-3 A-Act 4 GATE MOV 0jC STC/Q RPI SLTJ jNone INone Drawing Number 1-47W866-1 I - A-Act -

1-FCV-30-7-A 30 2 C-2 A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-8-B 30 2 C-2 A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-9-B 30 2 C-i A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-10-A 30 2 C-2 A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-14-A FCV-30-15-B 30 22 E-1 A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 30 E-1 A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-16-B 30 2 E-2 A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-16-B 30 2 E-1 A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-19-A 30 2 G-2 A-Act 12 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-20-B 30 2 G-1 A-Act 12 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-37-A 30 2 D-1C A-Act 12 BTFY CYL 0 C STC/Q ESC RPI SLTJ None None 1m-FCV-30-40-A 30 2 D-9 A-Act 8 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-50 30 2 C-9 A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-51 A 30 2 C-190 A-Act 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-30-52 300 2 C-9 I-C-0 -

A-Act

-c 24 BTFY CYL 0 C STC/Q FSC RPI SLTJ None None 24 BTY CL0CST/ S P ST oe Nn

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL N

INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 20 of 73 Table 2, Summary Listing of Valves Pace 7 of 31 C C NA L 0 PP S AO 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE I TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W866-1 (continued) 1-FCV-30-53 30 2 0-10 A-Act 24 BTFY CYL 0C STCIQ FSC RPI SLTJ None None 1-FCV-30-56 30 2 E-9 A-Act 24 BTFY CYL 0C STC/Q FSC RPI SLTJ None None 1 -FCV-30-57 30 2 E-1 0 A-Act 24 BTFY CYL 0C STCIQ FSC RPI SLTJ None None Cm 1-FCV-30-58 30 2 G-9 A-ActNN 12 BTFY CYL 0C STC/Q FSC RPI SLTJ None None 1-FCV-30-59 30 2 G-1 0 A-Act 12 BTFY CYL 0C STC/Q FSC RPI SLTJ None None 1-ES V-30-1 34-B 30 2 F-9 A-Act 0.5 GATE SQL 0C STC/Q FSC RPI SLTJ None None 1-ES V-30-1 35-A 30 2 F-i10 A-Act 0.5 GATE SQL 0 C STC/Q FSC RPI SLTJ None None D rawing Number 1-47W865-3 INone 0-CKV-31-2193 31 N E-8 C-Act 6 0KV SELF C 0 CVO/Q BDC/Q None SELF C O CVO/Q BDC/Q jNone None 0-CKV-31-2235 10-RFV-31-2252 1-F-1-20 31 N E-3 C-Act 311 N 0-3 C-Act 131 N 0-8 C-Act 6

lxi lxi 0KV SFV SFV SELF 1010 RV SELF 1010 RV None jNone None None Drawing Number 1-47W865-5 OVO/RO CVC/RO CVC/RO SLTJ CKV-CMP None 1-CKV-31-3378 1-CKV-31-3392 31 31 2

2 F-7 AC-Act E-7 AC-Act 0.5 0.5 CKV 0KV SELF SELF C B C B CVO/RO SLTJ CKV-CMP None

~ ~

-F~~~~~~~

3 ~ 1 c 1-CKV-31 -3407 31 2 0-7 IAC-Act 0.5 0KV SELF C 9 P B CVO/RO CVC/RO T SLTJ CKV-CMP n None n

1-CKV-31 -3421 31 2 B-7 AC-Act 0.5 0KV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-FCV-31 -305-B 31 2 B-7 A-Act 2 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-31 -306-A 31 2 B-7 A-Act 2 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-31-308-A 31 2 0-7 A-Act 2 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-31-309-B 31 2 0-7 A-Act 2 GLOBE DIAPH 0 C STCIQ FSC RPI SLTJ None None 1-FCV-31 -326-A 31 2 E-7 A-Act 2 GLOBE DIAPH 0 C STC/Q ESC RPI SLTJ None None DIAPH 0 C STC/Q None None 1-FCV-31-327-B 1-FCV-31-329-B 31 31 2

2 E-7 A-Act F-7 A-Act 2

2 iGLOBE GLOBE DIAPH 0 C FSC RPI STC/Q FSC RPI SLTJ SLTJ None None 2 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-31-330-A 31 2 F-7 A-Act

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 21 of 73 Table 2, Summary Listing of Valves Pag 8 of 31 C C N A L 0 PP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER I S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W865-7 0-CKV-31-2307 31 N F-8 C-Act 6 CKV SELF C 0 CVO/Q BDC/Q None None O-CKV-31-2364 31 N F-3 C-Act 6 CKV SELF C 0 CVO/Q BDC/Q None None 0-RFV-31-2326 31 N D-8 C-Act 6X1 SFV SELF C 0 RV None None O-RFV-31-2383 31 N D-3 I C-Act 1X1 SFV SELF C 0 RV None None Drawing Number 1-47W865-8 O-CKV-31-2607 31 N E-8 C-Act 6 CKV SELF IC 0CVO/Q BDC/Q None None 0-CKV-31-2649 31 N E-2 C-Act 6 CKV SELF C 0 CVO/Q BDC/Q None None 0-RFV-31-2623 31 N D-10 C-Act 1X1 SFV SELF C 0 RV None None 0-RFV-31-2665 31 N D-4 C-Act 1X1 SFV SELF C 0 RV None None Drawing Number 1-47W848-1 1 -BYV-32-288 32 2 A-9 A-Pas 2 GLOBE MAN C C SLTJ None None 1-BYV-32-298-A 32 2 C-9 A-Pas 2 GLOBE MAN C C SLTJ None None 1-BYV-32-308-B 32 2 D-9 A-Pas 2 GLOBE MAN C C SLTJ None None 1-CKV-32-293 32 2 A-9 AC-Act 2 CKV M SELF C BDO/NO CVC/CSD SLTJ AF-09 None 1-CKV-32-303-A 32 2 C-9 AC-Act 2 CKV SELF 0 C BDO/NO CVC/CSD SLTJ AF-09 None 1-CKV-32-313-B 32 2 D-9 AC-Act 2 CKV SELF 0 C BDO/NO CVC/CSD SLTJ AF-09 None 1-FCV-32-80-A 32 2 C-9 A-Act 2 GLOBE DIAPH 0 C STC/CSD FSC RPI SLTJ AF-09 None 1-FCV-32-102-B 32 2 D-9 A-Act 2 GLOBE DIAPH 0 C STC/CSD FSC RPI SLTJ AF-09 None 1-FCV-32-1 10-A 32 2 A-9 A-Act 2 GLOBE DIAPH 0 C STC/CSD FSC RPI SLTJ AF-09 None Drawing Number 1-47W848-5 -

o0-ISV-32-1013 132 1 N E-3 IB-Act 4 GATE MAN OIC IMS None INone Drawing Number 1-47W846-2 1-SV-33-713 331 2 1F-5 JA-Pas 2 1DIAPH IMAN ICIC SLTJ None None 1-ISV-33-714 33 2 F-6 A-Pa 2 DIAPH MAN C C SLTJ None None 1-V I APa MAN C C LTNon

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL I1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES I Pacie 22 of 73 Table 2, Summary Listing of Valves Paqe 9 of 31 C C NA L 0 P P S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W625-1 1-FCV-43-2-B 43 2 D-3 A-Act 0.375 GATE SOL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-43-3-A 43 2 D-5 A-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-43-1 1-B 43 2 B-2 A-Act 0.375 GATE SOL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-43-12-A 1-FCV-43-22-B 43 43 22 B-4 F-5 A-Act 0.375 GATE SQL SOL 0 0 C STC/Q FSC RPI SLTJ None None 1-FCV-43-23-A 43 2 D-5 A-Act 0.375 GATE SOL 0 C STC/Q FSC RPI SLTJ None None Drawing Number 1-47W625-2 1-FCV-43-34-B 43 2 B-2 A-Act 0.375 GATE SOL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-43-35-A 43 2 C-4 A-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-43-54D-B 43 2 C-7 B-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI None None 1-FCV-43-55-A 43 2 C-6 B-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI None None 1-FCV-43-56D-B N

43 2 C-7 B-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI None None

-I N 1-FCV-43-58-A 43 2 0-6 B-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI None None 1-FCV-43-59D-B 43 2 D-8 B-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI None None 1-FCV-43-61 -A 43 2 D-7 B-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI None None 1-FCV-43-63D-B 43 2 E-9 B-Act 0.3751 GATE DIAPH 0 C STC/Q FSC RPI None None 1-FCV-43-64-A 43 2 E-8 B-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI None None Drawing Number 1-47W625-7 1-FCV-43-75-B 43 2 E-7 A-Act 0.375 GATE SOL 0 C STC/Q FSC RPI SLTJ None None 1-FCV-43-77-A 43 2 E-8 A-Act 0.375 GATE DIAPH 0 C STC/Q FSC RPI SLTJ jNone None Drawing Number 1-47W625-11 1-FCV-43-201-A 43 2 F-5 A-Act 0.375 GATE SOL C 0 STO/Q RPI SLTJ None None 1-FCV-43-202-A 43 2 F-5 A-Act 0.375 GATE SOL C 0 STO/Q RPI SLTJ None None 1-FCV-43-207-B 43 2 D-6 A-Act 0.375 GATE SOL C 0 STO/Q RPI SLTJ None None 1-FCV-43-208-B 43 2 C-6 A-Act 0.375 GATE SOL C 0 STO/Q RPI SLTJ None None 1-FCV-43-433-A 43 2 F-4 A-Act 0.375 GATE SOL C 0 STO/Q RPI SLTJ None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 23 of 73 Table 2, Summary Listing of Valves Pae.10 of 31 C C NA L 0 PP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZEI TYPE ACTR 1_ I TESTS JUST. NUM.

Drawing Number 1_-FCV-43-434-A 1-47W625-11 ntinued-43 2 F-4 IA-Act mSOL -c 0.375 GATE C O STO/Q RPI SLTJ None one 1-FCV-43-435-B 43 2 D-5 A-Act 0.375 GATE SOL C0 JSTO/Q RPI SLTJ None None 1-FCV-43-436-B 43 2 C-5 A-Act 0.375 GATE SOL C 10 STO/Q RPI SLTJ None 7None Drawing Number 1-47W625-15 1 -CKV-43-834 43 2 H-5 AC-Pas 0.375 CKV SELF C C SLTJ None None 1-CKV-43-841 43 2 A-10 AC-Pas 0.375 CKV SELF C C SLTJ None None 1-CKV-43-883 43 2 G-5 AC-Pas 0.375 CKV SELF C C SLTJ None None 1-CKV-43-884 43 2 A-9 AC-Pas 0.375 CKV SELF C C SLTJ None None 1-FSV-43-250-A 43 1-FSV-43-251-A 43 22 D-1 C-1 A-Pas A-Pas 0.375 0.375 GATEI GATE SOL SOL CC CC RPI SLTJ RPISLTJ None None None None 1-FSV-43-287-A 43 2 B-8 A-Pas 0.375 GATE SOL C C RPI SLTJ None None 1-FSV-43-288-A 43 2 B-8 A-Pas 0.375 GATE SOL C C RPI SLTJ None None 1-FSV-43-307-A 43 2 B-9 A-Pas 0.375 GATE SOL C C RPI SLTJ None None 1-FSV-43-309-B 43 2 D-2 IA-Pas 0.375 GATE SOL C C RPI SLTJ None None 1-FSV-43-310-B 43 2 C-2 A-Pas 0.375 GATE SOL C C RPI SLTJ None None 1-FSV-43-318-B 43 2 B-9 A-Pas 0.375 GATE SOL C C RPISLTJ None None 1-FSV-43-319-B 43 2 B-9 A-Pas 0.375 GATE SOL C C RPI SLTJ None None 1 -FSV-43-325-B 43 2 B-10 A-Pas 0.375 GATE SOL C C RPI SLTJ None None 1-FSV-43-341-B 43 2 H-6 A-Pas 0.375 GATE SOL C C RPI SLTJ None None 1-FSV-43-342-A 43 2 BG-6oA-Pas 0.375 GATE SOL C C RPI SLTJ None None Drawing Number 47W331-3.

1-ESV-52-500 52 2 H-2 A-Pas 0.75 GATE MAS C C PSLTJ None None 1-ESV-52-501 52 2 H-2 A-Pas 0.75 GATE MAN C C SLTJ None None 1-ISV-52-502 52 2 H-2 A-Pas 0.75 GATE MAN C C SLTJ None None 1-ISV-52-503 52 2 H-2 A-Pas 0.75 GATE MAN C C SLTJ None None 1-ISV-52-504 52 2 1H-2 A-Pas 1 0.75 1,GATE MAN ClCISLTJ None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 24 of 73 Table 2, Summary Listing of Valves Pa.e 11 of 31 C C NA L 0 Pp S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 47W331-3 1-1SV-52-505 52 2 (continued)

H-2 A-Pas 0.75 GATE MAN C C SLTJ None None 1-ISV-52-506 52 2 H-2 A-Pas 0.75 GATE MAN C C SLTJ None None 1-ISV-52-507 52 2 H-2 A-Pas 0.75 GATE MAN C C SLTJ None None Drawing Number 1-47W856-1 mill 1-ISV-59-522 59 2 1 F-2 IA-Pas 2 BALL MAN C C SLTJ None None 1-ISV-59-698 59 2 F-2 A-Pas 2 DIAPH MAN CICSLTJ INone None Drawing Number 1-47W814-2 1-CKV-61-533 61 2 B-7 AC-Act 0.375 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-61-658 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-659 61 N D-12 C-Act 12 CKV SELF C OCVO/RO BDC/RO AF-10 None 1-CKV-61-660 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-661 61 N D-12 C-Act 12 CKV SELF C 0 1-CKV-61-662 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO CVO/RO BDC/RO BDC/RO AF-10 AF-10 None None 1-CKV-61-663 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-664 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-665 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-666 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-667 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-668 61 N D-12 C-Act 12 CKV SELF CO CVO/RO BDC/RO AF-10 None 1-CKV-61-669 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61 -668 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-lO None 1-CKV-61-676 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-671 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-1-0 None 1-CKV-61-672 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-671 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61 -673 61 N D-12 C-Act 12 CKV SELF C 0OCVO/RO BDC/RO AF-10 None 1-CV-6 N 12C-At 6 1 0K SEF C0 OO/R BD/R AF- on

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL I

1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 25 of 73 Table 2, Summary Listing of Valves C C Pa e12 of 31 N A SA 0 0 ALT. REL.

Drawing Number Y S R S S FREQ. REQ.

1-47W814-2 (continued)

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

1-CKV-61-675 61 N D-12 C-Act 12 CKV SELF C 0 CVO/RO BDC/RO AF-10 None E LF C 0O VO /R O B DC /RO A F- 10 N one 1-CK V-61 -676 1-CKV-61-677 61 N N D-12 D-12 C-Act C-Act 12 12 CKV S V CK SELF C 0 CVO/RO BDC/RO AF-10 None 1-CKV-61-680 61 2 B-7 AC-Act 0.375 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-61-692 61 2 F-i1 AC-Act 0.375 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-61-745 61 2 G-9 AC-Act 0.375 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-FCV-61-96-A 61 2 E-11 A-Act 2 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-61-97-B 61 2 E-11 A-Act 2 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-61 -117-A 61 2 G-9 A-Act 2 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-61-122-B 61 22 G-9 A-Act 2 1-FCV-61-1 22-A 61 A-6 A-Act 4 DIAPH DIAPH 0 DIAPH DIAPH 0 CC STC/Q STC/Q FSC FSC RPI RPI SLTJ SLTJ None None None None 1-FCV-61-191-A 61 2 A-6 A-Act 4 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None

-194-B 1-FCV-61 -1 92-B 61 61 2 2 A-6 B-7 A-Act A-Act 4 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 4 DIAPH 1-FCV-61-193-B 61 2 B-7 A-Act 4 DIAPH DIAPH DIAPH 0 0 C STC/Q FSC RPI SLTJ None None None None Drawing Number 1-47W809-1 1-CKV-62-504-S 62 2 H-1 0 C-Act 8 CKV SELF C B CVO/RO CVC/RO AF-1 1 None 1-CKV-62-523-A 62 2 G-9 AC-Act 2 CKV SELF C B CVO/Q CVC/Q LK None None 1-CKV-62-525-A 62 2 G-9 AC-Act 4 CKV SELF 0 B CVO/RO CVC/Q LK AF-1 1 None 1-CKV-62-530-B 62 2 F-9 AC-Act 2 CKV SELF C B CVO/Q CVC/Q LK None None 1-CKV-62-532-B 1-CKV-62-560-S 62 21 F-9 AC-Act 42 CKV SELF 0 B CVO/RO CVC/Q LK AF-11 None 62 F-6 C-Act CKV SELF 0 C BDO/NCVC/RO O CKV-CMP None 1-CKV-62-561-S 62 1 F-6 C-Act 2 CKV SELF 0 C BDO/NO CVC/RO CKV-CMP None 1-CKV-62-562-S 1-CKV-62-563-S 62 1 H-6 C-Act 2 CKV SELF 0 C BD BDO/N0O/N CVC/R O

CVC/RO O CKV-CMP CKV-CMP None None 1-CKV-62-576-S 62 1 E-4 C-Act 2 CKV SELF 0 C BDO/NO CVC/RO CKV-CMP None 1- V _ _r

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES I Paqe 26 of 73 Table 2, Summary Listing of Valves Page 13 of 31 SA 0 00 ALT. REL.

