ULNRC-05248, Submittal of Revision 23 to Pump and Valve Inservice Testing Program

Submittal of Revision 23 to Pump and Valve Inservice Testing Program

ML060370100
Person / Time
Site:	Callaway
Issue date:	01/19/2006
From:	Keith Young AmerenUE, Union Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-05248
Download: ML060370100 (187)

Text

Union Electric PO Box 620 Ca//away P/ant Fulton, MO 65251 January 19, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Ladies and Gentlemen: ULNRC-05248 10 CFR 50.55a DOCKET NUMBER 50-483 UNION ELECTRIC COMPANY WVAmeren CALLAWAY PLANT UF SUBMITTAL OF REVISION 23 OF CALLAWAY PUMP AND VALVE INSERVICE TESTING PROGRAM Union Electric Company (AmerenUE) hereby submits Revision 23 of the Callaway Pump and Valve Inservice Testing (IST) Program. This revision, included as an attachment to this letter, is provided for your information in accordance with regularly provided updates of the Callaway IST Program.

Revision 23 of the IST Program was primarily developed for implementation of the third 10-year inservice testing interval at Callaway, for which the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), 2001 Edition (through 2003 Addenda) is applicable.

Included in the attached revision of the IST program are the 10 CFR 50.55a requests (Relief Requests) that have been approved to date by the NRC for the third 10 -year IST interval. Callaway's 10-year IST interval became effective on December 19, 2005.

Please contact us for any questions you may have regarding the attached.

Sincerely, Keith D. Young Manager-Regulatory Affairs TBE/jdg Attachment @t5\A7 a subsidiaryofAmeren Corporation

ULNRC-05248 January 19, 2006 Page 2 cc: U.S. Nuclear Regulatory Commission (Original and 1 copy)

Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360

Attachment to ULNRC-05248 Callaway Nuclear Plant Inservice Testing Program Revision 23

E190.0074 wAmeren UE Callaway Plant Callawav Nuclear Plant Inservice Testing Program Revision 23

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APPROVALS:

Prepared by: Go~A 4 ,Ay ^ Date:

.1 IST Engineer Reviewed by: Lzwi  : Date: /f /,4/6 Qualifed Reter Approved by: Date: 121/q//9/

Supervisin ginee Performance/ISI I/

Revision Date: 12/19/05 Page I iV

Callaway Nuclear Plant IST Program IST PROGRAM REVISION INDEX Revision j Description Reference Docs Date 23 3 rd Ten Year Interval, Revision 23 12/19/05 Submittal to NRC. In Compliance with 2001 Edition through 2003 Addenda except where relief is requested.

Revision Date: 12119/05 Page 2

Callaway Nuclear Plant IST Program TABLE OF CONTENTS

1.0 INTRODUCTION

1.1 Purpose 1.2 Scope 2.0 INSERVICE TESTING PLAN FOR PUMPS 2.1 Pump Inservice Testing Plan Description 2.2 Pump Plan Table Description 2.3 Relief Requests For Pump Testing 3.0 INSERVICE TESTING OF VALVES 3.1 Valve Inservice Testing Plan Description 3.2 Valve Plan Table Description 3.3 Relief Requests or Test Deferral Justifications For Valve Testing 4.0 ATTACHMENTS 1 System and P&ID Listing 2 Pump Relief Request Index 3 Pump Relief Requests 4 Cold Shutdown Justification Index 5 Cold Shutdown Justifications 6 Refuel Outage Justification Index 7 Refuel Outage Justifications 8 Technical Position Index 9 Technical Positions 10 Inservice Testing Pump Table 11 Inservice Testing Valve Table Revision Date: 12/19/05 Page 3

Callaway Nuclear Plant IST Program

1.0 INTRODUCTION

The Third 10-Year Inservice Testing Program for Callaway Plant was developed in compliance with the rules and regulations of 10CFR 50.55a and American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants, (OM Code), 2001 Edition through 2003 Addenda. No Code Cases were utilized in developing Callaway's Inservice Testing Program. NRC Generic Letter 89-04 and NUREG 1482, Revision 1, have been used as guidance in the development of the IST Program.

Where the OM Code requirements were determined to be impractical, a relief request has been developed. These relief requests are included in Attachment 3 of this document.

This submittal of this Inservice Testing Program for pumps and valves will remain in effect through the next 10 year inservice testing interval ending December 19, 2014.

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

• Shutdown the reactor to the safe shutdown condition,

• Maintain the safe shutdown condition, or

• To mitigate the consequences of an accident The Callaway Nuclear Power Plant safe shutdown licensing basis is hot standby and the safe shutdown design basis is cold shutdown. [FSAR 5.4A]

The Inservice Testing Program test pumps and valves required for hot standby.

[CAR 199502105]

1.2 Scope The program plan was prepared to meet the requirements of the following subsections of the ASME OM Code (2001 Edition through 2003 Addenda).

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

Revision Date: 12/19/05 Page 4

Callaway Nuclear Plant IST Program

• Subsection ISTB, "Inservice Testing of Pumps in Light-Water Reactor Nuclear PowerPlants" Establishes the requirements for inservice testing of pumps in light-water reactor nuclear power plants. The pumps covered are those provided with an emergency power source, that are required in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident.

• Subsection ISTC, "Inservice Testing of Valves in Light-Water Reactor NuclearPower Plants" Establishes the requirements for inservice testing of valves in light-water reactor nuclear power plants. The valves covered include those which provide overpressure protection and are required to perform a specific function, either actively by changing valve obturator position or passively by effectively maintaining required obturator position in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident.

• Mandatory Appendix I, "Inservice Testing of PressureRelief Devices in Light- Water Reactor NuclearPower Plants" Provides the requirements for performance testing and monitoring of nuclear plant pressure relief devices. Methods, intervals, and record requirements for monitoring and testing are established, as well as guidelines for the evaluation of results. This Appendix may be applied to safety valves, safety relief valves, pilot-operated pressure relief valves, power-actuated pressure relief valves, nonreclosing pressure relief devices and vacuum relief devices, including all accessories and appurtenances.

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

Revision Date: 12/19/05 Page 5

Callaway Nuclear Plant IST Program 2.0 INSERVICE TESTING PLAN FOR PUMPS 2.1 Pump Inservice Testing Plan Description This plan establishes the test intervals and parameters to be measured to meet the requirements of ASME OM Code ISTA and ISTB with the exception of specific relief requests contained in Attachment 3.

2.2 Pump Plan Table Description The pumps included in the Callaway Nuclear Plant IST Plan are listed in Attachment 10. The information contained in these tables identifies those pumps to be tested to the requirements of ASME OM Code, the testing parameters and frequencies, and associated relief requests. The headings for the pump tables are delineated below.

• Pump Location Unique pump identification number.

• Safety Class ASME Code classification of the pump.

1 ASME Code Class l 2 ASME Code Class 2 3 ASME Code Class 3 NC Non-Code, Safety Related

• Pump Type Pump type.

Centrifugal Vertical Pump Driver Pump driver type.

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

P&ID Drawing number of the pump.

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

Revision Date: 12/19/05 Page 6

Callaway Nuclear Plant IST Program Category Pump group as defined in ISTB-2000.

Group A Pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations.

Group B Pumps in standby systems that are not operated routinely except for testing.

• Test Type Measured pump test parameters.

N Speed DP Differential Pressure Q Flow Rate V Vibration a - Denotes a Group A Pump Test b - Denotes a Group B Pump Test c - Denotes a Comprehensive Pump Test

• Test Freq. Frequency of the specified inservice test.

M3 Quarterly (92 Days)

Y2 Biennially (2 Years)

• Relief Request The applicable relief requests for the pump.

Tech. Pos. A technical position number is listed when the requirements of the code are not easily interpreted and clarifying information is needed.

The technical position is used to document how Code requirements are being implemented at the plant. Attachment 8 contains an index of all the Technical Positions included in Attachment 9.