Y S R S S FREQ. REQ.

Drawingj VALVE Number NUMBER1-47W809-1 S S D CAT SIZE TYPE ACTR I I TESTS JUST.

(continued)-- NUM.

1-CKV-62-577-S 62 1 E-2 C-Act 2 CKV SELF 0 C BDO/NO CVC/RO CKV-CMP None 1-CKV-62-578-S 62 1 G-2 C-Act 2 CKV SELF 0 C BDO/NO CVC/RO CKV-CMP None 1-CKV-62-579-S 62 1 G-4 C-Act 2 CKV SELF 0 C BDO/NO CVC/RO CKV-CMP None 1-CKV-62-638-S 62 1 A-2 C-Act 3 CKV SELF 0 C BDO/NO CVC/RO CKV-CMP None 1-CKV-62-639-S 62 21 C-7 1-CKV-62-640-S 62 A-1 AC-Act C-Act 0.75 3 CKV CKV ISELF SELF C 0

B C

CVO/RO BDO/NO CVC/RO CVC/RO SLTJ CKV-CMP CKV-CMP None None 1-CKV-62-659-S 62 1 A-2 C-Act 3 CKV SELF 0 C BDO/NO CVC/RO CKV-CMP None 1-CKV-62-660-S 62 1 A-1 C-Act 3 CKV SELF 0 C BDO/NO CVC/RO CKV-CMP None 1-CKV-62-661-S 62 1 B-2 C-Act 3 CKV SELF E C BDO/RO CVC/RO CKV-CMP None 1-FCV-62-61-S 62 1 B-2 C-Act 3 GATESELF E C BDO/RO RO CKV-CM None 1-FCV-62-63-A 62 2 B-8 A-Act 4 GATE MOV 0 C STC/CSD RPI SLTJ AF-14 None 1-FCV-62-69-S 62 1 A-2 B-Act 3 GLOBE DIAPH C C STC/CSD FSCRRPI AF-15 None 1-FCV-62-70-S 62 1 A-2 B-Act 3 GLOBE DIAPH C C STC/CSD FSC RPI AF-15 None 1-FCV-62-72-B FV 62-76 62IC 2 A-2 A-Act 3 GLOBE DIAPHO C STC/Q FSCRPISLTJ AF-1 None 1-FCV-62-72-A 62 2 A-5 A-Act 2 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-62-74-A 62 2 A-4 A-Act 2 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-62-76-A 62 2 A-4 A-Act 2 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-62-77-B 62 2 A-7 A-Act 2 GLOBE DIAPH 0 C STC/CSDFSC RPI SLTJ AF-15 None 1-FCV-62-83 62 2 A-8 B-Pas 2 GLOBE DIAPH 0 C RPI None None 1-FCV-62-84-A 62 1 B-2 B-Act 3 GLOBE DIAPH E B STC/CSD STO/CSD FSC RPI AF-08 None 1-FCV-62-90-A 62 2 D-8 B-Act 3 GATE MOV 0 C STC/CSD RPI AF-15 None 1-FCV-62-91-B 62 2 D-8 B-Act 3 GATE MOV 0 C STC/CSD RPI AF-15 None 1-FCV-62-1228-A 62 2 C-10 B-Act 1 GLOBE DIAPH 0 C STC/CSD FSC RPI AF-16 None 1-FCV-62-1229-B 62 2 C-10 B-Act 1 GLOBE DIAPH 0 C STC/CSD FSC RPI AF-16 None 1-LCV-62-132-A 62 2 D-10 B-Act 4 GATE MOV 0 C STC/CSD RPI AF-16 None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES I Paae 27 of 73 Table 2, Summary Listing of Valves

._Page 14 of 31 L 0 PP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS Drawingj Number 1-47W809-1 (continued) ________________________

JUST. NUM.

1-LCV-62-133-B 62 2 D-10 B-Act 4 GATE MOV 0 C STC/CSD RPI AF-16 None H-i-00 B-Act 8 GATE MOV C 0 STO/CSD RPI AF-16 11-LCV-62-135-A

-LCV-62-136-B 62 I22 H-1 62 B-Act 8 GATE MOV C 0 STO/CSD RPI AF-1 6 None 1-RFV-62-505-S 62 2 F-10 C-Act 0.75xl SFV SELF C 0 RV None None 1-RFV-62-636-S 62 2 B-6 C-Act 2x3 SFV SELF C O RV None None

-62 m -

1-RFV-62-649-S 62 2 C-9 C-Act 2x3 SFV SELF C 0 RV None None 1-RFV-62-662-S 62 2 A-3 AC-Act 2x3 SFV SELF C 0 RVSLTJ None None 1-RFV-62-675-S 62 2 B-10 C-Act 2x3 SFV SELF C 0 RV None None 1-RFV-62-1 221 621 2 G-10 C-Act 0.75xl SFV SELF C 0 RV None None 1-RFV-62-1222 62, 2 E-9 C-Act 0.75xl SFV SELF C IO RV None None Drawing Number 1-47W809-2 1-CKV-62-930 62 131 B-4 C-ActI 3 CKV SELFI C OICVO/RO BDC/RO 1AF-13 None 1-FCV-62-138-B 62 3 A-4 B-Act ,GLOBE MOV C OISTO/Q RPI INone jNone Drawing Number 1-47W809-3 1-RFV-62-955 62 2 C-1l C-Act 0.75x1 SFV SELF C 0 RV None None 2-RFV62-95 1-RFV-62-1079 62 2 C-7 cct o.75xl SF SELF Co.R 62 2 C-12 C-Act 4 SFV SELF C 0 RV one None N~one None 2-RFV-62-1079 62 2 C-7 C-Act SFV SELF C 0 RV jNone INone Drawing Number 1-47W809-5 S - -

1-CKV-62-1052-A 162 3 F-8 C-ActI2ICKVTSELFIBfBICVO/QCVC/Q None INone 1-CKV-62-1052-B 162 3jF-7 C-Act CKV SELFBB] CVO/Q CVC/Q INone ]None Drawing Number 1-47W81 1-1 1-CKV-63-502-S 63'2 F-10 C-Act 12 CKV SELF C 0 CVO/RO CVC/CSD AF-18 INone 1-CKV-63-51 0-S 63 2 D-1 0 C-Act 8 CKV SELF C B CVO/RO CVC/RO AF-1 1 None 1-CKV-63-524-A 631 2 F-8 AC-Act 4 CKV SELF C B CVO/RO CVC/Q LK AF-1i1 None 1-CKV-63-526-B 63 2 D-8 1AC-Act 4 CKV ISELF C B CVO/RO CVC/Q LK IAF-1 1 None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL I

I INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Paqe 28 of 73 Table 2, Summary Listing of Valves Paie 15 of 31 I L 0 P S A 0 0 ALT. REL.

Y S R TETSFREQ. REQ.

VALVE NUMBER IS S ID ICAT SIZE TYPE ACTR I IITESTS JUST. NUM.

Drawin Number 1-47W811-1 (Continued) 1-CKV-63-528-A 63 2 F-8 AC-Act 0.75 CKV SELF C B CVO/Q CVC/Q LK None None 1-CKV-63-530-B 63 2 D-8 AC-Act 0.75 CKV SELF C B CVO/Q CVC/Q LK None None 1-CKV-63-543-A 63 1 F-3 AC-Act 2 CKV SELF C B CVO/RO SLTP AF-1 1 None 1-CKV-63-545-A 63 1 F-3 AC-Act 2 CKV SELF C B CVO/RO SLTP AF-11 None 1-CKV-63-547-B 63 163-11ESFB E-3 AC-Act 2 CKV SELF C- B CVO/RO SLTP AF-11 None B_1I 1-CKV-63-549-B 63 1 E-3 AC-Act 2 CKV SELF C B CVO/RO SLTP AF-1I None 1-CKV-63-551-S 63 1 H-i AC-Act 2 CKV SELF C B CVO/RO SLTP AF-11 None 1-CKV-63-553-S 63 1 H-3 AC-Act 2 CKV SELF C B CVO/RO SLTP AF-11 None 1-CKV-63-555-S 63 1 G-3 AC-Act 2 CKV SELF C B CVO/RO SLTP AF-1 1 None 1-CKV-63-557-S 63 1 G-2 AC-Act 2 CKV SELF C B CVO/RO SLTP AF-11 None 16 -

1-CKV-63-558-B 63 1 E-2 AC-Act 61 CKV SELF C B CVO/RO SLTP AF-l1 None 1-CKV-63-559-B 63 1 E-1 AC-Act 6 CKV SELF C B CVO/RO SLTP AF-11 None 1-CKV-63-560-S 63 1 F-i AC-Act 10 CKV SELF C B CVO/RO SLTP CKV-CMP None 1-CKV-63-561-S 63 1 D-1 AC-Act 10 CKV SELF C B CVO/RO SLTP CKV-CMP None 1-CKV-63-562-S 63 1 E-2 AC-Act 10 CKV SELF C B CVO/RO SLTP CKV-CMP None Ill 6 -

1-CKV-63-563-S 63 1 F-2 AC-Act 10. CKV SELF C B CVO/RO SLTP CKV-CMP None 1-CKV-63-581-S 1-CKV-63-586-S 63 63 11 C-6 AC-Act 3.5 CKV SELF C 0 CVO/RO SLTP AF-11 None E-1 AC-Act 1.5' CKV SELF C 0 CVO/ROSLTP AF-i1 None 1-CKV-63-587-S 63 1 D-2 AC-Act 1.5 CKV SELF C 0 CVO/RO SLTP AF-11 None 1-CKV-63-588-S 63 1 E-2 AC-Act 1.5 CKV SELF C 0 CVO/RO SLTP AF-11 None 1 -CKV-63-589-S 63 1 F-2 AC-Act 1.5 0 KV SELF C 0OCVO/RO SLTP AF-11 None 1-CKV-63-622-S 63 1 D-1 AC-Act 10 CKV SELF C B CVO/RO SLTP CKV-CMP None 1-CKV-63-623-S 63 1 D-1 AC-Act 10 CKV SELF C B CVO/RO SLTP CKV-CMP None 1-CKV-63-624-S 63 1 D-3 AC-Act 10 0KV SELF C B CVO/RO SLTP CKVCMP None 1-CKV-63-625-S 63 1 D-3 AC-Act 10 I-I CKV SELF C-- B CVO/RO SLTP CKV-CMP None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 29 of 73 Table 2, Summary Listing of Valves Page 16 of 31 C C NA L 0 PP S A 0 00 ALT. REL.

Y S R SS FREQ. REQ.

VALVE NUMBER I S S D CAT SIZE TYPE ACTR I I I TESTS JUST. NUM.

Drawing Number 1-47W811-1 (continued) 1-CKV-63-632-A 63 1 H-2 AC-Act 6 CKV SELF C B CVO/RO SLTP AF-18 None 1-CKV-63-633-B 63 1 G-1 AC-Act 6 CKV SELF C B CVO/RO SLTP AF-18 None 1-CKV-63-634-A 63 1 G-3 AC-Act 6 CKV SELF C B CVO/RO SLTP AF-18 None 1-CKV-63-635-B 63 1 G-1 AC-Act 6 CKV SELF C B CVO/RO SLTP AF-18 None 1-CKV-63-640-S 63 11 G-3 AC-Act 8 CKV SELF C B CVO/RO SLTP AF-18 None 63 I-1-CKV-63-641-S 63 1 F-i AC-Act 6 CKV SELF C B CVO/RO SLTP AF-18 None 1-CKV-63-643-S 63 1 F-3 AC-Act 8 CKV SELF C B CVO/RO SLTP AF-1 8 None 1 -CKV-63-644-S 63 1 D-2 AC-Act 6 CKV SELF C B CVO/RO SLTP AF-18 None 1-CKV-63-725 63 2 E-8 C-Act 2 CKV SELF C B CVO/DIFCVC/DIF CKV-CMP None 1-FCV-63-1-A 63 22 E-10 1-FCV-63-3-A 63 E-8 B-Act B-Act 14 2 GATE GLOBE MOV MOV 0 C 0 C STC/CSD RPI STC/CSD RPI AF-19 AF-20 None None 1-FCV-63-4-B 63 2 E-8 B-Act 2 GLOBE MOV 0 C STC/Q RPI None None 1-FCV-63-5-B 63 2 D-10 B-Act 6 GATE MOV 0 C STC/CSD RPI AF-19 None 1-FCV-63-6-B 63 2 F-10 B-Act 4 GATE MOV 0C STO/Q RPI None None 1-FCV-63-7-A 63 2 F-1 0 B-Act 4 GATE MOV C 0 STO/Q RPI None None 1-FCV-63-8-A 63 2 H-9 B-Act 8 GATE MOV C 0 STO/RO RPI AF-21 None 1-FCV-63-1 1-B 63 2 H-9 B-Act 8 GATE MOV C 0 STO/RO RPI AF-21 None 1-FCV-63-22-B 63 2 E-6 B-Act 4 GATE MOV 0 C STC/CSD RPI AF-22 None 1-FCV-63-23-B 63 2 E-7 A-Act 1 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-63-25-B 63 2 B-7 B-Act 4 GATE MOV C 0 STO/CSD RPI AF-23 None 1-FCV-63-26-A 63 2 B-7 B-Act 4 GATE MOV C 0 STO/CSD RPI AF-23 None 1-FCV-63-47-A 63 2 E-10 B-Act 6 GATE MOV 0 C STC/Q RPI None None 1-FCV-63-48-B 63 2 E-10 B-Act 6 GATE MOV 0 C STC/Q RPI None None 1-FCV-63-67-B 63 1 B-5 B-Act 10 GATE MOV 0 C STC/RO RPI AF-24 None 1-FCV-63-71-A 63 2 D-6

- A-Act 0.75 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None II I

I WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Paqe 30 of 73 Table 2, Summary Listing of Valves Page 17 of 31 L 0 PP S A 0 00 ALT. REL.

Y S R S5 FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W811-1 (continued) 1 6-1-FCV-63-72-A 63 2 H-7 B-Act 18 GATE MOV C 0 STO/RO RPI AF-25 None 1-FCV-63-73-B 63 2 H-7 B-Act 18 GATE MOV C 0 STO/RO RPI AF-25 None 1-FCV-63-80-A 63 1 B-4 B-Act 10 GATE MOV 0 C STC/RO API AF-24 None 1-FCV-63-84-B 63 2 C-6 A-Act 0.75 GLOBE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-63-93-A 63 22 G-7 1-FCV-63-94-B 63 G-7 B-Act B-Act 88 GATE GATE MOV MOV 00 C C STC/CSD STC/CSD RPI RPI AF-26 AF-26 None None 1-FCV-63-98-B 63 1 B-3 B-Act 10 GATE MOV 0 C STC/RO RPI AF-24 None 1-FCV-63-118-A 63 1 B-1 B-Act 10 GATE MOV 0 C STC/RO RPI AF-24 None 1-FCV-63-152-A 63 2 F-7 B-Act 4 GATE MOV 0 C STC/Q RPI None None 1-FCV-63-153-B 63 2 E-7 B-Act 4 GATE MOV 0 C STC/Q RPI None None 1-FCV-63-156-A 63 2 F-6 B-Act 4 GATE MOV C C STO/Q RPI None None 1-FCV-63-157-B 63 2 D-6 B-Act 4 GATE MOV C 0 STO/Q RPI None None 1-FCV-63-172-B 63 2 F-6 B-Act 12 GATE MOV C 0 STO/CSD RPI AF-26 None 1-FCV-63-175-B 63 2 E-8 B-Act 2 GLOBE MOV 0 C STC/Q RPI None None 1-FCV-63-177 63 2 F-10 B-Pas 4 GATE MOV 0 0 APi None None 1-FCV-63-185 63 2 E-6 B-Act 0.75 GLOBE DIAPH 0 C STC/Q FSC RPI None None 1-RFV-63-28 63 2 D-6 AC-Act 0.75x1 SFV SELF C 0 RV SLTJ None None 1-RFV-63-511-S 63 2 E-10 C-Act 0.75x1 SFV SELF C 0 RV None None 1-RFV-63-534-A 63 2 E-7 C-Act 0.75x4 SA SELF C 0 RV None None 1-RFV-63-535-S 63 2 E-7 C-Act 0.75x1 SFV SELF C 0 RV None None 1--RFV-63-536- 63 2 1-7 C-Act 0.75X SFV SELF CIO RV None None 1-RFV-63-536-B 63 2 D-7 C-Act 0.75x1 SFV SELF C 0 RV None None 1-RFV-63-577-S 63 2 A-7 C-Act 0.75x1 SFV SELF C 0 RV None None 1-RFV-63-602-S 63 2 A-2 C-Act 0.75x1 SFV SELF C 0 RV None None 1-RFV-63-603-S 63 2 A-3 C-Act 0.75x1 SFV SELF C 0 RV None None 11-AFV-63-604-S 1631 2 1A-4 IC-Act 10-75X11 SWV SELFICI0 RV None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 31 of 73 Table 2, Summary Listing of Valves

_ Page 18 of 31 C C NA L 0 P P S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER I S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W811-1 (continued) 1-RFV-63-605-S 63 2 A-6 C-Act 075x1 SFV SELF C CRV None None 1-RFV-63-626-A 63 2 G-7 C-Act 2x3 SFV SELF C C RV None None 1-RFV-63-627-B 63 2 F-7 C-Act 2x3 SFV SELF C CRV None None 1-RFV-63-637-S 63 2 F-7 C-Act 0275x3 SFV SELF C CRV None None 1-RFV-63-835 63 2 E-10IC-Act 0.75xl SFV,. SELF _ _ _ _ _ _ _ None None Drawing Number 1-47W830-6 1-FCV-63-64-A 63 2 B-6 A-Act 1 GATE DIAPH 0 CSTC/Q FSC RPI SLTJ None None 1-FCV-68-305-A 68 2 G-7 A-Act 0.75 GLOBE DIAPH 0 CSTC/Q FSC RPI SLTJ None None 1-CKV-68-849 68 2 G-7 AC-Act 1 CKV SELF 0oC CVC/CSD BDO/NO SLTJ AF-30 None 1-CKV-63-868 63 2 B-7 AC-Act 1 CKV SELF O CCVC/CSD BDO/NO SLTJ AF-30 None Drawing Number 1-47W845-1 67m-CKV-67-502A-A 3 E-8 C-Act 2 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-502B-A 67 3 E-6 C-Act 2 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-502C-A 67 3 F-6 C-Act 2 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-502D-A 67 3 F-8 C-Act 2 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-502E-B 67 3 F-4 C-Act 2 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-502F-B 67 3 F-6 C-Act 2 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-502G-B 67 3 E-6 C-Act 2 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-502H-B 67 3 E-4 C-Act 2 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-503A-A 67 3 E-8 C-Act 20 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-503B-A 67 3 D-7 C-Act 20 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-503C-A 67 3 F-7 C-Act 20 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-503D-A 67 3 F-8 C-Act 20 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-503E-B 67 3 F-4 C-Act 20 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-503F-B 67 3 F-5 C-Act 20 CKV SELF B B CVO/Q CVC/Q None None 0-CKV-67-503G-B 67, 3 E-5 C-Act 20 CKV SELF B B CVO/Q CVC/Q None I-KV6I53FB 7 -SC-c 20 0K SEL BI V/ V/oe None Nn

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 32 of 73 Table 2, Summary Listing of Valves Page 19 of 31 C C NA LO P P S A 0 001 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER I S S D CAT SIZE TYPE ACTR I I1 TESTS JUST. NUM.

Drawin' Number 1-47W845-1 (continued) 0-CKV-67-503H-B 67 3 E-4 C-Act 20 CKV SELF B B CVO/Q CVC/Q None None 1-CKV-67-508A-A 67 3 C-10C-Act 8 CKV SELF 0 CCVC/DIFrBDO/NO CKV-CMP None 1-CKV-67-508B-B 67 3 C-5 C-Act 8 CKV SELF 0 C CVC/DIF BDO/NO CKV-CMP None 1-CKV-67-940A-A 67 N H-6 C-Act 3 CKV SELF C 0 CVO/Q BDC/RO CKV-CMP None 1-FCV-67-9A-A 67 3 G-9 B-Act 4 BALL MOV C 0 STO/Q None None 1 6-BC 1-FCV-67-9B-A 67 3 F-9 B-Act 4 BALL MOV C 0 STO/Q None None 1 -FCV-67-1 OA-B 67 3 F-3 B-Act 4 BALL MOV C 0 STO/Q None None 1 -FCV-67-150B-B 67 3 F-3 B-Act 4 BALL MOV C 0 STO/Q None None 1-RFV-67-509A-A 67 3 B-4 C-Act 0.75xl SFV SELF C O TRV None None 1-RFV-67-509B-B 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-514A-A 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-514A-A 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1042B-B 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1042B-B 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 2-CKV-67-508A-A 67 3 C-5 C-Act 8 CKV SELF 0 C CVC/DIFBDO/NO CKV-CMP None 2-CKV-67-508B-B 67 3 C-10 C-Act 8 CKV SELF 0 C CVC/DIF BDO/NO CKV-CMP None 2-CKV-67-935B-B 67 N H-6 C-Act 3 CKV SELF C 0 CVO/Q BDC/RO CKV-CMP None 2-FCV-67-9A-A 67 3 G-9 B-Act 4 BALL MOV C 0 STO/Q None None 2-FCV-67-9B-B 67 3 F-9 B-Act 4 BALL MOV C 0 STO/Q None None 2-FCV-67-1 OA-B 67 3 G-3 B-Act 4 BALL MOV C 0 STO/Q None None 2-FCV-67-1OB-B 67 3 H-3 B-Act 4 BALL MOV C 0 STO/Q None None 2-RFV-67-509A-A 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-509B-B 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-514A-A 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-514B-B 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None

-- - 6 -

2-RFV-67-1043A-A 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-1043B-B 67 3 B-4 C-Act 0.75x1, SR SELF C 0 TRV None None

WATTS BAR NUCLEAR PLANT LWBN _ _

SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Paqe 33 of 73 Table 2, Summary Listing of Valves Pa.e 20 of 31 C C N A L 0 PP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZEI TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W845-2 0-FCV-67-144 67 3 C-6 B-Act 16 GLOBE MOV 0 C STC/Q RPI None None 0-FCV-67-152-B 67 3 C-6 B-Act 24 BTFY MOV B B STO/Q STC/Q RPI None None 0-RFV-67-550-B 67 3 C-6 C-Act 0.75xl SFV SELF C 0 TRV None None 0-RFV-67-1021A-A 67 3 A-10 C-Act 0.75xl SFV SELF C 0 TRV None None 0-RFV-67-1021 1-FCV-67-123-BB-B 67 67 33 B-9 D-9 C-Act B-Act 0.75xl 18 SFV SELF C 0 TRV BTFY MOVcoCOSTC/RORPI None AF-12 None None 1-FCV-67-124-B 67 3 E-8 B-Act 18 BTFY MOV C 0 STC/RO RPI AF-12 None 1-FCV-67-125-A 67 3 C-9 B-Act 18 BTFY MOV C 0 STC/RO RPI AF-1 2 None 1-FCV-67-126-A 67 3 D-7 B-Act 18 BTFY MOV C 0 STC/RO RPI AF-12 None 1-FCV-67-143-A 67 3 C-8 B-Act 12 GLOBE MOV B B STO/Q STC/Q RPI None None 1-ISV-67-523B-B 67 3 F-10 B-Act 10 BTFY MAN 0 C MS None None 1-RFV-67-539A-A 5 67 3 D-8 C-Act 2x2 SFV SELF C 0 RV None None 1-RFV-67-539B-B 5 67 3 D-8 C-Act 2x2 SFV SELF C 0 RV None None 1-RFV-67-550 67 3 C-7 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1020A-A 67 3 F-8 C-Act 0.75xl SFV SELF C 0 TRV 1-RFV-67-1020B-B 67 3 E-8 C-Act 0.75xl SFV SELF C None None TRV None m None 1-RFV-67-1022-A 67 3 B-11 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-550-A 67 3 B-5 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-1044-B 67 3 B-3 C-Act 0.75x1 SFV SELF C 0 ITRV None None Drawing Number 1-47W845-3 1-CKV-67-575A-A 67 2 H-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-67-575B-B 67 2 E-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-67-575C-A 67 2 G-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-67-575D-B 67 2 D-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-67-580A-A 67 -

2 C-7 i m AC-Act 2 CKV SELF 0 C CVC/Q BDO/NO SLTJ None None i* I

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Paqe 34 of 73 Table 2, Summary Listing of Valves Page 21 of 31 L 0 PP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

1- V_ Number 1-47W845-3 (continued)

Drawin mC 1-CKV-67-580B-B 67 2 8-7 AC-Act 2 CKV SELF 0 C CVC/Q BDO/NO SLTJ None None 1-CKV-67-580D-A 67 2 B-7 AC-Act 2 CKV SELF 0 C CVC/Q BDO/NO SLTJ None None 1-CKV-67-585D-B 67 2 A-7 AC-Act 2 CKV SELF 0 C CVC/Q BDO/NO SLTJ None None 1-CKV-67-585A-A 67 2 D-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-67-585B-B 67 67 22 B-7 1 CKV-67-585C-A C-7 AC-Act AC-Act 0.5 0.5 CKV ISELF SELF CB CVO/RO CVO/RO CVC/RO C B-CKV CVC/RO SLTJ SLTJ CKV-OMP CKV-CMP None None 1-CKV-67-585D-B 67 2 A-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-67-1054A-A 67 2 H-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-67-1054B-B 67 2 E-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-67-1054C-A 67 2 G-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-67-1054D-B 67 2 D-7 AC-Act 0.5 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-FCV-67-83-A 67 2 H-8 A-Act 6 IBTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-87-A 67 2 H-7 A-Act 06 BTFY MOV C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-88-B 67 2 H-8 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-89-B 67 2 H-7 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-98-B 1-FCV-67-91-A 67 67 2 2 H-8 H-7 A-Act 6 BTFY MOV 0 0 STC/OSD RPI SLTJ AF-29 None A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-95-A 67 2 F-8 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-96-B 67 2 G-8 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-95-A 67 2 F-7 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-99-B 67 2 F-8 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-17-B 1-FCV-67-103-A 67 67 2 2 G-7 F-7 A-Act A-Act 6 6 BTFY BTFY MOV MOV 0 0 0C STC/CSD STC/CSD RPI RPI SLTJ SLTJ AF-29 None AF-29 None 1-FCV-67-107-A 67 2 E-8 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-111-B 67 2 D-7 A-Act -

6 - -

BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 I None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Paae 35 of 73 Table 2, Summary Listing of Valves Pa.e 22 of 31 C C NA L 0 P P S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W845-38 continued 6 - -0 -2 1-FCV-67-112-A 67 2 D-8 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1 -FCV-67-1 13-A 67 2 E-7 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-67-130-A 67 2 C-8 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-131-B 67 2 0-8 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-1 33-A 67 2 B-8 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-134-B 67 2 1-8 A-Act 2 PLUG IMOV C STC/Q RPI SLTJ None None 1-FCV-67-134-B 67 2 C-8 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-138-B 67 2 B-8 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-139-A 67 2 B-8 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-1412-B 67 2 A-8 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-142-A 67 2 A-8 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-295-A 67 2 C-7 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-296-A 67 2 C-7 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-297-B 67 2 B-7 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-FCV-67-298-B 67 2 A-7 A-Act 2 PLUG MOV 0 C STC/Q RPI SLTJ None None 1-RFV-67-566A-A 67 33 H-5 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV67-566B-B 67 F-5 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-566C-A 67 3 G-5 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-566D-B 67 3 E-5 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-573A-A 67 3 G-6 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-573B-B 67 3 E-6 C-Act 0.75xl SFV SELF C O TRV None None 1-RFV-67-573C-A 67 3 F-6 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-573D-B 67 3 D-6 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-582A-A 67 3 C-3 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-582B-B 67 3 B-3 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-582C-A 67 3 --

B-3 C-Act 0.75xl SFV SELF C -i 0 TRV None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 36 of 73 Table 2, Summary Listing of Valves Page 23 of 31 L 0 P S A 0 0O ALT. REL.

Y S R TEST FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I _ __ TESTS __ JUST. NUM.

Drawing Number 1-47W845-3 (continued) ,,,

1--RFV-67-582D-B 67 3 A-3 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1022A-A 67 3 H-4 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1022B-B 67 3 F-4 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1022C-A 67 3 G-4 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1022D-B 67 31 D-4 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1024A-A 67 3 H-3 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1024B-B 67 3 F-3 C-Act 0.75xl SFV SELFC C TRV None None 1-RFV-67-1024C-A 67 3 G-3 C-Act 0.75xl SFV SELF C £TRV None None 1-RFV-67-1024D-B 67 3 D-3 C-Act 0.75xl SFV SELF C fTRV None None 1-RFV-67-1025A-A 67 3 H-6 C-Act 0.75xl SFV SELF C TRV None None 1-RFV-67-1025B-B 67 3 F-6 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1025C-A 67 3 G-6 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1025D-B 67 3 D-6 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1026A-A 67 3 C-3 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1026B-B 67 3 B-3 C-Act 0.75xl SFV SELF C CTRV None None 1-RFV-67-1026A-A 1-RFV-67-1026B-B 67 33 0-3 JC-Act 0.75X1 SFV ISELFCTRV None None 67 B-3 C-Act 0.75xl SFV SELF C TRV None None 1-RFV-67-1026D-B 67 3 A-3 C-Act 0.75xl SFV SELF JCC TRV None *None Drawing Number 1-47W845-4 0-RFV-67-671-A 67 3 B-10 C-Act 0.75xl SFV SELF C CRV None None O-RFV-67-1039A-A 67 3 H-4 C-Act 0.75xl SFV SELF C TRV None None 0-RFV-67-1039B-B 67 3 H-6 C-Act 0.75xl SFV SELF C CTRV None None 1-FCV-67-162 67 3 B-4 B-Act 2 GLOBE DIAPH C C STO/Q FSO RPI None None 1-FCV-67-164 67 3 B-6 B-Act 2 GLOBE DIAPH C CSTO/Q FSO RPI None None m1nn D _________ - B__C____Nno - __1G 1-FCV-67-176 67 3 D-4 B-Act 1.5 GLOBE DIAPH C C STO/Q FSO RPI None None 1-FCV-67-182 67 3 D-6 B-Act 1.5 GLOBE DIAPH C C STO/Q FSO RPI None None 1-FCV-67-184 67 3 D-4 B-Act 1.5 IGLOBE DIAPH C CSTO/Q FSO RPI None None 1-FCV-67-186 67 3 D-6 B-Act 1.5 IGLOBE DIAPH C CSTO/Q FSO RPI None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES I Paqe 37 of 73 Table 2, Summary Listing of Valves Page 24 of 31 L 0 PP S A 0 00 ALT. REL.

Y S R SS FREQ. REQ.

VALVE NUMBER I S S D CAT SIZE I TYPE ACTRIII TESTS JUST. NUM.