Revision Date: 12/19/05 Page 7

Callaway Nuclear Plant IST Program 3.0 INSERVICE TESTING PLAN FOR VALVES 3.1 Valve Inservice Testing Plan Description This plan establishes the test intervals and parameters to be measured to meet the requirements of ISTA, ISTC, Appendix I, and Appendix II with the limitations imposed by 10CFR50.55a(b)(3).

Where the frequency requirements for valve testing have been determined to be impracticable, Cold Shutdown or Refuel Outage Justifications have been identified and written. These justifications are provided in Attachments 5 and 7 respectively.

3.2 Valve Plan Table Description The valves included in the Callaway Nuclear Plant IST Plan are listed in Attachment 11. The information contained in these tables identify those valves to be tested to the requirements of ISTA, ISTC, Appendix I, and Appendix II, the test parameters and frequencies, and the associated relief requests. The headings for the valve tables are delineated below.

• Valve Location Unique valve identification number.

• P&ID Drawing number of the valve.

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

• Safety Class ASME Code classification of the valve.

I ASME Code Class I 2 ASME Code Class 2 3 ASME Code Class 3 NC Non-Code, Safety Related

• Cat. The ASME OM Code category (or categories) as defined in ISTC-1300.

A Seat Leakage Limited.

B Seat Leakage Not Required.

C Self-Actuating Valves.

AC Both Categories A and C.

BC Both Categories B and C.

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

Revision Date: 12/19/05 Page 8

Callaway Nuclear Plant IST Program Valve Type The valve body style abbreviation.

13F Butterfly Valve CK Check Valve DI Diaphragm Valve GB Globe Valve GT Gate Valve PLG Plug Valve RV Relief Valve SV Solenoid Valve 3W 3-Way Valve

• Act. Type The valve actuator type abbreviation.

AO Air Operator HO Hydraulic Operator MA Manual MO Motor Operator SA Self-Actuating SO Solenoid Operator

• Active/Passive Active or Passive function determination for the valve in accordance with ISTC-2000.

A Active P Passive

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

C Closed LC Locked Closed DE De-energized (solenoid valves)

E Energized (solenoid valves) 0 Open LO Locked Open SYS System Condition Dependent Revision Date: 12/19/05 Page 9

Callaway Nuclear Plant IST Program Safety Position The safety function position(s). For valves that perform safety functions in the open and closed positions more than one safety function position may be specified.

C Closed o Open DE De-energized (solenoid valves)

E Energized (solenoid valves)

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

AT-01 Seat Leakage Rate Test (Appendix J)

AT-02 Seat Leakage Rate Test (PIV)

AT-03 Seat Leakage Rate Test (Other)

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

CO Exercise Test Open - Check Valve(l)

FC Fail Safe Test Closed FO Fail Safe Test Open LT Leakage Test (other than Appendix J or PIV)

PIT Position Indication Test RT Relief Valve Test

' Three letter designations may be used for check valve condition monitoring tests to differentiate between the various methods of exercising check valves. The letter following "CC" or "CO", should be "A" for acoustics, "D" for disassembly and examination, "F" for flow indication, "M" for magnetics, "R" for radiography, "T" for temperature, or "U" for ultrasonics.

Revision Date: 12/19/05 Page 10

Callaway Nuclear Plant IST Program Test Freq. The test frequency abbreviation.

App-J Appendix J CM Condition Monitoring(l)

Cs Cold Shutdown 43 Quarterly OP Operating Activities(2)

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

(")Frequency is as indicated in respect to the Condition Monitoring Plan for that valve group.

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

Relief Request The applicable relief request for the valve.

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

A Cold Shutdown Justification number is listed when the testing frequency coincides with Cold Shutdowns instead of being performed quarterly.

Cold Shutdown Justification numbers for valves are prefixed with "CSJ". Attachment 4 contains an index of all the Cold Shutdown Justifications included in Attachment 5.

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

Attachment 6 contains an index of all the Refueling Justifications included in Attachment 7.

Tech. Pos. A technical position number is listed when the requirements of the code are not easily interpreted and clarifying information is needed. The technical position is used to document how Code requirements are being implemented at the plant.

Attachment 8 contains an index of all the Technical Positions included in Attachment 9.

Revision Date: 12/19/05 Page I I

Callaway Nuclear Plant IST Program 4.0 ATTACHMENTS Attachment 1 - System and P&ID Listing Attachment 2 - Pump Relief Request Index Attachment 3 - Pump Relief Requests Attachment 4 - Cold Shutdown Justification Index Attachment 5 - Cold Shutdown Justifications Attachment 6 - Refuel Outage Justification Index Attachment 7 - Refuel Outage Justifications Attachment 8 - Technical Position Index Attachment 9 - Technical Positions Attachment 10 - Inservice Testing Pump Table Attachment 11 - Inservice Testing Valve Table Revision Date: 12119/05 Page 12

Callaway Nuclear Plant IST Program ATTACHMENT 1 System and P&ID Listing System System Name P&ID AB Main Steam M-22AB02 AE Feedwater M-22AE02 AL Auxiliary Feedwater M-22AL01 AP Condensate Storage and Transfer M-22AP01 BB Reactor Coolant M-22BB01,02,03,04 BG Chemical and Volume Control M-22BG01,02,03,04,05 BL Reactor Makeup Water M-22BL01 BM Steam Generator Blowdown M-22BM01 BN Borated Refuieling Water M-22BN01 EC Fuel Pool Cooling and Cleanup M-22EC01,02 EF Essential Service Water M-22EF01,02,M-U2EF01 EG Component Cooling Water M-22EG01,02,03 EJ Residual Heat Removal M-22EJ01 EM High Pressure Coolant Injection M-22EM01,02 EN Containment Spray M-22EN01 EP Accumulator Safety Injection M-22EP01 FC Auxiliary Feedwater Pump Turbine M-22FC01,02 GK Control Building HVAC M-22GK01,03 GS Containment Hydrogen Control M-22GS01 GT Containment Purge M-22GT01 HB Liquid Radwaste M-22HB01 HD Decontamination M-22HD01 JE Emergency Fuel Oil M-22JE01 KA Compressed Air M-22KA01,02,05 KB Breathing Air for Tasks M-22KB01 KC Fire Protection M-22KC02 KJ Standby Diesel Generator M-22KJ01,02,03,04,05,06 Reactor Bldg & Hot Machine Shop LF Floor and Equip Drain M-22LF03,09 Si Nuclear Sampling System M-22SJ01,04 Revision Date: 12/19/05 Page 13

Callaway Nuclear Plant IST Program ATTACHMENT 2 Pump Relief Request Index Relief Request Description No.

PR-01 j RHR Pump Discharge Pressure Gauge Range Requirements PR-02 I Centrifugal Charging Pump Suction Pressure l Gauge Range Requirements lPR-03j Boric Acid Transfer Pump Flow Measurement Revision Date: 12/19/05 Page 14

Callaway Nuclear Plant IST Program ATTACHMENT 3 Pump Relief Requests Revision Date: 12/19/05 Page 15

Callaway Nuclear Plant IST Program 10 CFR 50.55a Request Number PR-01 RHR Pump Discharge Pressure Gauge Range Requirements Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASME Code Component(s) Affected Pump Number System Class Category PEJOlA EJ 2 A PEJOIB EJ 2 A

2. Applicable Code Edition and Addenda ASME OM Code 2001 Edition through 2003 Addenda

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

4. Reason for Request Pursuant to 10 CFR 50.55a, "Codes and Standards", paragraph (a)(3), relief is requested from the requirement of ASME OM Code ISTB-35 I 0(b)(1). The basis of the relief request is that the proposed alternative would provide an acceptable level of quality and safety.

The installed discharge pressure gauge range of the residual heat removal pumps is 0 - 700 psig. The reference values for discharge pressure during Inservice Testing is between 200 psig and 300 psig. As a result, the instrument range exceeds the requirement of ISTB-35 10(b)(1).

Revision Date: 12/19/05 Page 16

Callaway Nuclear Plant IST Program 10 CFR 50.55a Request Number PR-01 RHR Pump Discharge Pressure Gauge Range Requirements (Continued)

5. Proposed Alternative and Basis for Use Pump discharge pressure is used along with pump suction pressure to determine pump differential pressure. Reference values for the RHR pumps during Inservice Testing is between 200 psig and 300 psig. Based on ISTB-3510(b)(1), this would require as a maximum, a gauge with a range of 0 to 600 psig (3 X 200 psig) to bound the lowest reference value for pressure. Applying the accuracy requirement of +/- 2 % for the quarterly Group A pump test, the resulting inaccuracies due to pressure effects would be +/- 12.0 psig (0.02 X 600 psig).

As an alternative, for the Group A quarterly test, Callaway Nuclear Plant will use the installed discharge pressure gauge (0 to 700 psig) calibrated to less than i 2 %

such that the inaccuracies due to pressure will be less than that required by the Code (+/- 12.0 psig). Use of the installed pressure gauge calibrated to less the i 2

% is equivalent in terms of measuring differential pressure.

Using the provisions of this relief request as an alternative to the specific requirements of ISB-3510(b)(1) 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 requirements identified in this request.

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 3 120 month interval.

7. Precedents This relief request was previously approved for 2 nd 120 Month Interval at Callaway Nuclear Plant as relief request P-01.

Revision Date: 12/19/05 Page 17

Callaway Nuclear Plant IST Program 10 CFR 50.55a Request Number PR-02 Centrifugal Charging Pump Suction Pressure Gauge Range Requirements Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASME Code Component(s) Affected Pump Number Svstem Class Category PBG0SA BG 2 B PBG05B BG 2 B

2. Applicable Code Edition and Addenda ASME OM Code 2001 Edition through 2003 Addenda

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

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

The installed suction pressure gauge range of the centrifugal charging pumps is 0 - 150 psig. The reference values for suction pressure during Inservice Testing are between 30 and 40 psig. As a result, the instrument range exceeds the requirement of ISTB-35 10(b)(1).

Revision Date: 12/19/05 Page 18

Callaway Nuclear Plant IST Program 10 CFR 50.55a Request Number PR-02 Centrifugal Charging Pump Suction Pressure Gauge Range Requirements (Continued)

5. Proposed Alternative and Basis for Use

-Pump suction pressure is used along with pump discharge pressure to determine pump differential pressure. Reference values for the centrifugal charging pumps during Inservice Testing are between 30 psig and 40 psig. Based on ISTB-3510(b)(1), this would require as a maximum, a gauge with a range of 0 to 90 psig (3 X 30 psig) to bound the lowest reference value for pressure. Applying the accuracy requirement of +/- 2 % for the quarterly Group B pump test, the resulting inaccuracies due to pressure effects would be +/- 1.8 psig (0.02 X 90 psig).

As an alternative, for the Group B quarterly test, Callaway Nuclear Plant will use the installed suction pressure gauge (0 to 150 psig) calibrated to less than +/- 2 %

such that the inaccuracies due to pressure will be less than that required by the Code (-+/- 1.8 psig). Use of the installed pressure gauge calibrated to less the +/- 2 %

is equivalent in terms of measuring differential pressure.

Using the provisions of this relief request as an alternative to the specific requirements of ISB-3510(b)(1) 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 requirements identified in this request.

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 3 rd 120 month interval.

7. Precedents This relief request was previously approved for 2nd 120 Month Interval at Callaway Nuclear Plant as relief request P-06.

Revision Date: 12/19/05 Page 19

Callaway Nuclear Plant IST Program 10 CFR 50.55a Request Number PR-03 Boric Acid Transfer Pump Flow Measurement Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASME Code Component(s) Affected Pump Number System Class Category PBG02A BG 3 A PBG02B BG 3 A

2. Applicable Code Edition and Addenda ASME OM Code 2001 Edition through 2003 Addenda

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

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

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

Revision Date: 12/19/05 Page 20.

Callaway Nuclear Plant IST Program 10 CFR 50.55a Request Number PR-03 Boric Acid Transfer Pump Flow Measurement (Continued)

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

As an alternative to measuring differential pressure and flow during the group A quarterly test, only the differential pressure will be measured and compared to its reference value. Additionally, vibration measurements are also recorded and compared to their reference values. The Group A test will be performed on the fixed resistance mini-flow path (Attachment 1). The reference value is approximately 112 psig at a flow rate of 15 gpm. At this flow rate, the point on the pump curve is relatively flat such that a +/- 25% change in flow would result in less than I % change in differential pressure. Based on this, it is not warranted to install additional instrumentation to ensure flow is measured and compared to its reference value.

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

Performing full spectrum analysis, and continued quarterly and comprehensive testing, an accurate assessment of pump health and operational readiness is determined. This alternative provides an acceptable level of quality and safety.

Using the provisions of this relief request as an alternative to the specific requirements of ISTB-5121(c) 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 requirements identified in this request.

This alternative provides an acceptable level of quality and safety.

Revision Date: 12/19/05 Page 21

Callaway Nuclear Plant IST Program 10 CFR 50.55a Request Number PR-03 Boric Acid Transfer Pump Flow Measurement (Continued)

6. Duration of Proposed Alternative This proposed alternative will be utilized for the entire 3d 120 month interval.

7. Precedents This relief request was previously approved for 2nd 120 Month Interval at Callaway Nuclear Plant as relief request P-09.

Attachment 1 Boric Acid Transfer Pump Test Diagram Boric Minimum Flow Acid <Recirculation Line Tank B1618

- BG155(167)

) [f Bl4S666

. ,4_1I6_ Charging Pump Suction

_ BG147(165)

Boric Acid Transfer Pump A(B)

From other Boric Acid Transfer Pump B(A)

Revision Date: 12/19/05 Page 22

Callaway Nuclear Plant IST Program ATTACHMENT 4 COLD SHUTDOWN JUSTIFICATION INDEX Cold Shutdown Justification Description No.

CSJ-01 Main Steam Isolation Valves (ABHVOO1 1,14,17,20)

CSJ-02 Steam Generator Power Operated Relief Valves (ABPV000 1,2,3,4, ABV0345,46,47,48,49,50,51,52)

CSJ-03 l SG Feedwater Supply Isolation Valves (AEFV0039,40,41,42)

CSJ-04 l Auxiliary Feedwater Pump Discharge Check Valves (ALFV0030,42)

CSJ-05 [fAuxiliary Feedwater Pump Discharge Check Valves (ALV=054)

CSJ-06 ll Reactor Vessel Head Vent Valves (BBHV8001A,B, 8002A,B)

CSJ-07 Pressurizer Power Operated Relief Valves (BBPCV0455A,0456A)

CSJ-08 l Hot Leg to RHIR Pump Suction Isolation Valves (BBPV8702A,B)

CSJ-09 [Charging to Regen Heat Exchanger Isolation Valve (BGHV8105,6)

CSJ-10 ifCVCS Letdown Isolation Valves (BGHV8152,8160)

CSJ-l1 VCT Outlet Isolation Valves (BGLCVO I12B,C)

CSJ-12 Letdown to Regen Heat Exchanger Level Control Valves l (BGLCV0459,460)

CSJ-13 Boric Acid to Charging Pumps Suction Check Valves (BGV0147,165,174)

CSJ-14 l Safety Injection Pumps Minimum Flow Isolation Valve (BNHV8813)

CSJ-15 I RHR Heat Exchanger Outlet Check Valves (EJ8730A,B)

CSJ-16 i RHR Pump Suction Isolation Valves (EJHV8701A,B)

CSJ-17 I RHR to RCS Hot Leg Recirculation Isolation Valves (EJHV8716A,B)

CSJ-18 i RHR to SI/CVCS Pumps Supply Isolation Valves (EJHV8804A,B)

CSJ-19 ]f RHR Injection Supply Isolation Valves (EJHV8809A,B)

CSJ-20 I Containment Sump to RHR Suction Isolation Valves (EJHV88 1IA,B)

CSJ-21 [ RHR Train A/B Hot Leg Recirculation Isolation Valve (EJHV8840)

CSJ-22 ][ SI Pump Discharge to RCS Cold Leg Isolation Valve (EMHV8835)

CSJ-23 [ Containment Recirc Sump to CS Pump Isolation Valves (ENHVOOO1,7)

CSJ-24 1 SI Accumulator Tank Outlet Isolation Valves (EPHV8808A,D)

CSJ-25 SI Accumulator Tank Vent Isolation Valves (EPHV8950A,B,CD,EF)

CSJ-26 Reactor Building Supply Flow Control Valve (KAFV0029)

CSJ-27 SG Main Feedwater Control Valves and Bypass Valves I11(AEFCV0510/520/530/540/550/560/570/580)

Revision Date: 12/19/05 Page 23

Callaway Nuclear Plant IST Program ATTACHMENT 5 Cold Shutdown Justifications Page 24 Revision Date: 12/19/05

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-01 Valve Number System Class Category ABHVOO1 AB 2 B ABHV0014 AB 2 B ABHV0017 AB 2 B ABHV0020 AB 2 B Function These normally open, hydraulically operated valves must close to isolate the Steam Generator from the non-safety related portion of the Main Steam header.