Drawing Number 1-47W845-4 (continued) 11N 1-FCV-67-213 67 3 A-4 B-Act 1.5 GLOBE DIAPH C 0 STO/Q FSO RPI None None 1-FCV-67-215 67 3 B-6 B-Act 1.5 GLOBE DIAPH C 0 STO/Q FSO RPI None None 1-FCV-67-342 67 3 G-4 B-Act 2 GLOBE DIAPH C 0 STO/Q FSO RPI None None 1-FCV-67-344 67 3 G-6 B-Act 2 GLOBE DIAPH C 0 STO/Q FSO RPI None None 1-FCV-67-346 67 3 F-4 B-Act 1.5 GLOBE DIAPH C 0 STO/Q FSO RPI None None 1-FCV-67-348 67 3 F-4 B-Act- 1.5 GLOBE DIAPH C STO/Q FSO RPI None None 1-FCV-67-350 67 3 F-6 B-Act 1.5 GLOBE DIAPH C 0 STO/Q FSO RPI None None 1-FCV-67-352 67 3 F-4 B-Act 1.5 GLOBE DIAPH C O STO/Q FSO RPI None None 1-FCV-67-354 67 3 G-6 B-Act 1.5 GLOBE DIAPH C 0 STO/Q FSO RPI None None 1-FCV-67-356 67 3 G-6 B-Act 1.5 GLOBE DIAPH C 0 STO/Q ESO RPI None None 0-FSV-67-1221-A 67 3 B-12 B-Act 1 GATE SOL C 0 STO/Q FSO None PV-04 1-RFV-67-1027A-A 67 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1027B-B 67 3 B-7 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1028A-A 67 3 B-3 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1028B-B 67 1II-3 C-7 jC-Act 0.75xl SFV SELF C O TRV None - None 1-RFV-67-1029A-A 67 3 C-2 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1029B-B 67 3 C-8 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1030B 67 3 C-8 C-Act 0.75xl SFV SELF C O TRV None None 1-RFV-67-1031 A-A 67 3 D-2 C-Act 0.75xl SFV SELF C O TRV None None 1-RFV-67-1031B-B 67 3 D-6 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1032A-A 67 3 D-8 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1032A-A 67 3 D-2 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1033B-B 67 3 E-8 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1033A-A 67 3 E-2 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1034A-A 67 3 F-2 C-Act 0.75xl SFV SELF C 0 TRV None None

-iN ---

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 38 of 73 Table 2, Summary Listing of Valves Page 25 of 31 L 0 PP SA 0 00 ALT. REL.

YS R SS FREQ. REQ.

VALVE NUMBER S S D I CAT SIZE TYPE ACTR I TESTS JUST. I NUM.

Drawing Number 1-47W845-4 (continued) 1-RFV-67-1034B-B 67 3 F-8 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1035A-A 67 3 F-3 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1035B-B 67 3 F-8 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1036A-A 67 3 F-2 C-Act 0.75xl SFV SELF C O TRV None None 1-RFV-67-1036B-B 67 3 G-8 C-Act 0.75xl SFV SELF C O TRV None None 1-RFV-67-1038A-A 67 3 G-2 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-67-1038B-B 67 3 G-8 C-Act 0.75xl SFV SELF C 0 TRV None None Drawing Number 1-47W845-5 0-FCV-67-205-A 671 3 1 H-2 B-Act 4 j BTFY 1MOV 1 0 1CSTC/Q RPI None None 0-FCV-67-208-B 67 3 H-3 B-Act 4 BTFY MOV 0 C STC/Q RPI iNone None Drawing Number 1-47W845-7 O-RFV-67-672-B 67 3 B-12 C-Act 0.75xl SFV SELF C 0 RV None None O-FSV-67-1223-B 67 3 A-10 B-Act 1 GATE SQL C 0 STO/Q FSO None PV-04 2-FCV-67-217 67 3 C-4 B-Act 2 GLOBE DIAPH C 0 STO/Q FSO RPI None None 2-FCV-67-219 67 3 C-6 B-Act 2 GLOBE DIAPH C 0 STO/Q FSO RPI None None 2-FCV-67-336 67 3 A-4 B-Act 1 GLOBE DIAPH C 0 STO/Q FSO RPI None None 2-FCV-67-338 67 3 A-6 B-Act 1 GLOBE DIAPH C STO/Q FSO RPI None None 2-FCV-67-354 67 3 F-4 B-Act 1.5 GLOBE DIAPH C 0 STO/Q FSO RPI None None 2-FCV-67-356 67 3 F-6 B-Act 1.5 GLOBE DIAPH C 0 STO/Q FSO RPI None None 2-RFV-67-1037A-A 67 3 G-2 C-Act 0.75xl SFV SELF C TORV None None 2-RFV-67-1037B-B 67 3 G-8 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-1040A-A 67 3 B-3 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-1040B-B 67 3 B-7 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-1041A-A 67 3 A-2 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-67-1041 B-B 67 3 A-8 C-Act 0.75xl SFV SELF C 0 TRV None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL I1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 39 of 73 Table 2, Summary Listing of Valves Page 26 of 31 L 0 p S A 0 00 ALT. REL.

Y S R SS FREQ. REQ.

VALVE NUMBER I S S Drawin gN um ber 1-47W625-8 D CAT SIZE TYPE ACTRI I __ _ _ _ TESTS JUST. _

NUM._ _ _

1-FCV-68-307-A 681 2 1 G-2 IA-Act 0.375 GATE DIAPH 0 ICISTC/Q FSCORPI SLTJ None None 1-FCV-68-308-B 68 2 F-1 A-Act 0.375 GATE I DIAPH 0 C STC/Q FSC RPI SLTJ None None Drawinq Number 1-47W813-1 1-CKV-68-559-S 68 2 H-4 C-Act 4 CKV SELF C B CVC/DIF CVO/DIF CKV-CMP None 1-FCV-68-22 68 2 B-8 B-Pas 0.375 GLOBE DIAPH 0 0 RPI None None 1-FCV-68-332-B 68 1 C-2 B-Act 3 GATE MOV 0 C STC/Q RPI None None 1-FCV-68-333-A 68 1 B-2 B-Act 3 GATE MOV 0 C STC/Q RPI None None 1-FSV-68-394-A 68 2 F-7 B-Act 1 GLOBE SOL C O STO/CSD STC/CSD FSC RPI AF-28 None 1-FSV-68-395-B 68 2 G-7 B-Act 1 GLOBE SOL C 0 STO/CSD STC/CSD FSC RPI AF-28 None

-ESIV-68-396-B 68 2 F-5 B-Act 1 GLOBE SOL C 0 ET/CSD ES API AF-28 PV-03 1-FSV-68-397-A 68 2 G-6 B-Act 1 GLOBE SOL C 0 ET/CSD FSC RPI AF-28 PV-03 1-PCV-68-334-B 68 1 C-i B-Act 3 GLOBE SOL C B STO/RO STD/RO FSC RPI None None 1-PCV-68-340A-A 68 1 B-1 B-Act 3 GLOBE SOL C B STO/RO STC/RO FSC RPI None None V - 3 C 11-RFV-68-563-S 68 1 A-3 C-Act 6x6 SFV SELF C 0 RV None None 1-RFV-68-564-S 68 1 A-2 C-Act 6x6 SFV SELF C O RV None None 1-RFV-68-565-S 68 1 A-2 C-Act 6x6 SFV SELF C 0 RV None None Drawing Number 1-47W859-1 0-CKV-70-504-B 70 3 D-7 C-Act 16 CKV SELF B B CVO/Q CVC/Q None None 0-FCV-70-197-A 70 3 B-5 B-Act 20 BTFY MOV 0 C STC/Q RPI None None 0-RFV-70-527A 70 3 H-4 C-Act 0.75x1 SFV SELF C 0 TRV None None 0-RFV-70-527B 70 3 H-6 C-Act 0.75x1 SFV SELF C 0 TRV None None 1-CKV-70-504A-A 70 3 B-7 C-Act 16 CKV SELF B B

- - CVO/Q CVC/Q None None 1-CKV-70-504B-S 70 3 C-7 C-Act 16 CKV SELF B B CVO/Q CVC/Q None None 1-FCV-70-66 70 3 E-3 B-Act 2 ANG DIAPH 0 C STC/Q FSCORPI None None

-ISV-70-516 70 3 B-5 B-Act 8 BTFY MAN 0 C MS None None 1-RFV-70-538-S 70 I 3- E-3

- C-Act 3x4 SFV SELF C OIRV I m None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 40 of 73 Table 2, Summary Listing of Valves Pa e 27 of 31 C C N A L 0 P p S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I ITESTS JUST. NUM.

Drawing Number 1-47W859-1 (continued_

1-RFV-70-539-S 70 3 E-3 C-Act 3 SFV SELF C 0 RV None None 1-RFV-70-521 70 3 A-10 C-Act 0.75xl SFV SELF C 0 TRV None None 2-FCV-70-66 70 3 E-3 B-Act 2 ANG DIAPH 0 C STC/Q FSC RPI None None 2-RFV-70-521 70 3 A-1 C-Act 0.75X1 SFV SELF C 0 ITRV None None Drawing Number 1-47W859-2 1-CKV-70-679 70 2 H-3 AC-Act 3 CKV SELF 0 C CVC/CSD BDO/NO SLTJ AF-29 None 1-CKV-70-681A 70 3 G-8 C-Act 2 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-70-681 B 70 3 F-8 C-Act 2 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-70-681 C 70 3 F-8 C-Act 2 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-70-681D 70 3 H-8 C-Act 2 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1

__7G2SFN 1-CKV-70-682A 70 3 G-8 C-Act 2 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-70-682B 70 3 F-8 C-Act 2 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-70-682C 70 3 E-8 C-Act 2 CKV SELF 0 C CVC/RO BDO/NO CKV-CMP None 1-CKV-70-682D 70 3 H-9 C-Act 2 CKV SELF 0 C CVC/RO BOO/NO CKV-CMP None 1-CKV-70-687 70 2 H-9 AC-Act 0.75 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-CKV-70-698 70 2 E-9 AC-Act 0.75 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP Nlone 1-CKV-70-790 70 2 G-3 AC-Act 0.75 CKV SELF C B CVO/RO CVC/RO SLTJ CKV-CMP None 1-FCV-70-85-B 70 2 D-10 A-Act 6 BTFY DIAPH 0 C STC/Q RPI SLTJ None None 1-FCV-70-87-B 70 2 H-9 A-Act 3 GATE MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-70-89-B 70 2 E-9 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1 II -

1-FCV-70-90-A 70 2 F-10 A-Act 3 GATE MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-70-92-A 70 2 E-10 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-70-1 00-A 70 2 G-3 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-70-133-A 70 3 H-3 B-Act 3 GATE MOV 0 C STC/CSD RPI AF-29 None 1-FCV-70-134-B 70 2 H-3 A-Act 3 GATE MOV 0 C STC/CSD RPI SLTJ AF-29 None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL /ý 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES I Pacie 41 of 73 Table 2, Summary Listing of Valves Page 28 of 31 L 0 PP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

Drawing Number 1-47W859-2 (continued) 1-FCV-70-140-B 70 2 G-3 A-Act 6 BTFY MOV 0 C STC/CSD RPI SLTJ AF-29 None 1-FCV-70-143-A 70 2 E-3 A-Act 6 BTFY MOV 0 C STC/Q RPI SLTJ None None 1-FCV-70-183-A 70 3 C-9 B-Act 3 GATE MOV 0 C STC/Q RPI None None 1-FCV-70-215-A 70 3 A-8 B-Act 3 GATE MOV 0 C STC/Q RPI None None 1-ISV-70-700 70 3 E-11 B-Act 6 BTFY MAN O C MS None None 1-RFV-70-703 70 2 E-5 AC-Act 3x4 SFV SELF C 0 RV SLTJ None None 1-RFV-70-578 70 3 A-7 C-Act 0.75xl SFV SELF C 0 RV None None 1-RFV-70-835 70 3 H-6 C-Act 0.75 SFV SELF C 0 RV None None 1-RFV-70-584 70 3 B-6 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-70-683A 70 3 - G-8 C-Act 0.75xl SFV SELF C O TRV None None

-I -

1-RFV-70-683B 70 3 F-8 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-70-683C 70 3 E-8 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-70-683D 70 3 H-8 C-Act 0.75xl SFV SELF C 00 TRV None 1-RFV-70-694 70 3 F-4 C-Act 0.75xl SFV SELF C TRV None Drawing Number 1-47W859-4 1-FCV-70-156-A 70 3 F-4 B-Act 18 BTYF MOV C 0 STO/Q RPI None None 1-RFV-70-551A-A5 70 3 E-5 C-Act 1.5x2 SFV SELF C 0 RV None None 1-RFV-70-551B-B 5 70 3 E-2 C-Act 1.5x2 SFV SELF C 0 RV None None 1-RFV-70-556A-A5 70 3 A-4 C-Act 0.75xl SFV SELF C 0 RV None None 1-RFV-70-556B-B5 70 3 A-2 C-Act 0.75xl SFV SELF C OIRV None None 1-RIW-70-565A-A 70 3 C-4 C-Act 0.75x1 SFV SELF C 0 RV None None 1-RFV-70-565B-B 5 70 3 C-2 C-Act 0.75xl SFV SELF C 0 RV None None 1-RFV-70-5615A 70 3 B-4 C-Act 0.75xl SFV SELF C 0 TRV None None 1-RFV-70-561B 70 3 B-3 C-Act 0.75xl SFV SELF C 0 TRV None oe None Nn

-4 C-c-.5lSVSLFCOIR 1-RV-7-57A 1-RFV-70-570A 70 33 D-4 7

C-Act 0.75xl I SFV SELF C OITRV None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 42 of 73 T

Table 2, Summary Listing of Valves Pa.e 29 of 31 L 0 pPP S A 0 00 ALT. REL.

YS R SS FREQ. REQ.

VALVE NUMBERI S S D CAT SIZE TYPE IACTR I I TESTS JUST. NUM.

Drawinc Number 1-47W859-4 (continued) 1-RFV-70-570B 70 3 D-3 C-Act 0.75xl 2-RFV-70-551A SFV SELF C 0 TRV 70 3 D-11 C-Act 0.75xl SFV SELF C 0 TRV None None 2-RFV-70-556A 70 3 H-1 1 C-Act 0.75x1 SEV SELF C 10 TRV None None None lNone Drawing Number 1-47W812-1 1-CKV-72-506-A 72 2 C-10 C-Act 12 CKV SELF C 0 CVO/Q CVC/Q CKV-CMP None 1-CKV-72-507-B 72 2 B-1 0 C-Act 12 CKV SELF C 0 CVO/DIF CVC/Q CKV-CMP None 1-CKV-72-524-A 72 2 D-6 C-Act 10 CKV SELF C 0 CVO/Q BDC/Q CKV-CMP None 1-CKV-72-525-B 72 2 A-6 C-Act 10 CKV SELF C 0 CVC/DIF CVO/DIF CKV-CMP None 1-CKV-72-548-A 72 22 D-2 IC-Act 10 CKV SELF C 0 CVO/DIF 1-CKV-72-549-B 72 A-2 C-Act 10 CKV SELF C 0 CVO/DIF CVC/DIF CVC/DIF CKV-CMP CKV-CMP None None 1-CKV-72-562-A 72 2 F-2 C-Act 8 CKV SELF C 0 CVO/DIF CVC/DIF CKV-CMP None 1-CKV-72-563-B 72 2 E-2 C-Act 8 CKV SELF C 0 CVO/DIF CVC/DIF CKV-CMP 1-FCV-72-2-B 72 2 A-3 A-Act 10 GATE MOV C 0 STO/Q RPI SLTJ None None None 1-FCV-72-13-B 72 2 B-6 B-Act 2 GLOBE MOV C 0 STO/Q RPI None None I-FCV-72-21 1-FCV-72-22-A -B 72 2 B-60 B-Act 12 GATE MOV C C 72 2 C-l B-Act 12 STC/Q RPI None None 1-FCV-72-34-A3 GATE MOV 0 C STC/Q RPI 72 2 C-6 B-Act 2 GLOBE MOV None None 1-FCV-72-39-A C C STO/Q RPI 72 2 C-3 A-Act 10 GATE None None 1-FCV-72-40-A MOV C C STO/Q RPI SLTJ 72 2 F-3 A-Act 8 GATE None None 1-FCV-72-41-B MOV C 0 STO/RO RPI SLTJ 72 2 E-3 A-Act 8 GATE AF-04 None MOV C 0 STO/RO RPI SLTJ AF-04 None 1-FCV-72-44-A 72 2 G-3 B-Act 12 GATE MOV C 0 STO/RO RPI AF-25 None 1-FCV-72-45-B 1-R FV-72-41 72 22 H-3 B-Act 12 72 E-3 AC-Act 0.75x l GATE SRI MOV C 0 STO/RO RPI SELF AF-25 None 1-RFV-72-40 72 2 F-3 AC-Act 0.75xl SFV SELF C C 00 RV SLTJ None None None None

-I -I - - x- I ~e INn 1-RFV-72-508-A 72 2 C-9-- C-Act 0.75xl

~ SFV SELF C O RV None - None 1-RFV-72-509-B 72 2 A-9 C-Act 0.75xl SFV SELF C 0 RV None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES I Paqe 43 of 73 Table 2, Summary Listing of Valves Pale 30 of 31 C (C N A L 0 PP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBER S S D CAT SIZE TYPE ACTR I I TESTS JUST. I NUM.

Drawing Num ber 1-47 W81 0-1__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ __ _ _ _ _ _

1-CKV-74-514-A 74 2 F-8 C-Act 8 CKV SELF C B CVO/RO CVC/RO AF-1 8 None 1-CKV-74-515-B 74 2 C-8 C-Act 8 CKV SELF C B CVO/RO CVC/RO AF-18 None 1-CKV-74-544-A 74 2 F-5 C-Act 8 CKV SELF C B CVO/RO CVC/Q AF-1 8 None 1-CKV-74-545-B 74 2 C-5 C-Act 8 CKV SELF C B CVO/RO CVC/Q AF-18 None 1-FCV-74-1-A 74 1 G-2 A-Act 14 GATE MOV C 0 STO/CSD SLTP RPI AF-17 None 1-FCV-74-2-B 74 1 G-3 A-Act 14 GATE MOV C 0 STO/CSD SLTP RPI AF-17 None 1-FCV-74-3-A 74 2 F-9 B-Act 14 GATE MOV 0 C STC/Q RPI None None 1-FCV-74-8-A 74 1 G-3 A-Act 10 GATE MOV C 0 STO/CSD SLTP RPI AF-1 7 None 1-FCV-74-9-B 74 1 G-2 A-Act 10 GATE MOV C 0 STO/CSD SLTP RPI AF-17 None 1-FCV-74-12-A 74 2 G-7 B-Act 3 GLOBE MOV 0 B STC/Q STO/Q RPI None None 1-FCV-74-21 -B 74 2 C-9 B-Act 14 GATE MOV 0 C STC/Q RPI None None 1-FCV-74-24-B 74 2 B-6 B-Act 3 GLOBE MOV 0 B STC/Q STO/Q RPI None None 1-FCV-74-33-A 74 2 E-4 B-Act 8 GATE MOV 0 C STC/CSD RPI AF-26 None 1-FCV-74-35-B 74 2 C-4 B-Act 8 GATE MOV 0 C STC/CSD RPI AF-26 None 1-RFV-74-505-S 74 2 H-3 C-Act 3x4 SFV SELF C 0 RV None None Drawing Number 1-47W830-1 1-FCV-77-9-B 77 2 D-1 A-Act 3 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-77-1 0-A 77 2 E-1 A-Act 3 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-77-16-B 77 2 B-5 A-Act 0.75 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-77-17-A 77 2 B-6 A-Act 0.75 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-77-18-B 77 2 B-5 A-Act 1 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-77-19-A 77 2 B-5 A-Act 1 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-77-20-A 77 2 C-5 A-Act 1 DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 11 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES I Paae 44 of 73 Table 2, Summary Listing of Valves Pa.e 31 of 31 L 0 pP S A 0 00 ALT. REL.

Y S R S S FREQ. REQ.

VALVE NUMBERI S S D CAT SIZE TYPE ACTR I I TESTS JUST. NUM.

LDrawing Number 1-47W851-1 1-FCV-77-127-B 77 2 F-7 A-Act 2 PLUG DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-77-128-A 77 2 F-7 A-Act 2 PLUG DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-RFV-77-2875 77 2 F-7 AC-Act 2 SFV SELF C B RV SLTJ 'None 1-1SV-78-557 2D I None N Drawing Number 1-47W855-1 1-ISV-78-557 78 2 G-7 A-Pas 4 DIAPH MAN C C SLTJ None None 4 DIAPH MAN C CSLTJ None None

_-SV-78-5_0 78 2 G-8 A-Pas 1-ISV-78-560 78 2 H-8 A-Pas 6 DIAPH MAN C C SLTJ None None 1-ISV-78-561 78 2 H-7 A-Pas 6 DIAPH MAN C C SLTJ ANone None Drawing Number 1-47W819-1 1-CKV-81-502 1-FCV-81-12-A [1 811 2 1F 4 JAC-Act 2 -4 A-Act 3

3 1 KV ISELF 101 C CVC/CS D BODO/NO SLTJ DIAPH DIAPH 0 C STC/Q FSC RPI SLTJ ~ AF-27 None INone None Drawing Number 1-47W809-7 1-ISV-84-530-S 2 F7 A-Pas 1 1 JGLOBEDMAN C SC/SLTJ INone INone Drawinq Number 1-47W610-90-3 1-FCV-90-108-B 90 2 A-9 A-Act 1.5 GATE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1.5 GATE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-90-107-B 90 2 C-8 A-Act 1.5 GATE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-90-110-B 90 2 C-8 A-Act GATE DIAPH 0 C STC/Q FSC RPI SLTJ None None None None 1-FCV-90-1 10-B 90 2 C-8 A-Act 1.5 1-FCV-90-111-A A 90 22 C-8D-A-Act 1.5 GATE DIAPH 0 C0 C STC/Q STC/Q FSC FSC RPI SLTJ RPI SLTJ None None 90 9 A-Act 1-FCV-90-114-1-FCV-90-1 13-A 90 2 A-5 A-Act 1.5 GATE DIAPH 0 C STC/Q ESO RPI SLTJ None None 1V-FCV-90-114-B 90 2 C-4 A-Act 1.5 GATE DIAPH 0 C STC/Q FSC RPI SLTJ None None 1-FCV-90-115-B 90 2 0-4 A-Act 1.5 GATE DIAPH 0 C STC/Q FSC FSC RPI RPI SLTJ SLTJ None None 1-FCV-90-116-B 90 2 0-4 A-Act 1.5 GATE DIAPH 0 C STC/Q 1-FCV-90-117-A 90 2 C-5 A-Act 1.5 GATE DIAPH 0 C STC/Q ESO RPI SLTJ None None

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 45 of 73 APPENDIX A Page 1 of 13 ALTERNATIVE FREQUENCY JUSTIFICATIONS AF-01 I. Affected Component(s) FCV-1 T, 1-FCV-1 T, 1-FCV-1 T, 1-FCV-1 T (1-47W801 -1)

II. Function of Affected Component(s) - Closes to interrupt loss of SG inventory through a ruptured main steam line. Provides flow boundary isolation between the seismically qualified and non-seismically qualified portions of the main steam system.

I1l. Basis for Alternative Frequency - Closing these valves causes a loss of main steam flow from one steam generator which in turn causes a steam generator level transient, either of which could cause a unit trip and safety injection. Valves are equipped with part stroke capability, however, even a part stroke exercise increases the risk of an inadvertent valve closure when the unit is operating (Reference NUREG-1482, Revision 1, Section 4.2.6, Note 1). In accordance with the manufacturer's recommendation, these valves should only be stroke time tested with steam on the valve.

Therefore, stroke time testing can only be performed during MODE 3 operation, which is during the startup or shutdown sequence.

IV. Proposed Alternative Frequency - Full stroke exercise and stroke time to the closed position each refueling outage.

AF-02 I. Affected Component(s) FCV-1 A, 1-FCV-1 B (1-47W803-2)

I1. Function of Affected Component(s) - Closes to prevent blowdown of main steam in the event of failure of the steam driven auxiliary feedwater pump or of the main steam piping to the pump.

Ill. Basis for Alternative Frequency - Testing these valves to close completely isolates the steam driven auxiliary feedwater pump from its source of steam. Failure of either valve to reopen will cause a complete loss of auxiliary feedwater for the loss of all AC power or station blackout accidents.

IV. Proposed Alternative Frequency - Full stroke exercise to the closed position in conjunction with cold shutdown, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-03 I. Affected Component(s) FCV-1-147-A, 1-FCV-1-148-B, 1-FCV-1-149-A, 1-FCV-1-150-B (1-47W801 -1)

II. Function of Affected Component(s) - Closes to interrupt loss of SG inventory through a ruptured main steam line and to provide flow boundary isolation between the seismically qualified and non-seismically qualified portions of the main steam system during the startup phase of plant operation when the valves are open to provide steam line warming.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 46 of 73 APPENDIX A Page 2 of 13 I1l. Basis for Alternative Frequency - The control circuitry for these valves has been modified to require the valves to be de-energized when unit startup is complete. The valves are then maintained in the de-energized and closed condition during power operation. This modification was made to alleviate 1 OCFR50 Appendix R fire interactions from causing the valves to come open in a spurious fashion. Since the only time period in which these valves serve an active function is during startup, it is not prudent to restore power to the valve and place the valve, which is normally maintained in its fail safe condition, in other than its safe condition.

IV. Proposed Alternative Frequency - Full stroke exercise to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-04 I. Affected Component(s) FCV-72-40-A, 1-FCV-72-41-B (1-47W812-1)

II. Function of Affected Component(s) - Opens to admit RHR pump flow to the RHR Spray Headers Ill. Basis for Alternative Frequency - These valves are electrically interlocked with containment sump valves 1-FCV-63-72-A and 1-FCV-63-73-B in such a manner that the sump valves must be opened to allow the spray valves to open. Opening the containment sump valves during operation requires either draining an extensive portion of the RHR system or allowing it to drain to the containment sump. Draining and refilling these lines requires a considerable amount of time and could extend forced outage duration. Allowing the affected piping to drain to the sump requires extensive cleanup time. Therefore testing during forced outages is not practical.

V. Proposed Alternative Frequency - Full stroke exercise to the open position during refueling outages.

AF-05 I. Affected Component(s) CKV-3-508, 1-CKV-3-509, 1-CKV-3-510, 1-CKV-3-511 (1-47W803-1)

I1. Function of Affected Component(s) - Closes to interrupt main feedwater to prevent a rapid primary side cooldown in the event of a main steam line break and or to prevent loss of steam generator water inventory in the event of a break in the main feedwater line before the isolation valve.

I1l. Basis for Alternative Frequency - Exercising these valves during power operation causes a loss of feedwater to the Steam Generator they supply which in turn causes a steam generator level transient, either of which could result in unit trip and safety injection.

IV. Proposed Alternative Frequency - Full stroke exercise the CKVs to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns. Bi-directional open test is verified during normal operations.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 47 of 73 APPENDIX A Page 3 of 13 AF-06 Affected Component(s) FCV-3-33-A, 1-FCV-3-35, 1-FCV-3-35A, 1-FCV-3-47-B, 1-FCV-3-48, 1-FCV-3-48A, 1-FCV-3-87-A, 1-FCV-3-90, 1-FCV-3-90A, 1-FCV-3-1 00-B, 1-FCV-3-103, 1-FCV-3-103A, 1-FCV-3-236, 1-FCV-3-239, 1-FCV-3-242, 1-FCV-3-245 (1-47W803-1)

IH. Function of Affected Component(s) - Closes to interrupt main feedwater to prevent a rapid primary side cool down in the event of a main steam line break and or to prevent loss of steam generator water inventory in the event of a break in the main feedwater line before the isolation valve.

Ill. Basis for Alternative Frequency - Exercising these valves during power operation causes a change of feedwater flow to the Steam Generator they supply which in turn causes a steam generator level transient, either of which could result in unit trip and safety injection. Stroke time testing of the FCVs is normally performed in MODE 3 during shutdown for a refueling when isolation of feedwater is performed. The test procedure is written to allow performance during MODEs 5 and/or 6, but performance in these modes requires extensive lifting/re-landing of permanent wiring and installation/removal of jumpers and test switches to allow testing of individual valves. MODEs 5 and 6 performance is only used for Post Maintenance Testing purposes on a valve-by-valve bases.

Therefore, testing during forced outages is not practical.

IV. Proposed Alternative Frequency - Full stroke exercise and stroke time the FCVs to the closed position each refueling.

AF-07 Affected Component(s) CKV-3-805-A, 1-CKV-3-806-B, 1-CKV-3-81 0-S, 1-CKV-3-864-S (1-47W803-2)

11. Function of Affected Component(s) - Open to admit auxiliary feedwater to the steam generators during loss of main feedwater. Valves 1-CKV-3-805-A, 1-CKV-3-806-B and 1-CKV-3-81 0-S also close when the Condensate Storage Tank is exhausted to provide a flow boundary for ERCW going to the pump suction.

Ill. Basis for Alternative Frequency - Exercising these valves to their safeguard position requires operating the AFW pumps at full flow to the steam generators while the steam generators are pressurized. The resulting introduction of cold water into the steam generator will cause undesirable thermal fatigue cycles on the feedwater piping and SG feedwater nozzles and will cause level transients due to SG shrink that could result in unit trip and unnecessary actuation of the safety injection system. Testing the valves during return to power operation during mid-cycle shutdowns would delay startup of the plant because the test is performed in MODE 3 in order to flow to the steam generators at full steam generator pressure. Valves 1-CKV-3-805-A, 1-CKV-3-806-B and 1-CKV-3-81 0-S can be back-seated quarterly.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 48 of 73 APPENDIX A Page 4 of 13 IV. Proposed Alternative Frequency - Full stroke exercise the valves to the open position during refueling outages. Full stroke exercise valves 1-CKV-3-805-A, 1-CKV-3-806-B, and 1-CKV-3-810-S to the closed position quarterly.

AF-08 I. Affected Component(s) FCV-62-84-A I1. Function of Affected Component(s) - Valve 1-FCV-62-84-B closes to prevent the loss of reactor coolant system inventory through a break in the Code Class 2 piping behind it and opens to provide auxiliary spray during certain reactor transients.

Ill. Basis for Alternative Frequency - Exercising this valve during power operation results in initiation of auxiliary RCS spray. This causes a quenching effect on the pressurizer steam volume, resulting in a drop in RCS pressure and an increase in pressurizer level. Actuation of auxiliary spray flow also adversely impacts the fatigue evaluation, which accounts for and limits the number of thermal stress cycles to be experienced by the nozzles associated with auxiliary spray.

IV. Proposed Alternative Frequency - Full stroke exercise 1-FCV-62-84 in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-09 I. Affected Component(s) CKV-32-293, 1-CKV-32-303-A, 1-CKV-32-313-B, 1-FCV-32-80-A, 1-FCV-32-102-B, 1-FCV-32-1 10-A (1-47W848-1)

II. Function of Affected Component(s) - Closes to provide containment isolation II. Basis for Alternative Frequency - Exercising these valves to the closed position interrupts the air supply to a number of critical instruments and valves inside containment. Failure of these valves to reopen could cause unstable operation and unit trip by allowing all of the valves and instruments to assume their failed condition.

IV. Proposed Alternative Frequency - Full stroke exercise to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

Bi-directional open test of the check valves is verified during normal operations.

AF-10 1I. Affected Component(s) CKV-61-658, 1-CKV-61-659, 1-CKV-61-660, 1-CKV-61-661, 1-CKV-61-662, 1-CKV-61-663, 1-CKV-61-664, 1-CKV-61-665, 1-CKV-61-666, 1-CKV-61-667, 1-CKV-61-668, 1-CKV-61-669, 1-CKV-61-670, 1-CKV-61-671, 1-CKV-61-672, 1-CKV-61-673, 1-CKV-61-674, 1-CKV-61-675, 1-CKV-61-676, 1-CKV-61-677 (1-47W814-2)

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 49 of 73 APPENDIX A Page 5 of 13

11. Function of Affected Component(s) - Opens during ice melt portion of an accident to drain water into lower compartment to prevent water level in the ice storage compartment from interfering with the operation of the lower inlet doors.