The valves are required to close in the event of a Main Steam Line Break or Steam Generator Tube Rupture.

These valves open during normal operation to provide a flow path from the S/G to the main steam power conversion system. The open function does not support safe shutdown or accident mitigation.

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

Closing these valves for testing during normal power operations would interrupt steam flow from the steam generator to the main steam/turbine systems and result in a severe transient. Testing by isolating each main steam header is also possible but would cause a power reduction which is also unacceptable from an operational viewpoint. Partial stroke exercising these valves is also impracticable since even a part-stroke exercise increases the risk of a valve closure when the unit is generating power.

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

Revision Date: 12/19/05 Page 25

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-02 Valve Number System Class Category ABV0345 Al NC C ABV0346 AB NC C ABV0347 AR NC C ABV0348 AR NC C ABV0349 AR NC C ABV0350 AR NC C ABV0351 AB NC C ABV0352 All NC C ABPVOOO1 AB 2 B ABPV0002 All 2 B ABPV0003 AR 2 B ABPV0004 AR 2 B Function Air operated valves ABPVOOO1/2/3/4 are normally closed to isolate the main steam system from atmosphere to prevent overcooling of the RCS. During accidents requiring the use of the AFW Turbine, the valve must remain closed to prevent diverting steam from the AFW Turbine. These valves fail closed on a loss of electrical power or pneumatic supply. These valves must open to allow the main steam to be directed to the atmosphere in order to remove decay heat from the Reactor Coolant System when the MSIVs are closed or the turbine bypass system is not available. These valves open automatically based on pressure to remove decay heat and reduce S/G pressure.

Check valves ABV0345/347/349/251 must open to provide a flow path of safety-related nitrogen supply from the accumulator to the actuator of the Steam Generator PORV during accident conditions.

Check valves ABV0346/348/350/352 must close to provide to prevent backflow from the nitrogen auxiliary gas supply to the Steam Generator PORV actuator thereby allowing the PORV actuator to open to remove heat from the reactor coolant system during accident conditions.

Justification It is impracticable to routinely exercise ABPVOOOI/2/3/4 open or closed during normal power operations since exercising these valves may result in a plant transient and subsequent reactor trip.

Exercising these valves during normal power operations to perform testing would cause a decrease in pressure in the respective main steam header resulting in a power transient which is unacceptable from an operational viewpoint Revision Date: 12/19/05 Page 26

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-02 (Continued)

Alternative Test Air operated valves ABPV0001/2/3/4 will be exercised open and closed and fail safe tested during cold shutdowns.

Check valves ABV0345/347/349/251 will be exercised open and closed when ABPV0001/2/3/4 are exercised at cold shutdowns.

Check valves ABV0346/3481350/352 will be exercised in their non-safety open, direction when ABPV0001/2/3/4 are exercised at cold shutdowns. NOTE:

ABV0346/348/350/352 will be exercised in their safety close direction every quarter and therefore the close test is not part of this justification.

Revision Date: 12/19/05 Page 27

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-03 Valve Number System Class Category AEFV0039 AE 2 B AEFV0040 AE 2 B AEFV0041 AE 2 B AEFV0042 AE, 2 B Function These normally open system medium operated valves must close automatically on a Feedwater Isolation Signal (FWIS) during accident conditions requiring feedwater isolation. Energy for closing the valve is provided by the process fluid (feedwater), which is admitted to the volume above the actuator piston (upper piston chamber) to close the valve. The valve actuator utilize six solenoid valves, three solenoids per actuation train, to perform its design safety function.

These valves are normally open to provide feedwater flow from the feedwater system to the steam generator during normal power operation. This function is not required for safe shutdown or accident mitigation since the supply of normal feedwater is not safety related.

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

Exercising these valves close during normal power operations requires isolating normal feedwater flow to the steam generator. This testing may result in a severe transient in the steam generator and subsequent reactor trip. Partial stroke exercising these valves is also impracticable since even a part-stroke exercise increases the risk of a valve closure when the unit is generating power.

Alternative Test These valves will be exercised closed and fail safe tested during cold shutdowns when the steam generators and feedwater system are not required to be in service.

Revision Date: 12/19/05 Page 28

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-04 Valve Number System Class Category ALFV0030 Al, 2 C ALFV0042 AL 2 C Function These check valves are required to open to provide a flow path from Auxiliary Feedwater pump discharge to the Steam Generators for emergency cool down of the RCS. The auxiliary feedwater pump flow will maintain sufficient water level in the steam generators to ensure adequate heat transfer and continuation of the decay heat removal process.

These check valves must close to prevent the back flow of the other auxiliary feedwater pumps to flow through the associated non-operating pump.

Justification It is impracticable to exercise these valves open or closed during normal power operations since exercising these valves would result in establishing cold water flow to the steam generators.

Exercising these valves open during normal power operations requires injection of cold water into the steam generators to verify the open full flow position of the valves. This type of test places the plant in an undesirable condition since flow through these valves would unnecessarily thermally shock the steam generator feedwater nozzles. Since the closure testing of these valves can only be performed during the open testing, is also impracticable to test these valves closed during normal power operations.

Alternative Test These valves will be exercised open and closed during cold shutdowns.

Revision Date: 12/19/05 Page 29

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-05 Valve Number System Class Cateeorv ALVO054 AJ 2 C Function This check valve is required to open to provide a flow path from Turbine Driven Auxiliary Feedwater pump discharge to the Steam Generators for emergency cool down of the RCS. The auxiliary feedwater pump flow will maintain sufficient water level in the steam generators to ensure adequate heat transfer and continuation of the decay heat removal process.

This check valve must close to prevent the back flow of the other auxiliary feedwater pumps to flow through the associated non-operating pump.

Justification It is impracticable to exercise this valve open or closed during normal power operations since exercising this valve would result in establishing cold water flow to the steam generators.

Exercising this valve open during normal power operations requires injection of cold water into the steam generators to verify the open full flow position of the valve. This type of test places the plant in an undesirable condition since flow through this valve would unnecessarily thermally shock the steam generator feedwater nozzles. Since the closure testing of this valve can only be performed during the open testing, is also impracticable to test this valve closed during normal power operations.

Alternative Test This valve will be exercised open and closed during cold shutdowns.

Revision Date: 12/19/05 Page 30

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-06 Valve Number System Class Category BBHV8001A BB 2 B BBHV8001B BB 2 B BBHV8002A BB 2 B BBHV8002B BB 2 B Function These normally closed solenoid operated valves must open to vent the reactor vessel head during post accident conditions.

The valves must close to maintain the reactor coolant pressure boundary and isolate RCS pressure from the containment atmosphere. These valves fail closed upon loss of power.

Justification It is impracticable to exercise these valves open and closed during normal power operations since exercising these valves would place the plant in an undesirable configuration along with an increase in personnel radiation exposure to perform testing.

Exercising these valves open and closed during normal power operations would require venting of the reactor coolant system directly to containment. During normal power operations this test would result in a potential Loss of Coolant Accident since only one valve would remain to establish the reactor coolant system boundary. Additionally, containment entry is required to install the necessary vent test rig to perform this test. This would result in an increase in personnel radiation exposure.