I1l. Basis for Alternative Frequency - Valves are installed on the end of the ice condenser drains inside the biological shield in the lower compartment. Radiation levels in this area during operation prevent entry. The drains are located some distance from the floor, requiring the construction of scaffolding to reach. Therefore it is impractical to try to test the valves during a cold shutdown.

IV. Proposed Alternative Frequency - Full stroke exercise the valve open and closed manually during refueling outages.

AF-1 1 Affected Component(s) CKV-62-504-S, 1-CKV-62-525-A, 1-CKV-62-532-B (1-47W809-1) 1-CKV-63-51 O-S, 1-CKV-63-524-A, 1-CKV-63-526-B, 1-CKV-63-543-A, 1-CKV-63-545-A, 1-CKV-63-547-B, 1-CKV-63-549-B, 1-CKV-63-551 -S, 1-CKV-63-553-S, 1-CKV-63-555-S, 1-CKV-63-557-S, 1-CKV-63-558-B, 1-CKV-63-559-B, 1-CKV-63-581 -S, 1-CKV-63-586-S, 1-CKV-63-587-S, 1-CKV-63-588-S, 1-CKV-63-589-S (1-47W81 1-1)

11. Function of Affected Component(s) - Valves are part of the Emergency Core Cooling System (ECCS). Open to admit flow from the refueling water storage tank through their respective ECCS pumps to the reactor vessel during accidents involving loss of primary system inventory. Several of the valves also close to provide a flow boundary (i.e., prevent reverse flow through a shutdown pump or provide second isolation to RWST during recirculation phase operation).

I1l. Basis for Alternative Frequency - The centrifugal charging pumps cannot be run at full flow through their associated valves without causing undesirable RCS temperature and/or boron concentration changes resulting in changes in reactivity during operations which could result in a plant trip and subsequent safety injection actuation or causing undesirable thermal cyclic stresses which would eventually use all of the design basis for thermal cycles due to a Safety Injection. The safety injection pumps do not develop sufficient head to deliver to the reactor vessel during normal operation. Letdown capacity precludes testing during MODE 5 without compromising cold over pressure protection provisions. Full stroke exercising 1-CKV-62-504-S or 1-CKV-63-51 0-S to the closed position renders both trains of their respective systems inoperable.

IV. Proposed Alternative Frequency - Full stroke exercise to the open position at refueling. Full stroke exercise valves 1-CKV-62-504-S and 1-CKV-63-51 0-S to the closed position at refueling.

AF-12 Affected Component(s) FCV-67-123-B, 1-FCV-67-124-B, 1-FCV-67-125-A, 1-FCV-67-126-A (1-47W845-2)

11. Function of Affected Component(s) - Opens to allow ERCW flow to the Containment Spray [CS]

Heat Exchangers. Valve is normally closed to provide a boundary between the river water in ERCW and the chemically treated water maintained in the CS Heat Exchangers as a corrosion inhibitor.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 50 of 73 APPENDIX A Page 6 of 13 Ill. Basis for Alternative Frequency - Opening these valves allows river water from ERCW to enter the heat exchangers. As a result, the lay-up water chemistry [such as chloride content] cannot be maintained without draining and refilling the heat exchangers followed by recirculating the water through a portable demineralizer.

IV. Proposed Alternative Frequency - Full stroke exercise to the open position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-13 I. Affected Component(s) CKV-62-930 (1-47W809-2)

II. Function of Affected Component(s) - Opens to pass emergency boration flow to the CCP suction.

Ill. Basis for Alternative Frequency - Passing emergency boration flow through this valve during operation results in undesirable boration of the RCS. This could cause undesirable changes in rod position to compensate for the negative reactivity insertion. Testing during mid-cycle cold shutdown would also cause a negative reactivity insertion which could adversely affect the length of time required to dilute to an operating boron concentration or adversely impact the reactivity balance during shutdown conditions.

IV. Proposed Alternative Frequency - Full stroke exercise to the open position once per refueling cycle.

AF-1 4 I. Affected Component(s) FCV-62-61 -B, 1-FCV-62-63-A (1-47W809-1)

I1. Function of Affected Components - Closes to provide containment isolation.

I1l. Basis for Alternative Frequency - Exercising valves during operation would cause loss of seal water return to and potentially damage the reactor coolant pump seals, resulting in high seal losses with resultant maintenance, contamination and clean up problems.

IV. Proposed Alternative Frequency - Full stroke exercise to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-15 I. Affected Component(s) FCV-62-69-S, 1-FCV-62-70-S, 1-FCV-62-77-B, 1-FCV-62-90-A, 1-FCV-62-91-B (1-47W809-1)

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 51 of 73 APPENDIX A Page 7 of 13

11. Function of Affected Components FCV-62-69 and 1-FCV-62-70 close in response to a low pressurizer level, prior to receipt of a reactor trip to isolate the Code Class 2 piping behind them.

1-FCV-62-90-A and 1-FCV-62-91-B close to isolate the normal charging and letdown lines during a safety injection. 1-FCV-62-77-B closes to provide containment isolation.

Ill. Basis for Alternative Frequency - Exercising these valves to the position required to fulfill their safety function causes a loss of flow in either the charging or letdown portions of the Chemical and Volume Control System. As described in the Westinghouse letter to TVA, WAT-D-8347 (RIMS T33 911231 810), isolation of the charging and letdown lines during operation can result in a thermal transient at the charging nozzle of from 500 degrees F to 70 degrees F in a two to five minute period. This results in an increase in the fatigue usage factor beyond that assumed for the original design analysis of these systems.

IV. Proposed Alternative Frequency - Full stroke exercise the valves to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-16 Affected Component(s) FCV-62-1228-A, 1-FCV-62-1229-B, 1-LCV-62-132-A, 1-LCV-62-133-B, 1-LCV-62-135-A, 1-LCV-62-136-B (1-47W809-1)

I1. Function of Affected Component(s) - The LCVs change position to realign charging pump suction from the Volume Control Tank to the RWST during safety injection. The FCVs are normally open to vent hydrogen from the charging pump suction but change position to provide a flow boundary during safety injection.

IIl. Basis for Alternative Frequency - Cycling these valves during operation results in the charging pumps taking suction from the RWST for normal charging requirements. This will result in addition of borated water which has a different boron concentration than that in the reactor coolant system since the likelihood of both the RWST and the RCS being at the same boron concentration at the same time is very small. The change in boron concentration in the RCS caused by charging from the RWST during testing would cause unstable unit operation, especially if any of the valves fail to return to their normal position. The FCVs are electrically interlocked with the LCVs in such a manner that if they are stroked independently of the LCVs, position indication and consequently the ability to time the valves is lost.

IV. Proposed Alternative Frequency - Full stroke exercise 1-FCV-62-1228-A, 1-FCV-62-1229-B, 1-LCV-62-132-A and 1-LCV-62-133-B to the closed position and 1-LCV-62-135-A and 1-LCV-62-136-B to the open position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 52 of 73 APPENDIX A Page 8 of 13 AF-17 Affected Component(s) FCV-74-1-A, 1-FCV-74-2-B, 1-FCV-74-8-A, 1-FCV-74-9-B (1-47W81 0-1)

11. Function of Affected Component(s) - Opens to provide decay heat removal for cooling to the cold shutdown condition.

Ill. Basis for Alternative Frequency - Exercising the valve during operation would result in over pressurizing the RHR piping, causing a loss of both trains of a safety system.

IV. Proposed Alternative Frequency - Full stroke exercise to the open position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-18 Affected Component(s) CKV-63-502-S, 1-CKV-63-632-A, 1-CKV-63-633-B, 1-CKV-63-634-A, 1-CKV-63-635-B, 1-CKV-63-640-S, 1-CKV-63-641 -S, 1-CKV-63-643-S, 1-CKV-63-644-S (1-47W81 1-1) 1-CKV-74-514-A, 1-CKV-74-515-B, 1-CKV-74-544-A, 1-CKV-74-545-B (1-47W81 0-1)

11. Function of Affected Component(s) - Opens to admit flow from the RHR pumps to the reactor during LOCA or post LOCA recovery. Valves 1-CKV-74-544-A and 1-CKV-74-545-B also close to prevent dead heading the weaker pump when at minimum flow (i.e., when RCS pressure is at or near the pressure available during minimum flow operation) during all modes except shutdown cooling. Valves 1-CKV-74-514-A and 1-CKV-74-515-B also close to prevent recirculation of RHR flow through a tripped pump during the shutdown cooling mode when both trains are in service.

Ill. Basis for Alternative Frequency - The RHR pumps do not develop sufficient head to open the valves during power operation. With the RHR pump suction being supplied from the normal loop 4 suction path during shutdown and discharging to a closed vessel, the pumps cannot develop sufficient flow to satisfy the full flow requirements for the check valves. In order to achieve full flow, the vessel must be open and the pump suction taken from the RWST. Valves 1-CKV-74-514-A and 1-CKV-74-515-B cannot be exposed to the pressure of a running RHR pump during plant operation without opening 1-HCV-74-36 and 1-HCV-74-37. Opening these valves or back-seating 1-CKV-63-502S adversely affects both trains of a safety system. Valves 1-CKV-74-544-A and 1-CKV-74-545-B can only be back seated during operation. While in shut down conditions, the valve alignments necessary to back-seat these valves adversely affects both trains of a safety system.

IV. Proposed Alternative Frequency - Full stroke exercise to the open position during refueling outages. Full stroke exercise 1-CKV-74-544-A and 1-CKV-74-545-B to the closed position quarterly during operation. Full stroke exercise 1-CKV-63-502-S to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns. Full stroke exercise 1-CKV-74-514-A and 1-CKV-74-515-B to the closed position during refueling outages.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 53 of 73 APPENDIX A Page 9 of 13 AF-19 I. Affected Component(s) FCV-63-1 -A, 1-FCV-63-5-B (1-47W81 1-1)

I1. Function of Affected Component(s) - Closes when the associated pump suction (either RHR or SIS) is transferred from the RWST to the containment sump following a LOCA.

II1. Basis for Alternative Frequency - Exercising valve during operation results in losing suction from RWST to both trains of a safety system. If valve fails to reopen both trains of the affected safety system would be made inoperable.

IV. Proposed Alternative Frequency - Full stroke exercise to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-20 I. Affected Component(s) FCV-63-3-A (1-47W811-1)

I1. Function of Affected Component(s) - Valve is closed to prevent flow to the RWST during the recirculation phase of a LOCA.

Ill. Basis for Alternative Frequency - Exercising valve during operation results in isolating the recirculation line to both trains of safety injection pumps. Failure of the valve to reopen would make both trains of a safety system inoperable.

IV. Proposed Alternative Frequency - Full stroke exercise to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-21 I. Affected Component(s) FCV-63-8-A, 1-FCV-63-1 1-B (1-47W81 1-1)

II. Function of Affected Component(s) - Opened to establish suction flow path from the RHR pumps to safety injection and/or centrifugal charging pumps during the recirculation phase of a LOCA.

II1. Basis for Alternative Frequency - Both valves are electrically interlocked with the safety injection pump recirculation isolation valves 1-FCV-63-3-A, 1-FCV-63-4-B and 1-FCV-63-175-B in such a manner that both trains of the Safety Injection System will have their minimum flow recirculation path isolated to cycle either valve. Isolation of these recirculation paths adversely affects both trains of a safety system and could cause failure of both trains. Additionally, the valves are interlocked with the containment sump suction valves in such a manner that they must be fully open to allow these valves to operate. Opening the containment sump valves during operation requires either draining an extensive portion of the RHR system or allowing it to drain to the containment sump. Draining and refilling these lines requires a considerable amount of time and could extend forced outage duration. Allowing the affected piping to drain to the sump requires extensive cleanup time.

Therefore testing during forced outages is not practical.[See also AF-25]

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 54 of 73 APPENDIX A Page 10 of 13 IV. Proposed Alternative Frequency - Full stroke exercise to the open position during refueling outages.

AF-22 I. Affected Component(s) FCV-63-22-B (1-47W81 1-1)

I1. Function of Affected Component(s) - Closed when safety injection pumps are placed on hot leg recirculation after a LOCA.

I1l. Basis for Alternative Frequency - Exercising valve during operation isolates both trains of safety injection from their normal flow path to the cold legs. Failure of the valve to reopen results in total loss of system function.

IV. Proposed Alternative Frequency - Full stroke exercise to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-23 I. Affected Component(s) FCV-63-25-B, 1-FCV-63-26-A (1-47W81 1-1)

I1. Function of Affected Component(s) - Valves are part of the Emergency Core Cooling System (ECCS) and open to admit flow from the centrifugal charging pumps to the reactor vessel during accidents involving loss of primary system pressure.

Ill. Basis for Alternative Frequency - Charging header pressure during normal operation exceeds the pressure downstream of the check valves associated with these FCVs. If the FCVs are opened for testing, the pressure in the charging header will initiate flow through the high head safety injection system piping. This will:

1. Cause pressurizer level transients, due to the additional water being added to the RCS, which will cause unstable operation and may result in unit trip and subsequent initiation of the entire safety injection system.

2. Cause a thermal stress transient in the associated piping which will have to be counted as one of the limited number of safety injection system actuations permitted during the design life of the plant.

IV. Proposed Alternative Frequency - Full stroke exercise to the open position in conjunction with cold shutdowns, but not more often than once per quarter in the event of frequent cold shutdowns.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 55 of 73 APPENDIX A Page 11 of 13 AF-24 Affected Component(s) FCV-63-67-B, 1-FCV-63-80-A, 1-FCV-63-98-B, 1-FCV-63-118-A (1-47W811-1)

11. Function of Affected Component(s) - Valves are normally open and allow the cold leg accumulators to function as a passive component. However, during accidents which do not involve loss of primary system integrity, the valves must close to isolate the cold leg accumulators from the RCS so that the RCS can be depressurized to the RHR cut-in pressure for continued cool down to the cold shutdown condition without discharging the cold leg accumulators.

Ill. Basis for Alternative Frequency - WBN is not analyzed for operation with a Cold Leg Accumulator isolated. Thus, closing any one of these valves during power operation results in placing the plant in an unanalyzed condition. This test can only be performed in a very narrow window, as RCS pressure nears 1000 psig. This condition occurs during the startup and shutdown sequence and cannot be duplicated in MODE 5 [Cold Shutdown] without discharging the associated Cold Leg Accumulator to the Reactor Coolant System. At the time the valves would be available for testing during non-RFO related, forced shutdowns, the plant is either in the process of shutting down to allow repairs to be made or of returning to power operation.

IV. Proposed Alternative Frequency - Full stroke exercise and stroke time to the closed position each refueling outage.

AF-25 Affected Component(s) FCV-63-72-A, 1-FCV-63-73-B (1-47W81 1-1) 1-FCV-72-44-A, 1-FCV-72-45-B (1-47W812-1)

II. Function of Affected Component(s) - Opens to allow safety related systems to take suction from containment sump.

I1l. Basis for Alternative Frequency - Opening the containment sump isolation valves during operation requires either draining an extensive portion of the RHR and CS systems or allowing it to drain to the containment sump. Draining and refilling these lines requires a considerable amount of time and could extend forced outage duration. Allowing the affected piping to drain to the sump requires extensive cleanup time. Therefore testing during forced outages is not practical. [See also AF-22]

IV. Proposed Alternative Frequency - Full stroke exercise to the open position each refueling outage.

AF-26

1. Affected Component(s) FCV-63-93-A, 1-FCV-63-94-B, 1-FCV-63-172-B (1-47W811-1) 1-FCV-74-33-A, 1-FCV-74-35-B (1-47W81 0-1)

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 56 of 73 APPENDIX A Page 12 of 13 II. Function of Affected Component(s) - All except 1-FCV-63-172-B are open during ECCS injection mode to allow either train of RHR to provide injection flow to all four RHR injection lines. The valves are closed to establish the flow boundary during the hot leg recirculation phase of a LOCA.

1-FCV-63-172B is normally closed and remains closed during the injection phase of a LOCA but opens to initiate hot leg recirculation.

11. Basis for Alternative Frequency - Closing any one of the four normally open valves causes operation in an unanalyzed condition by isolating two of the four cold legs from the RHR pumps.

Opening 1-FCV-63-172-B would require closure of 1-FCV-74-33-A and 1-FCV-63-35-B to avoid having RHR aligned to hot leg injection and cold leg injection simultaneously. Since these valves cannot be closed without affecting both trains of RHR, 1-FCV-63-172-B cannot be opened.

IV. Proposed Alternative Frequency - Full stroke exercise 1-FCV-63-93-A, 1-FCV-63-94-B, 1-FCV-74-33-A, and 1-FCV-74-35-B to the closed position and 1-FCV-63-172-B to the open position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-27 I. Affected Component(s) CKV-81-502 (1-47W819-1)

II. Function of Affected Component(s) - Closes to provide Containment Isolation I1l. Basis for Alternative Frequency - Cycling this valve results in loss of primary water to the RCP stand pipes and PRT. Also this valve is physically located in the number 4 accumulator room in the reactor building. Access to this area will be limited during operation due to radiation exposures.

IV. Proposed Alternative Frequency - Full stroke exercise to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-28 I. Affected Component(s) FSV-68-394-A, 1-FSV-68-395-B, 1-FSV-68-396-B, 1-FSV-68-397-A, (1-47W813-1)

I1. Function of Affected Component(s) - These FSVs open to provide a reactor head vent and close to terminate a reactor head vent.

Ill. Basis for Alternative Frequency - These valves are solenoid to open and spring to close. With any single valve open for stroke time testing, the remaining valves are required to seat against full RCS pressure upstream with the downstream pressure at Pressurizer Relief Tank pressure. If the valves that remain closed are not well seated, stroking of a single valve to the open position while at power could result in leakage from the RCS in excess of the TS limits or depressurization of the RCS. Failure of any single valve to reclose would leave a single valve to prevent leakage from the RCS.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 57 of 73 APPENDIX A Page 13 of 13 IV. Proposed Alternative Frequency - Full stroke exercise to the open position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-29 Affected Component(s) FCV-67-83-A, 1-FCV-67-87-A, 1-FCV-67-88-B, 1-FCV-67-89-B, 1-FCV-67-91 -A, 1-FCV-67-95-A, 1-FCV-67-96-B, 1-FCV-67-97-B, 1-FCV-67-99-A, 1-FCV-67-103-B, 1-FCV-67-104-A, 1-FCV-67-105-A, 1-FCV-67-107-A, 1-FCV-67-1 l-B, 1-FCV-67-112-A, 1-FCV-67-113-A (1-47W845-3) 1-CKV-70-679, 1-FCV-70-87-B, 1-FCV-70-89-B, 1-FCV-70-90-A, 1-FCV-70-92-A, 1-FCV-70-1 00-A, 1-FCV-70-133-A, 1-FCV-70-134-B, 1-FCV-70-140-B (1-47W859-2)

11. Function of Affected Component(s) FCV-70-133-A closes to provide a second train of isolation to interrupt a potential source of dilution water to the containment sump. The remaining valves are containment isolation valves.

I1. Basis for Alternative Frequency - Exercising these valves during operation causes a loss of flow to the associated equipment (Lower Compartment Coolers, Control Rod Drive Mechanism Coolers, Reactor Coolant Pump [RCP] Motor Coolers, RCP oil coolers, and/or RCP Thermal Barrier Coolers).

In many cases [i.e., RCP Pump Oil Coolers or RCP Thermal Barrier Coolers] loss of flow to the associated equipment for even a brief period of time could easily result in failure of the associated equipment, unit trip, and potentially even a safety injection. Failure of the remaining valves to reopen would cause a sustained loss of flow to the associated equipment and would result in the same consequences.

IV. Proposed Alternative Frequency - Full stroke exercise the valves to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

AF-30

1. Affected Component(s) CKV-68-849, 1-CKV-63-868 (1-47W830-6)

If. Function of Affected Component(s) - Closes to provide Containment Isolation Ill. Basis for Alternative Frequency - Cycling these valves during power operation interrupts the nitrogen supply inside containment to a number of components and systems. Additionally personnel radiation exposure and valve inaccessibility prohibit quarterly exercising of these valves.

IV. Proposed Alternative Frequency - Full stroke exercise to the closed position in conjunction with cold shutdowns, not to exceed once per quarter in the event of frequent cold shutdowns.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 58 of 73 APPENDIX B Page 1 of 10 REQUESTS FOR RELIEF Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1 Second 10-Year Interval Request for Relief Number PV-01 Systems/Components For Which Relief Is Requested Affected components are identified by their Unique Identification Number (UNID) in Table P-I.

II. Code Requirements ASME OM Code, ISTB-3300(a), "Initial reference values shall be determined from the results of testing meeting the requirements of ISTB-31 00, Preservice Testing, or from the results of the first inservice test." The ASME OM Code of Record for the Second Inservice Interval is 2001 Edition with Addenda through 2003.

Ill. Code Requirement From Which Relief Is Requested Relief is being requested from establishing reference values solely on the basis of the data collected during preservice or inservice testing for those vibration points that have unusually low levels of vibration. This request applies only to reference values associated with vibration testing.

IV. Basis for Relief The pumps listed in Table P-1 have at least one vibration reference value (VR) that is currently less than 0.05 inches per second (ips). Small values for VR produce small acceptable ranges for pump operation. The acceptable ranges are defined in Tables ISTB-51 00-1 and ISTB-5200-1, as less than or equal to 2.5VR. Based on a small acceptable range, a smooth running pump could be subject to unnecessary corrective action caused by numerically small changes in vibration levels.

For very small reference values, hydraulic noise and instrument error can be a significant portion of the reading and affect the repeatability of subsequent measurements. Also, experience gathered from the preventive maintenance program has shown that changes in vibration levels in the range of 0.05 ips do not normally indicate significant degradation in pump performance.

To avoid unnecessary corrective action, a minimum value for VR of 0.05 ips has been established for velocity measurements. This minimum value will be applied to individual vibration locations for the pumps listed in Table P-1 where the measured reference value is less than 0.05 ips.

When new reference values are established per ISTB-3310, ISTB-3320 or ISTB-6200(c), the measured parameters will be evaluated for each location to determine if the provisions of this relief request still apply. If the measured VR is greater than 0.05 ips, the requirements of ISTB-3300 will be applied even if the pump is listed in Table P-1. Conversely, if the measured VR is less than 0.05 ips, a minimum value of 0.05 ips will be used for VR even if the pump is not currently listed in Table P-1.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 59 of 73 APPENDIX B Page 2 of 10 In addition to the requirements of ISTB, the pumps in the ASME Inservice Testing Program are included in the Predictive Maintenance Program. The Predictive Maintenance Program currently employs the following predictive monitoring techniques on an as applicable and as needed basis:

1. vibration monitoring and analysis beyond that required by ISTB,

2. oil sampling and analysis, and

3. thermographic analysis.

Bearing temperature trending is available for some components through the plant process computer system.

Ifthe measured parameters are discovered to be outside the normal operating range or to be trending toward an unacceptable degraded state, appropriate actions are taken that may include:

1. increased monitoring to establish rate of change,

2. review of component specific information to identify cause, and

3. removal of the pump from service to perform maintenance.

It should be noted that all of the pumps in the IST Program will remain in the Predictive Maintenance Program even if certain pumps have very low vibration readings and are considered to be smooth running pumps. This alternative to the requirements of ISTB-3300 provides an acceptable level of quality and safety.

V. Alternative Examinations Pumps with a measured reference value below 0.05 ips for a particular vibration measurement location shall have subsequent test results for that location compared to an acceptable range based on 0.05 ips. In addition to the Code requirements, all pumps in the IST Program are included in and will remain in the Predictive Maintenance Program regardless of their smooth running status.

VI. Justification for the Granting of Relief Using the provisions of this relief request as an alternative to the specific requirements of ISTB-3300 identified above will provide adequate indication of pump performance and continue to provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i) we request relief from the specific ISTB Code requirements identified in this relief request.

This relief request was approved for the First Ten Year Interval using 0.10 as a minimum instead of 0.05. Change to 0.05 is more conservative and consistent with the industry.

VII. Implementation Schedule Relief is requested for the Second Inservice Interval, which is described in Section 1.0 of the Program Description.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 60 of 73 APPENDIX B Page 3 of 10 Table P-1 Pump UNID Vibration Code OM Number Points System Class Group Description O-PMP-67-28-A A-A, B-H, B-V 0-PMP-67-32-A A-A, B-H, B-V O-PMP-67-36-A A-A, B-V 0-PMP-67-40-A All ERCW 3 A Essential Raw Cooling 0-PMP-67-47-B All but A-H Water Pumps 0-PMP-67-51 -B All but A-H 0-PMP-67-55-B All but B-V 0-PMP-67-59-B A-A, B-H 1-PMP-67-431 -A All 1-PMP-67-440-B A-A, B-H, B-V ERCW 3 A ERCW Screen Wash Pumps 2-PMP-67-437-A All 2-PMP-67-447-B All 1-PMP-70-46-A All 1-PMP-70-38-A All Component 3 A Component Cooling Pumps O-PMP-70-51 -S All Cooling 0-PMP-31-80-A All but B-V Chilled 3 A Main Control Room Chilled 0-PMP-31-96A-B All Water Water Pumps 0-PMP-31-128/1-A A-V, B-V, B-A Chilled 3 A Electric Board Room Chilled 0-PMP-31-129/1 -B All Water Water Pumps 0-PMP-31-36/1-A B-V. B-A Chilled 3 A Shutdown Board Room 0-PMP-31-49/1-B A-V, B-H, B-A Water Chilled Water Pumps 1-PMP-62-230-A All but B-V Chemical and 3 A Boric Acid Transfer Pumps 1-PMP-62-232-B A-H, A-A, B-H Volume Control I 1-PMP-63-1 0-A All Safety 2 A Safety Injection Pump 1-PMP-63-15-B A-H Injection _1 I

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 61 of 73 APPENDIX B Page 4 of 10 Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1 Second 10-Year Interval Request for Relief Number PV-02

1. Systems/Components For Which Relief Is Requested ERCW Screen Wash Pumps (1-PMP-67-431-A, 1-PMP-67-440-B, 2-PMP-67-437-A, 2-PMP-67-447-B) (1-47W845-1)

II. Code Requirement ASME OM Code, ISTB-5121(b), 'The resistance of the system shall be varied until the flow rate equals the reference point. The differential pressure shall then be determined and compared to its reference value. Alternatively, the flow rate shall be varied until the differential pressure equals the reference point and the flow rate determined and compared to the reference flow rate value." The ASME OM Code of Record for the Second Inservice Interval is 2001 Edition with Addenda through 2003.

Ill. Code Requirement From Which Relief Is Requested Relief is being requested from measuring the pump flow rate during Inservice Testing of the Screen Wash Pumps.

IV. Basis for Relief No in-line instrumentation exists to measure flow and the physical configuration of the pump and piping does not allow the use of portable flow measuring equipment such as ultrasonics. Piping from the discharge of the screen wash pumps is open-ended to the spray nozzles at the traveling screen and is relatively short with multiple elbows, reducers, and valves in different planes. The physical configuration of this piping system is such that no portion of the piping meets the requirements for adequate installation of a permanent flow measuring device. Therefore, measured flow readings from an installed device may not be repeatable nor representative of actual pump flow. Significant system modifications, such as piping rerouting and support redesign, would be required to obtain a configuration that would provide reliable flow readings.

Flow is not the critical parameter for these pumps. The nature of their operation is to ensure that sufficient pressure is maintained at the spray nozzles during flushing operations of the traveling water screens to ensure that sufficient force is exerted on the debris accumulated on the screen to remove it. This can be verified by verifying the effectiveness of the flushing operation.

V. Alternative Examinations Verify that the flow delivered through the spray nozzles in the traveling water screens provides coverage of the screen spray area and adequately flushes away debris present on the screen.

Pressure and vibration data for the pumps will be collected and analyzed in accordance with ISTB.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 62 of 73 APPENDIX B Page 5 of 10 The pumps will be tested in this manner for both the quarterly Group A test and the biennial Comprehensive test.

VI. Justification for the Granting of Relief Based upon the above discussion, the alternative test provides an acceptable level of quality and safety. Authorization to implement the proposed alternative is requested in accordance with 10CFR50.55a(3)(i).

This relief request was approved for the First Ten Year Interval.

VII. Implementation Schedule Relief is requested for the Second Inservice Interval, which is described in Section 1.0 of the Program Description.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 63 of 73 APPENDIX B Page 6 of 10 Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1 Second 10-Year Interval Request for Relief Number PV-03 I. Systems/Components For Which Relief Is Requested 1-FSV-68-396-B, 1-FSV-68-397-A (1-47W813-1)

I1. Code Requirement ASME OM Code, ISTC-1 51 (a), "Active valves shall have their stroke times measure when exercised in accordance with ISTC-3500."

ASME OM Code, ISTC-5151(b), 'The limiting value of full stroke time of each valve shall be specified by the Owner."

ASME OM Code, ISTC-5151 (c), "Stroke time shall be measured to at least the nearest second."

The ASME OM Code of Record for the Second Inservice Interval is 2001 Edition with Addenda through 2003.

III. Code Requirement From Which Relief Is Requested Relief is being requested from measuring and assessing the stroke time of the Reactor Coolant System Head Vent throttle valves.

IV. Basis for Relief The Reactor Coolant System Head Vent throttle valves are throttled open manually by Main Control Room operator action to (1) provide a reactor vessel head vent path; (2) vent non-condensables from the head during an accident to promote natural circulation; and (3) prevent gases from impeding reactor coolant circulation flow through the core. These valves are totally enclosed [seal welded bonnet], one-inch Target Rock solenoid valves, with thumb wheel actuated controllers that permit remote positioning of the valves. Valve opening and closing speed, and consequently valve opening and closing stroke time, is controlled by the rate at which the thumbwheel controller is moved, not upon valve condition. Design requirements impose a minimum stroke time limitation on these valves of not faster than 5 seconds. Restricting the stroke time to not less than 5 seconds effectively prohibits stroke timing the valve because the valve is capable of stroking considerably faster than the 5 second limit. Even if the 5 second limit did not exist, stroke timing of the valve using its thumb-wheel actuated controller would result in timing the ability of the operator to turn the thumb-wheel and not the ability of the valve to move.

An enhanced maintenance program of disassembly and inspection of valve internal parts was evaluated. This method was not considered appropriate for the following reasons:

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 64 of 73 APPENDIX B Page 7 of 10

[1] Frequent disassembly can lead to distortion of the valve parts caused by the repetitive welding process to reinstall the seal weld. This distortion could cause unacceptable operational seat leakage, binding of internal parts, and other operational problems.

[2] The physical appearance of the internal parts does not always provide clear and evident verification of acceptable valve operation.

V. Alternative Examinations TVA proposes to utilize an enhanced maintenance program based on the following attributes:

[1] Periodic replacement of critical valve parts [i.e., the linear voltage differential transformer (LVDT) that provides valve position indication feedback, the coil that operates the valve, and the valve's electrical terminal board] is in accordance with TVA's environmental qualification binder for the valve. The current schedule for valve part replacement is every 132 months for the LVDT, every 294 months for the coil, and every 432 months for the valve terminal board.

[2] Calibration of the valve's position control system is performed each refueling outage. This calibration involves utilizing the valve controller to position the valve at various positions and utilizing the LVDT to determine the valve stem position. These are compared to ensure valve operation is as expected.

In addition to the enhanced maintenance program, tests will be conducted as follows to provide positive verification of the valve's ability to fulfill its specific function:

[1] Full stroke exercise of each valve is performed during shutdowns. This test consists of cycling the valve controller through one complete cycle and verifying [using the valve position indicator operated by the LVDT attached to the valve stem] that the valve cycles through one full cycle in response to the valve controller.