Alternative Test These valves will be exercised open and closed and fail safe tested during cold shutdowns when the reactor coolant system is depressurized and radiation levels permit entry into containment.

Revision Date: 12/19/05 Page 3 1

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-07 Valve Number System Class Categorv BBPCV0455A BB 1 B BBPCV0456A B1R 1 B Function These normally closed solenoid operated valves must open to provide a flow path from the pressurizer to the pressurizer relief tank to reduce reactor coolant system pressure during low temperature operation. The two pressurizer power operated relief valves are supplied with actuation logic to ensure that a redundant and independent RCS pressure control back-up feature is provided for the operator during low temperature operations.

These valves must close to maintain the reactor coolant system pressure and prevent loss of RCS inventory via the pressurizer relief tank. The valves close automatically when pressurizer pressure is below 2185 psig. Additionally, these valves fail closed upon loss of electrical power.

Justification It is impracticable to exercise these valves open and closed during normal power operations since exercising these valves would cause an RCS pressure transient and subsequent reactor trip.

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

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

Revision Date: 12/19/05 Page 32

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-08 Valve Number System Class Categorv BBPV8702A BB 1 A BBPV8702B BB 1 A Function These normally closed motor operated valves must close or remain closed to isolate the reactor coolant system from the lower pressure residual heat removal system, The valves are considered pressure isolation valves, required to maintain the RCS pressure boundary. The valves are interlocked shut such that they cannot be opened if reactor coolant system pressure in greater than 360 psig.

This valve opens to provide a flow path from the RCS hot leg to the RHR pump suction during normal unit cooldown, when RCS pressure is less than 425 psi.

Justification It is impracticable to exercise these valves open and closed during normal power operations since exercising these valves would place the plant in an undesirable configuration.

Exercising these valves open and closed during normal power operations would require overriding the logic which maintains the valves in their closed safety position when the reactor coolant system is greater than 360 psig. In addition, opening these valves during normal power operations would over pressurize the lower pressure RHR system.

Alternative Test These valves will be exercised open and closed during cold shutdowns when the reactor coolant system is depressurized.

Revision Date: 12/19/05 Page 33

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-09 Valve Number System Class Categorv BGHV8105 BG 2 A BGHV8106 BG 2 B Function These normally open motor operated valves must close automatically upon receipt of a safety injection signal to isolate the normal charging return flow path during the injection mode of ECCS. Closure of these valves ensures adequate injection flow to the reactor coolant system cold legs during all modes of ECCS operation.

These valves may also be closed by remote manual operation to isolate containment from the charging system. Valve BGHV8105 is also considered a containment isolation valve for penetration P-80.

These valves are open during normal operation to provide a flow path from the charging pumps, through the regenerative heat exchanger tubes to recover heat from the letdown flow, then to the reactor coolant system. This function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise: these valves closed (full or partial) during normal power operations since exercising these valves places the plant in an undesirable condition.

Exercising these valves closed during normal power operations places the plant in an undesirable configuration since closure of the valves interrupts charging flow to the reactor coolant system. Interruption of charging flow to the reactor coolant system may result in a loss of pressurizer level control and subsequent reactor trip.

Alternative Test These valves will be exercised closed during cold shutdowns when the chemical and volume control system is not required to be in service.

Revision Date: 12/19/05 Page 34

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-10 Valve Number System Class Category BGHV8152 BG 2 A BGHV8160 BG 2 A Function These normally open air operated valves must close upon receipt of a Phase A containment isolation signal to isolate containment from the chemical and volume control system. The valves are considered containment isolation valves for penetration P-23. These valves also fail closed on loss of air or electrical power.

The valves are normally open to provide a letdown flow path from the letdown orifice header to the letdown heat exchanger. This function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves closed (full or partial) during normal power operations since exercising these valves places the plant in an undesirable condition.

Exercising these valves closed during normal power operations places the plant in an undesirable configuration since failure may cause a loss of pressurizer level control and subsequent reactor trip.

Alternative Test These valves will be exercised closed and fail safe tested during cold shutdowns when the reactor coolant system is depressurized.

Revision Date: 12/19/05 Page 35

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-11 Valve Number System- Class Category BGLCV0112B BG 2 B BGLCV0112C BG 2 B Function These normally open motor operated valves must close automatically upon receipt of a safety injection signal to isolate the volume control tank from the charging pump suction. Closure of these valves is required to ensure a flow path from the refueling water storage tank to the charging pumps during the injection mode of ECCS. The valves will also close automatically upon receipt of a volume control tank low water level signal.

The valves are normally open to provide a suction path from the volume control tank to the charging pumps during normal power operations to maintain and control reactor coolant inventory. This function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves closed (full or partial) during normal power operations since exercising these valves places the plant in an undesirable condition.

Exercising these valves closed during normal power operations places the plant in an undesirable configuration since closure of these valves isolates the normal suction of the charging pumps. Alternate charging suction paths would increase the reactor coolant system boron inventory and may result in a reactor trip.

Alternative Test These valves will be exercised closed during cold shutdowns when the chemical and volume control system is not required to be in service.

Revision Date: 12/19/05 Page 36

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-12 Valve Number System Class Categorv BGLCV0459 BG 1 B BGLCV0460 BG 1 B Function These normally open air operated valves must close automatically upon receipt of a pressurizer low level signal to isolate the letdown line and regenerative heat exchanger from the reactor coolant system thus preventing further loss of reactor coolant. The valves are interlocked such that they can not be opened if any orifice valves (BGHV8149A,B,C) are open. These valves also fail closed upon loss of air or electrical power.

The valves are open to provide a letdown flow path from the reactor coolant system to the regenerative heat exchanger during normal power operation. This function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves closed (full or partial) during normal power operations since closure would isolate the normal letdown flowpath which places the plant in an undesirable condition.

Exercising these valves closed during normal power operations places the plant in an undesirable configuration since normal letdown from the reactor coolant system would be isolated. Closure of these valves at power may cause a voiding effect which could lead to water hammer. Additionally, closure of these valves during normal power operation could adversely affect pressurizer level control and result in a trip of the reactor.

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

Revision Date: 12/19/05 Page 37

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-13 Valve Number System Class Category BGV0147 BG 3 C BGV0165 BG 3 C BGV0174 BG 3 C Function These check valves must open to provide a flow path from the discharge of the boric acid transfer pumps to the charging pump suction header when emergency boration is required.

Valves BGV0147,0165 must close to prevent backflow through an idle pump while the other pump is operating for emergency boration. Closure of this valve ensures adequate flow of boric acid to the charging pump suction header, which is ultimately delivered to the reactor coolant system during emergency boration operations.

Valve BGV0174 must close to prevent the flow of RHR Heat Exchanger discharge or RWST supply to the charging pump suction header from being diverted from the suction of the charging pumps. The closing of this valve will ensure that these other charging pump suction sources will be delivered to the charging pumps, which is ultimately delivered to the reactor coolant system during an accident.

Justification Exercising these valves open during normal power operations requires injection of a substantial amount of boron into the reactor coolant system to verify full flow.

Boration of the reactor coolant system to perform this test would cause a power transient due to the negative reactivity addition and would result in reactor power fluctuations and subsequent reactor trip.

Alternative Test These valves will be exercised open during cold shutdowns when the chemical and volume control and reactor coolant systems are not required. Also, BGV0174 will be exercised close during cold shutdowns. BGV0147 and BGV0165 are exercised closed during normal operations of (the opposite train) boric acid transfer pumps.

Revision Date: 12/19/05 Page 38

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-14 Valve Number System Class Category BNHV8813 BN 2 B Function This normally open motor operated valve must close to isolate the RWST from the safety injection pump discharge piping during switchover from injection mode to recirculation mode of emergency core cooling system (ECCS). The valve is closed by remote manual operation. The valve does not receive any automatic actuation signals and is maintained in the open position with power removed during normal operations.