[2] During refueling outages, in addition to cycling the controller through one complete cycle and using the valve position indicator to verify valve travel, supplement the verification of valve travel by (a) ensuring no detectable flow is present through the valves with the valves closed, (b) ensuring that with each valve open flow is present, and (c) ensuring that when each valve is returned to the closed position no detectable flow is present. The presence or absence of flow is verified by monitoring a change in a process perimeter either the valve tail pipe temperature for an increase/decrease or the pressurizer relief tank [to which the valves discharge] for a temperature increase/decrease or level increase/no change. This additional verification which is consistent with ISTC-3520, Valve Obturator Movement, ensures the valve disk is still attached to the stem and is capable of controlling flow.

VI. Justification for the Granting of Relief Based upon the above discussion, the alternative test provides an acceptable level of quality and safety. Authorization to implement the proposed alternative is requested in accordance with 10CFR50.55a(3)(i).

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 65 of 73 APPENDIX B Page 8 of 10 This relief request was approved for the First Ten Year Interval.

VII. Implementation Schedule Relief is requested for the Second Inservice Interval, which is described in Section 1.0 of the Program Description.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 66 of 73 APPENDIX B Page 9 of 10 Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1 Second 10-Year Interval Request for Relief Number PV-04 I. Systems/Components For Which Relief Is Requested 0-FSV-67-1221 -A (1-47W845-4) 0-FSV-67-1223-B (1-47W845-7) i1. Code Requirement ASME OM Code, ISTC-1 51 (a), "Active valves shall have their stroke times measure when exercised in accordance with ISTC-3500."

ASME OM Code, ISTC-51 51 (b), 'The limiting value of full stroke time of each valve shall be specified by the Owner."

ASME OM Code, ISTC-5151 (c), "Stroke time shall be measured to at least the nearest second."

The ASME OM Code of Record for the Second Inservice Interval is 2001 Edition with Addenda through 2003.

Ill. Code Requirement From Which Relief Is Requested Relief is being requested from measuring and assessing the stroke time of the ERCW isolation valves to the Auxiliary Air Compressors.

IV. Basis for Relief These solenoid valves are mounted on the auxiliary air compressor skid. They are totally enclosed, solenoid actuated valves manufactured by Target Rock and have no remote position indication capability. The inability to see any moving parts of the valve combined with the lack of remote position indication capability prevents visual confirmation of valve position, thus preventing direct measurement of the stroke time of the valve.

Additionally, the air compressors have a thermostatic valve, installed in series with these solenoid valves, that modulates in response to system temperature. The thermostatic valve does not start opening until air compressor temperatures are elevated. Until air compressor temperatures have risen sufficiently to open the thermostat, no cooling water flow exists to the compressor, even though the solenoid valves are open. Although a flow element is provided in the cooling water line, the presence of the thermostatic valve prevents use of the onset of flow as an indirect indication of solenoid valve stroke time.

As discussed in NUREG-1 482 Rev 1," Guidelines for Inservice Testing at Nuclear Power Plants,"

Section 3.4, "Skid-Mounted Components and Component Subassemblies," when an individual component cannot be tested to the requirements of the ISTC, testing of the larger component [in this case, the auxiliary air compressor] ensures that the subcomponent is functioning properly.

Demonstration of the ability of the auxiliary air compressors to operate without overheating will

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 67 of 73 APPENDIX B Page 10 of 10 provide an adequate means for assuring operational readiness of cooling water supply valves 0-FSV-67-1221 -A and 0-FSV-67-1223-B.

V. Alternative Examinations Exercise the valves to the open position quarterly by operating the auxiliary air compressor and observing the discharge air and jacket water temperatures during compressor operation to ensure the temperatures are maintained at acceptable levels. This verifies that the cooling water supply solenoid valves operate to supply ERCW cooling water to the auxiliary air compressors.

VI. Justification for the Granting of Relief Based upon the above discussion, the alternative test provides an acceptable level of quality and safety. Authorization to implement the proposed alternative is requested in accordance with 10CFR50.55a(3)(i).

This relief request was approved for the first ten year interval.

VII. Implementation Schedule Relief is requested for the Second Inservice Interval, which is described in Section 1.0 of the Program Description.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 68 of 73 Page 1 of 2 Relief Valve Groups Class 1 Test Group 1 - Pressurizer Safety Valves 1-RFV-68-563 1-RFV-68-564 1-RFV-68-565 Class 2 Valves Tested to Class 1 Requirements Main Steam Safe Valves (MSSVs) 1-SFV-1-512 1-SFV-1 -517 1-SFV-1-522 1-SFV-1 -527 1-SFV-1-513 1-SFV-1-518 1-SFV-1-523 1-SFV-1-528 1-SFV-1-514 1-SFV-1-519 1-S FV-1 -524 1-SFV-1 -529 1-SFV-1-515 1-SFV-1-520 1-SFV-1-525 1-SFV-1 -530 1-SFV-1-516 1-SFV-1-521 1-SFV-1-526 1-SFV-1-531 Class 2 and 3 Test Group 2 1-RFV-70-551 A 1-RFV-70-551 B 1-RFV-70-835 1-RFV-77-2875 Test Group 3 1-RFV-63-602 1-RFV-63-603 1-RFV-63-604 1-RFV-63-605 Test Group 4 1-RFV-62-636 1-RFV-62-675 1-RFV-62-626-A 1-RFV-62-649 1-RFV-62-955 1-RFV-63-627-B 1-RFV-62-662 2-RFV-62-955 1-RFV-74-505 Test Group 5 0-RFV-67-671 0-RFV-67-672 1-RFV-70-556A Test Group 6 1-RFV-62-505-S 1-RFV-63-28 1-RFV-63-535-S 1-RFV-63-637-S 1-RFV-62-1221 1-RFV-63-511 1-RFV-63-536-B 1-RFV-63-835 1-RFV-62-1222 1-RFV-63-534-A 1-RFV-63-577 1-RFV-72-508-A 1-RFV-72-509-B Test Group 7 1-RFV-70-538 1-RFV-70-703 Test Group 8 1-RFV-70-556B 1-RFV-70-565A 1-RFV-70-565B Test Group 9 1-RFV-62-1079 2-RFV-62-1079 1-RFV-70-539

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 69 of 73 Appendix C Page 2 of 2 Test Group 10 O-RFV-31-2623 I 0-RFV-31-2665 Test Group 11 0-RFV-31-2210 10-RFV-31-2252, 0-RFV-31-2326 I 0-RFV-31-2383 Test Group 12 1-RFV-67-539A I 1-RFV-67-539B I 1-RFV-70-578 1-RFV-72-40 1-RFV-72-41

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 70 of 73 Appendix D Page 1 of 1 Pressure Isolation Valve Listing 1-CKV-63-543, HOT LEG 1 SAFETY INJECTION SECONDARY CHECK.

1-CKV-63-545, HOT LEG 3 SAFETY INJECTION SECONDARY CHECK.

1-CKV-63-547, HOT LEG 2 SAFETY INJECTION SECONDARY CHECK.

1-CKV-63-549, HOT LEG 4 SAFETY INJECTION SECONDARY CHECK.

1-CKV-63-551, COLD LEG 1 SAFETY INJECTION SECONDARY CHECK.

1-CKV-63-553, COLD LEG 2 SAFETY INJECTION SECONDARY CHECK.

1-CKV-63-555, COLD LEG 3 SAFETY INJECTION SECONDARY CHECK.

1-CKV-63-557, COLD LEG 4 SAFETY INJECTION SECONDARY CHECK.

1-CKV-63-581, BORON INJECTION LINE CHECK.

1-CKV-63-561, COLD LEG 2 INJECTION HEADER CHECK 1-CKV-63-562, COLD LEG 3 INJECTION HEADER CHECK 1-CKV-63-632, COLD LEG 2 INJECTION HEADER CHECK 1-CKV-63-634, COLD LEG 3 INJECTION HEADER CHECK 1-CKV-63-560, COLD LEG 1 INJECTION HEADER CHECK 1-CKV-63-563, COLD LEG 4 INJECTION HEADER CHECK 1-CKV-63-633, COLD LEG 1 INJECTION HEADER CHECK 1-CKV-63-635, COLD LEG 4 INJECTION HEADER CHECK 1-CKV-63-640, HOT LEG 4 RHR INJECTION SECONDARY CHECK.

1-CKV-63-643, HOT LEG 2 RHR INJECTION SECONDARY CHECK.

1-CKV-63-558, HOT LEG 4 SAFETY INJECTION PRIMARY CHECK.

1-CKV-63-559, HOT LEG 2 SAFETY INJECTION PRIMARY CHECK.

1-CKV-63-586, COLD LEG 1 BORON INJECTION PRIMARY CHECK.

1-CKV-63-587, COLD LEG 2 BORON INJECTION PRIMARY CHECK.

1-CKV-63-588, COLD LEG 3 BORON INJECTION PRIMARY CHECK.

1-CKV-63-589, COLD LEG 4 BORON INJECTION PRIMARY CHECK.

1-CKV-63-640, HOT LEG 1 RHR INJECTION SECONDARY CHECK.

1-CKV-63-644, HOT LEG 3 SIS/RHR INJECTION PRIMARY CHECK.

1-CKV-63-622, ACCUMULATOR 1 OUTLET CHECK.

1-CKV-63-623, ACCUMULATOR 2 OUTLET CHECK.

1-CKV-63-624, ACCUMULATOR 3 OUTLET CHECK.

1-CKV-63-625, ACCUMULATOR 4 OUTLET CHECK 1-FCV-74-1, LOOP 4 HOT LEG TO RHR SUCTION 1-FCV-74-2, LOOP 4 HOT LEG TO RHR SUCTION 1-FCV-74-8, 1-FCV-74-2 BYPASS RHR SUCTION 1-FCV-74-9, 1-FCV-74-1 BYPASS RHR SUCTION

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 71 of 73 Appendix E Page 1 of 3 Editorial Errors in the 2003 Addenda 2003 Paragraph Reference 2005 Paragraph Reference Comments ISTB-9200 ISTA-3120 ISTB-9200 ISTA-3110 ISTB-9200 contains requirements for records keeping. The reference in the 2003 Code is to a paragraph dealing with establishing the Inservice Interval. The correct reference is to ISTA-31 10 which does address records keeping requirements.

ISTB-9200 ISTA-3170 ISTB-9200 ISTA-3160 The referenced paragraph in the 2003 Code does not exist. The correct reference is to ISTA-3160 Table ISTC-3500 Table ISTC-3560 Note 1 addresses requirements for fail safe actuator testing, which are contained in ISTC-3500-1, ISTC-3500-1, ISTC-3560 as referenced by the 2005 Code rather than ISTC-3500 as referenced by the Note 1 Note 1 2003 Code..

ISTC-3510 ISTC-3560 ISTC-3510 ISTC-3570 ISTC-3510 addresses valve exercising frequency requirements and contains a list of exceptions. ISTC-3560, as referenced in the 2003 Code, deals with testing requirements for fail safe actuators, not exercising frequency requirements. The correct reference is to ISTC-3570, as contained in the 2005 Code.

ISTC-3620 10CFR50 ISTC-3620 10CFR50 ISTC-3620 discusses leak testing requirements. The 2003 Code refers to 10CFR50 Nonmandatory Appendix J Nonmandatory Appendix J, which is incorrect. The reference should be to 10CFR50 Appendix J Appendix J. Nonmandatory Appendix J in the 2003 Code discusses post maintenance check valve testing, not containment leak rate testing.

ISTC-3630 10CFR50 ISTC-3630 10CFRS0 ISTC-3630 discusses leak testing requirements. The 2003 Code refers to 10CFR50 Nonmandatory Appendix J Nonmandatory Appendix J, which is incorrect. The reference should be to 10CFR50 Appendix J Appendix J. Nonmandatory Appendix J in the 2003 Code discusses post maintenance check valve testing, not containment leak rate testing.

ISTC-3630(b)(4) "valve" ISTC-3630(b)(4) 'value" The 2003 Code contains a misspelled word that was corrected in the 2005 Code.

ISTC-5114(c) ISTC-5115(b) ISTC-5114(c) ISTC-5114(b) ISTC-5114(c) establishes an exemption for fast acting power operated relief valves. The exemption in the 2003 Code is not consistent with the exemption for other type valves.

As written in the 2003 Code, fast acting power operated relief valves are exempted from the retest requirements of ISTC-5115(b) but not the acceptance criteria requirements of ISTC-5114(b). The correct reference, which is consistent with other type valves, is to paragraph ISTC-5114(b), as referenced in the 2005 Code, which addresses acceptance I criteria rather than retest requirements.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 72 of 73 Appendix E Page 2 of 3 2003 Paragraph Reference 2005 Paragraph Reference Comments ISTC-5115(a) ISTC-5114(b) ISTC-5115(a) ISTC-5113(b) ISTC-5115(a) addresses actions to be taken when a valve stroke time exceeds the limiting value of full stroke time [i.e., not capable of fulfilling its safety function].

ISTC-5114(b), as referenced in the 2003 Code, does not address limiting stroke times. It addresses potentially degraded stroke times. ISTC-5115(b) addresses the actions to be taken for potentially degraded stroke times. The correct reference for ISTC-5115(a) is to ISTC-5113(b), as shown in the 2005 Code, which does address limiting values of full stroke time.

ISTC-5115(b) ISTC-5114(b) ISTC-5115(b) ISTC-5114 ISTC-5115(b) addresses the actions required when a potentially degraded stroke time is encountered. As referenced in the 2003 Code, it would only apply to valves with a reference stroke time less than or equal to 10 seconds. The correct reference, as shown in the 2005 Code, is to paragraph ISTC-5114, not subparagraph ISTC-5114(b). This correctly applies the provisions of ISTC-5115(b) to all valves.

ISTC-5222 ISTC-5222 ISTC-3530 The 2003 Code omitted reference to valve obturator movement requirements, which should also be implemented if a check valve is removed from a condition monitoring program. This omission was corrected in the 2005 Code by adding the appropriate paragraph reference.

ISTC-91 10(d) ISTC-91 10(d) ISTC-5113(b) The 2003 Code omitted reference to limiting values of full stroke time for power operated relief valves in ISTC-91 10(d). This was corrected in the 2005 Code by adding the appropriate paragraph reference for power operated relief valves.

ISTC-9200 ISTA-3120 ISTC-9200 ISTA-31 10 ISTC-9200 contains requirements for records keeping. The reference in the 2003 Code is to a paragraph dealing with establishing the Inservice Interval. The correct reference is to ISTA-3110 which does address records keeping requirements.

ISTC-9200(d) ISTC-5522 ISTC-9200(D) ISTC-5223 ISTC-9200(d) contains records keeping requirements for the basis for testing series valves as a unit. The 2003 Code references a paragraph that deals with the check valve condition monitoring program. The correct reference is to the paragraph that establishes the requirements for testing series valves as a unit, ISTC-5223, as contained in the 2005 Code.

The following paragraphs are from Mandatory Appendix I 1-7300 - 1-7300 1-1370, 1-1380, 1-7300 contains a reference to other paragraphs that establish the frequency requirements and 1-1390 for testing relief devices. The 2003 Code failed to tabulate all the necessary references.

This was corrected in the 2005 Code by the addition of these three references.

1-7370 1-1350 1-7370 1-1360 1-7370 in the 2003 refers to periodic replacement of nonreclosing relief devices but refers to a paragraph for Class 2 and 3 relief valves. The correct reference, as listed in the 2005 Code, is to paragraph 1-1360, which does establish the frequency for replacement of nonreclosing relief devices.

.4,.

WATTS BAR NUCLEAR PLANT WBN SECOND INSERVICE INTERVAL 1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Page 73 of 73 Appendix E Page 3 of 3 2003 Paragraph Reference 2005 Paragraph Reference Comments 1-7470 1-1350 1-7470 1-1360 1-7470 in the 2003 refers to disposition after maintenance of nonreclosing relief devices but refers to a paragraph for Class 2 and 3 relief valves. The correct reference, as listed in the 2005 Code, is to paragraph 1-1360, which does address nonreclosing relief devices.

1-8320(a) 1-1340(C) 1-8320(a) 1-1 350(c) 1-8320(a) addresses increasing sample size based on valve setpoint failures. However, the 2003 Code references a paragraph that does not include provisions for sample expansion. This was corrected in the 2005 Code to reference paragraph 1-1350(c), which does include provisions for sample expansion.

ML061870144

Text

1.0 INTRODUCTION

1.0 INTRODUCTION

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