This valve is normally open to provide a minimum flow path to recirculate flow to the RWST in the event that the pumps are started with the RCS pressure above pump shutoff head. Additionally, this valve permits pump testing during normal plant operation. These functions are not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise this valve closed (full or partial) during normal power operations since closure of this valve would place the plant in an undesirable configuration.

Exercising this valve closed during normal power operations places the plant in an undesirable configuration since both trains of safety injection pumps would be inoperable. Additionally, failure of the valve in the closed position would damage the safety injection pumps due to overheating, in the event of a safety injection signal with the reactor coolant pressure above that of the safety injection pump discharge pressure.

Alternative Test These valves will be exercised closed during cold shutdowns when the safety injection pumps are not required to be in service.

Revision Date: 12/19/05 Page 39

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-15 Valve Number System Class Category EJ8730A EJ 2 C EJ8730B EJ 2 C Function These check valves must open to provide a flow path from the Residual Heat Removal (RHR) Pump to the Reactor Coolant (RCS) System. The valves are located on the discharge header for the associated RHR Pump. The valve isolates one train of RHR and must open to allow flow during the Injection and Recirculation phases of ECCS.

These valves must close to prevent diverting Residual Heat Removal flow when the associated pump is secured but the opposite train pump is running. The RHR System is designed to be a redundant (two train) system. Therefore, one train of RHR could be required in an accident while the other train is secured or inoperable. In that case this valve would be required to close to prevent diverting flow from the operating train.

Justification Exercising these valves open during normal power operations would require injection of cold water by the residual heat removal pumps into the RCS hot legs.

Since the residual heat removal pump can not overcome the reactor coolant system pressure during normal power operations, this testing cannot be performed.

Alternative Test These valves will be exercised open and closed during cold shutdowns.

Revision Date: 12119/05 Page 40

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-16 Valve Number System Class Category EJHV8701A EJ 1 A EJHV8701B EJ 1 A Function These normally closed motor operated valves must close to isolate containment and the Reactor Coolant System from the RHR System. Closure of these valves is by remote manual operation, and they do not receive an automatic signal to close.

The valves are considered containment isolation valves for Penetration P-79/P-52.

The valves are also considered a pressure isolation valves (PIV) and must close to isolate the RCS from the RHR System.

These valves open to provide a flow path from the Reactor Coolant System (RCS) to the Residual Heat Removal (RHR) Pump suction when RCS cooling is required during shutdowns. The RHR system is used to remove heat from the RCS when RCS pressure and temperature are less than 400 psig and 350F, respectively. This valve is interlocked to prevent opening when RCS pressure is greater than 360 psig.

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

Exercising these valves open and closed during normal power operations would require defeating the interlock which maintains the valves closed when reactor coolant pressure is greater than 360 psig. Additionally, opening these valves at power would cause the reactor coolant system to overpressurize the lower pressure residual heat removal system.

Alternative Test These valves will be exercised open and closed during cold shutdowns when the reactor coolant system is depressurized below 360 psig.

Revision Date: 12/19/05 Page 4 1

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-17 Valve Number System Class Categorv EJHV8716A EJ 2 B EJHV8716B EJ 2 B Function These normally open, motor operated valves must open to provide a flow path from the Residual Heat Removal (RHR) pump to the Reactor Coolant System (RCS) cold legs during ECCS Injection. The system is designed such that either RHR pump may inject into all four of the cold legs. Therefore these valves are maintained open during modes 1 through 3. The valves must also open to provide a flow path from the RHR pump to the RCS hot legs during ECCS hot leg recirculation mode. These valves does not receive any automatic actuation signals and are operated by remote manual operation. [FSAR Table 6.3-3]

These valves must close to prevent diversion of flow away from the RCS and the Safety Injection/Charging Pumps during ECCS Cold Leg Recirculation. The RHR System includes two redundant trains. However, the trains are cross-connected on the discharge of the RHR pumps, and these valves isolate one train from the cross-connect pipe. To prevent certain failures from affecting both trains, these valves must close.

Justification It is impracticable to exercise these valves open or closed (full or partial) during normal power operations since closing either valve places the plant in an undesirable configuration.

Exercising the valves open and closed during normal power operations places the plant in an undesirable configuration since closure of either valve isolates the respective RHR pump from two RCS cold legs. In this configuration, both trains of Emergency Core Cooling System (ECCS) are inoperable.

Alternative Test These valves will be exercised open and closed during cold shutdowns.

Revision Date: 12/19/05 Page 42

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-18 Valve Number System Class Category.

EJHV8804A EJ 2 B EJHV8804B EJ 2 B Function These normally closed, motor operated valves must open to provide a flow path from the Residual Heat Removal (RHR) System to the suction of the Centrifugal Charging Pumps (EJHV8804A) and Safety Injection Pumps (EJHV8804B). The valves are required to open to supply the high head pumps with recirculated cooling water. The valves do not receive any automatic actuation signals and are opened by the operator during switchover; EJHV8804A must remain closed during the Injection mode of ECCS to isolate the RHR System from the suction of the Centrifugal Charging Pumps (EJHV8804A}

and Safety Injection Pumps (EJHV8804B) thereby providing sufficient flow for RHR Injection. The valve is interlocked such that it cannot be opened unless the Safety Injection Pump minimum flow line is isolated (EMHV8814A/B closed) and the RHR Suction valve from the RCS (EJHV87O1A/B) is closed.

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

Exercising these valves open during normal power operations would require defeating the ECCS interlocks which would render both trains of safety injection inoperable.

Alternative Test These valves will be exercised open during cold shutdowns.

Revision Date: 12/19/05 Page 43

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-19 Valve Number System Class Categorv EJHV8809A EJ 2 B EJHV8809B EJ 2 B Function These normally open, motor operated valves must remain open to provide a flow path from the Residual Heat Removal (RHR) Pumps to the Reactor Coolant System cold legs during ECCS injection and cold leg recirculation. The valves are maintained open with power removed during Modes 1-3 to ensure a flow path to the RCS cold legs from the RHR System.

The valves must close to isolate the Reactor Coolant System cold legs from the RHR System during hot leg recirculation. These valves do not receive any automatic isolation signals and are closed by the operator during switchover from cold leg recirculation to hot leg recirculation. The valves are also considered containment isolation valves required to close to isolate penetration P-27/82. The valves do not receive a CIS but may be closed by the operator for containment isolation purposes.

Justification It is impracticable to exercise these valves closed (full or partial) during normal power operations since closure of this valve would place the plant in an undesirable configuration.

Exercising the valves closed during normal power operations places the plant in an undesirable configuration since closure of these valves requires restoration of power to the valves and placing the RHR portion of ECCS in an inoperable status.

Alternative Test These valves will be exercised closed during cold shutdowns.

Revision Date: 12/19/05 Page 44

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-20 Valve Number System Class Categor-v EJHV8811A EJ 2 B EJHV8811B EJ 2 B Function These normally closed, motor operated valves must open to provide a flow path from the Containment Recirculation Sump to the suction of the Residual Heat Removal (RHR) Pump when the Emergency Core Cooling (ECCS) System shifts from Injection to Recirculation modes. The valves open automatically on a Refueling Water Storage Tank (RWST) low-low 1 signal coincident with a Safety Injection signal (SIS). [FSAR Table 6.3-3] This function supports safe shutdown and accident mitigation by providing a recirculation flow path from the Containment Sump when the RWST is exhausted following the Injection mode.

The valves are considered Containment Isolation valves for Penetration P-14/15 and may be closed by remote manual operation to isolate the Containment Recirculation Sump and Containment from the Residual Heat Removal System.

These valves do not receive an automatic Contaimnent Isolation signal since it must remain open during the Recirculation mode of ECCS. During normal operations the valves are interlocked and cannot be opened unless the RHR suction valves from both the RWST and RCS are closed.

Justification It is impracticable to exercise these valves open or closed (full or partial) during normal power operations since opening the valves places the plant in an undesirable configuration.

Exercising the valves open and closed during normal power operations places the plant in an undesirable configuration since opening these valves requires defeating the interlocks on the RHR suction isolation valves from the RWST and RCS.

This test would require placing both trains of RHR in an inoperable status.

Alternative Test These valves will be exercised open and closed during cold shutdowns when RHR is not required and the suction isolation valves from the RWST and RCS may be opened.

Revision Date: 12/19/05 Page 45

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-21 Valve Number System Class Category EJHV8840 EJ 2 B Function This normally closed, motor operated valve must open to provide a flow path from the Residual Heat Removal (RHR) pumps to the Reactor Coolant System (RCS) Hot Legs during the Hot Leg Recirculation mode of ECCS. This valve is opened by the operator during switchover from Cold Leg Recirculation to Hot Leg Recirculation. This valve does not receive any automatic signals. Therefore it is opened remote, manually when the Recirculation Phase of ECCS is initiated. This function supports safe shutdown and accident mitigation.

This valve must close to isolate the RCS Hot Legs from the RHR system during Injection and Cold Leg Recirculation modes of ECCS. The valve is maintained in the closed position with power locked out to prevent inadvertent operation during normal power operations. The valve is also a Containment Isolation valve for Penetration P-21 and may be closed by remote manual operation to isolate Containment from the RHR system. The valve does not receive a Containment Isolation Signal since it must open during Hot Leg Recirculation.

Justification It is impracticable to exercise this valve open (full or partial) during normal power operations since opening this valve places the plant in an undesirable configuration.

Exercising the valve open during normal power operations places the plant in an undesirable configuration since opening this valve requires restoration of power to the valve and placing the RIM portion of ECCS in an inoperable status.

Alternative Test These valves will be exercised open during cold shutdowns.

Revision Date: 12/19/05 Page 46

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-22 Valve Number System Class CategorV EMHV8835 EM 2 B Function This normally open motor operated valve must open to provide a flow path from the safety injection pumps to the reactor coolant system cold legs during injection and cold leg recirculation modes of ECCS. This valve is maintained in the open position and blocked from inadvertent operation by having its power removed during normal plant operation.

This valve must close to isolate the reactor coolant system cold legs from the safety injection system during hot leg recirculation. This valve is closed by the operator during switchover from cold leg recirculation to hot leg recirculation and does not receive any automatic isolation signals. This valve is considered a contaimnent isolation valve for penetration P-49 and may be closed by remote manual operation to isolate containment from the safety injection system. This valve does not receive an automatic containment isolation signal since it must remain open during safety injection and cold leg recirculation modes of operation.

Justification It is impracticable to exercise this valve closed and open (full or partial) during normal power operations since closing this valve places the plant in an undesirable configuration.

Exercising the valve open and closed during normal power operations places the plant in an undesirable configuration since closure of this valve isolates the cold leg injection path to the RCS. In this configuration, the cold leg injection path of Emergency Core Cooling System (ECCS) is inoperable.

Alternative Test This valve will be exercised open and closed during cold shutdowns when the safety injection to the cold legs of the RCS is not required to be in service.

Revision Date: 12/19/05 Page 47

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-23 Valve Numl ber I Svste mn I Class I Catevorv JENHVOOOI EN 2 B IENHV0007 EN I 2 B Function This normally closed motor operated valve must open to provide a suction flow path from the containment recirculation sump to the containment spray pump when the containment spray pump suction is switched to the containment recirculation sump. This valve does not receive any automatic actuation signals and is opened remote manually by the operator during switchover to recirculation phase when the low-low-2 level in the RWST is reached.

This valve must remain closed to isolate containment from the containment spray system. The valve receives a confirmatory Phase A containment isolation signal (CIS-A) to close within 30 seconds. This valve is considered a containment isolation valve for Penetration P-13 (ENHV0007) / P-16 (ENHVOOO1).

Justification Exercising the valve open during normal power operations places the plant in an undesirable configuration since opening the valve would run the risk of draining the containment spray pumps suction headers into the contaimnent sump which would cause severe damage to the pumps and render them inoperable. The RWST would be required to be isolated during this testing to prevent flooding of containment should the single check valve fail to close. Current procedure require the containment spray suction header to be drained prior to exercising these valves for testing purposes. Due to the amount of time for system draining/filling/venting to perform this test along with the increased risk associated with the RWST isolated, this testing is considered impracticable to perform during power operations.

Alternative Test These valves will be exercised open and closed during cold shutdowns when the the containment spray suction piping is not required to be inservice and the RWST isolated from the containment spray suction piping.

Revision Date: 12/19/05 Page 48

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-24 Valve Number System Class Categorv EPHV8808A EP 2 B EPHV8808D EP 2 B Function These normally open motor operated valves must remain open to provide a flow path from the safety injection tank accumulator to the reactor coolant system cold leg during accident conditions whenever the reactor coolant system pressure decreases below 600 psia. During normal operation, these valves are maintained in the open position with their power removed to prevent inadvertent operation.

The valves receives a confirmatory signal to open on a safety injection signal and a safety injection signal unblock pressure and are interlocked such that they cannot be closed with an SIS present. The valves are not required to reposition to support any accident analysis events. Therefore, the open function for these valves is considered passive.

These valves must close prior to reducing RCS pressure below 1000 psig to avoid a loss of accumulator water inventory to the reactor coolant system during safe shutdown (hot standby to cold shutdown). Additionally, the valves are closed during normal plant shutdown after the RCS has been depressurized below 1000 psig to prevent a loss of accumulator water inventory to the reactor coolant system. The power to the valves is disconnected after they are closed to prevent inadvertent operation. During normal plant startup, the valve is returned to the open position and power is disconnected before the RCS pressure exceeds 1000 psig.

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

Exercising these valves closed during normal plant operations requires the safety injection accumulator to be isolated. Isolating the a safety injection accumulator during normal power operations places the plant in an undesirable plant configuration rendering the respective safety injection accumulator tanks inoperable.

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

Revision Date: 12/19/05 Page 49

Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-25 Valve Number System Class Category EPHV8950A EP 2 B EPHV8950B EP 2 B EPHV8950C EP 2 B EPHV8950D EP 2 B EPHV8950E EP' 2 B EPHV895OF EP' 2 B Function These normally closed solenoid operated valves must open to depressurize the safety injection accumulator tank during emergency cold shutdown conditions in the event, that the outlet valves 8808A-D cannot be closed, to prevent the loss of accumulator water to the RCS.

These valves are normally closed to isolate the safety injection accumulator tank vent to containment atmosphere, thereby providing sufficient pressure in the accumulator for injection purposes. This function is not required for safe shutdown or accident mitigation since the accumulator level and pressure is continuously monitored and alarmed in the control room. If excessive leakage is detected, the operator is required to take actions to maintain the plant operation within the requirements of Technical Specifications or bring the plant to a safe shutdown condition.

Justification It is impracticable to exercise these valves open (partial or full) during normal power operations since exercising these valves place the plant in an undesirable configuration.

Exercising these valves open during normal power operations would place the plant in an undesirable configuration rendering the respective safety injection accumulator inoperable. The Technical Specification action statement may not allow adequate time to test the valves and restore the accumulator. Additionally, should one of the valves fail to close, insufficient time is allowed to repair/replace/retest prior to shutting down the plant.

Alternative Test These valves will be exercised open during cold shutdowns when the safety injection accumulators are not required to be in service.

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Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-26 Valve Number System Class Categorv KAFV0029 KA 2 A Function This normally open, air operated valve must close to isolate Containment from the non-safety related Instrument Air (KA) System. This valve is a containment isolation valve for Penetration P-30. The valve receives a Phase A Containment Isolation Signal to close automatically within 5 seconds.

This valve is open during normal operation to supply Instrument Air to the Reactor Building primarily for use in operating various valves. However, supplying Instrument Air to the Reactor Building does not support safe shutdown or accident mitigation.

Justification Exercising this valve closed (luring normal power operations would interrupt the instrument air supply to the valves and equipment necessary for system control and operation. Closure of the valve would affect the normal letdown flow path and isolation of the pressurizer spray feature.

Alternative Test These valves will be exercised closed and fail safe tested during cold shutdowns when the instrument air system is not required by important plant components.

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Callaway Nuclear Plant IST Program Cold Shutdown Justification CSJ-27 Valve Number System Class Catezorv AEFCV0510 AE NC B AEFCV0520 AE NC B AEFCV0530 AE NC B AEFCV0540 Al: NC B AEFCV0550 AE NC B AEFCV0560 AE NC B AEFCV0570 AL, NC B AEFCV0580 AE NC B Function These valves provide a diverse backup to the Main Feedwater Isolation Valves to limit the quantity of high energy fluid that enters the containment through the broken loop.

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

Exercising these valves closed during normal power operations requires isolating normal feedwater flow to the steam generator. This testing may result in a severe transient in the steam generator and subsequent reactor trip. Partial stroke exercising these valves is also impracticable since even a part-stroke exercise increases the risk of a valve closure when the unit is generating power.

Alternative Test These valves will be exercised closed and fail safe tested during cold shutdowns when the steam generators and feedwater system are not required to be in service.

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Callaway Nuclear Plant IST Program ATTACHMENT 6 REFUEL OUTAGE JUSTIFICATION INDEX Refuel Outage Justification Description No.

RJ-o1 SG Feedwater Supply Check Valves (AEVO120,121,122,123)

RJ-02 [Normal/Alternate Charging to RCS Check Valves (BB8378A,B,8379A,B)

RJ-03 [RCP Thermal Barrier Cooling Water Valves (BBHVOO13,14,15,16)

RJ-04 [PORV Block Valve Exercising (BBHV8000A,B)

RJ-05 RCP Seal Water Supply Isolation Valves (BBHV835 IA,B,C,D)

RJ-06CCW to RCP Theal Barrier Supply Check Valves (BBV0122,152,212,474,476,479,480 RJ-07 I[VCT to NCP/CCP Hdr Check (BG8440)

RJ-08 [Charging Pump Discharge Check Valves (BG8481A,B)

RJ-09 [ RWST to Charging Pump Suction Check Valves (BG8546A,B)

RJ-10 RCP Seal Water Retum Valves (BGHV8100,8112)

RJ-1 1 ][ RWST to RHR Pump Suction Check Valves (EJ8958A,B)

RJ-12 ][ Charging to RCS Cold Leg (Boron Injection) Check Valve (EM8815)

RJ-13 i Safety Injection Pump Discharge Check Valves (EM8922A,B)

RJ-14 ][ RWST to Safety Injection Pump Suction Check Valves (EM8926A,B)

RJ-15 i SI Pump to Accumulator Fill Line Check Valve (EMV0006)

RJ-16 J Shutdown Purge Isolation Dampers (GTHZ0006,7,8,9)

Revision Date: 12/19/05 Page 53

Callaway Nuclear Plant IST Program ATTACHMENT 7 Refuel Outage Justifications Revision Date: 12/19/05 Page 54

Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-01 Valve Number System Class Categorv AEV0120 AE 2 C AEV0121 AE: 2 C AEV0122 AEi 2 C AEV0123 AE 2 C Function These check valves must open to provide a flow path from the auxiliary feedwater pump to the steam generator during accident conditions requiring auxiliary feedwater system initiation. The valves are open during normal power operation to provide the normal feedwater system flow to the steam generator.

These valves close to prevent reverse flow through the associated feedwater line and to prevent blowdown of the associated Steam Generator in the event of a secondary pipe break upstream of this valve but downstream of the Feedwater Isolation valve.

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

Exercising these valves closed during normal power operations or during cold shutdowns would require isolating feedwater to the steam generator. Isolating feedwater flow to the steam generator would result in a severe transient in the steam generator and possible reactor trip.

Alternative Test These valves will be exercised closed during refueling outages when the feedwater system is not required to be operational.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-02 Valve Number System Class Category BB8378A BB 1 C BB8378B BB 1 C BB8379A BB 1 C BB8379B BB 1 C Function These check valves must close to isolate the reactor coolant system from the lower pressure charging system in the event of a pipe break in the CVCS system.

Valves BBV8378AB open to provide a flow path for normal charging flow from the charging pumps to the RCS. Valves BBV8379A,B open to provide a flow path for alternate charging flow from the charging pumps to the RCS. The normal charging flow path maintains the required water inventory in the RCS during normal operation, power changes, startup, and shutdown. The alternate charging provides backup to the normal charging flow path. These open functions are not required for safe shutdown or accident mitigation since neither the normal charging or alternate charging flow paths are not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these check valves closed during normal power operations or cold shutdown since interrupting charging flow to the RCS places the plant in an undesirable configuration. Access to these valves requires entry behind the reactor bioshield wall inside containment, which is not practicable from a radiation exposure standpoint during normal plant operations and is not practical during cold shutdowns when the area is highly radioactive and the valve body is insulated at a temperature that exceeds non-intrusive equipment adhesive ratings.

Alternative Test These valves will be exercised closed during refueling outages when the charging system is not required and radiation levels permit entry into containment.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-03 Valve Number System Class Categorv BBHV0013 BB 3 B BBHV0014 BB 3 B BBHV0015 BB 3 B BBHV0016 BB 3 B Function These valves must close to isolate the RCS from the component cooling water system in the event of a cooling coil tube leak. In the event of a leak in the thermal barrier, the valves close automatically upon receipt of a high flow signal in the component cooling water return line.

These normally open motor operated valves provide a cooling water return flow path from the RCP thermal barrier cooling coil to the component cooling water system. This function prevents RCP pump damage and degradation of the pump seals that could result due to blockage of RCP cooling water. This function is not required for safe shutdown or accident mitigation since the reactor coolant pumps are not relied upon for safe shutdown.

Justification It is impracticable to exercise these valves closed during normal power operations or during cold shutdowns since interrupting thermal barrier cooling coil flow would damage the reactor coolant pump seals.

Exercising these valves closed, or partially closed during normal power operations or during cold shutdown periods would interrupt flow to the reactor coolant pump thermal barriers which could lead to damage of the pump seals and pump radial bearing which would ultimately damage the pump.

Alternative Test These valves will be exercised closed during refueling outages when the reactor coolant pumps are not required to be in service.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-04 Valve Number System Class Category BBHV8000A BB 1 B BBHV8000B BB 1 B Function These normally open motor operated valves must open to provide a flow path from the pressurizer to the pressurizer relief tank when the power operated relief valve (PORV) is required to be open for reactor coolant system depressurization.

This valve must close to isolate the reactor coolant system pressurizer in the event the pressurizer power operated relief valve (PORV) develops excessive seat leakage or if it fails to close. Additionally, this valve must close by operator action to isolate the reactor coolant system in the event of a spurious PORV actuation signal or during an inadvertent ECCS system initiation.

Justification It is impracticable to exercise these valves during normal power operations or cold shutdown when the PORV is inoperable due to excessive seat leakage. Opening the valve may result in inadvertent depressurization of the RCS.

When these valves are closed to isolate an inoperable PORV (due to excessive leakage) the valve is administratively maintained closed with power to it. If required to open to perform its intended safety function, the valve is opened by the operator. Opening of this valve at any other time, while the PORV is inoperable due to excessive seat leakage, would result in an uncontrolled RCS discharge to the pressurizer relief tank, a loss of pressurizer pressure control, and a potential inadvertent depressurization of the RCS.

Callaway Nuclear Plant Technical Specifications 3.4.11, requires that if the block valve is closed to isolate a PORV due to excessive leakage, that power be maintained to the block valve. This condition may not exceed the next refueling outage.

Additionally, these valves may not be partial stroke exercised since they are not provided with this feature.

Alternative Test These valves will be exercised open and closed quarterly when they are not required to be closed to isolate an inoperable leaking PORV. These valves will be exercised open and closed during refueling outages when the RCS is depressurized when they are required to be closed to isolate a leaking PORV.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-05 Valve Number System Class Category BBHV8351A BB 2 A BBHV8351B BB 2 A BBHV8351C B1 2 A BBHV8351D Bl 2 A Function These normally open motor operated valves must open to provide a flow path from CVCS charging pumps the RCP seals for emergency boration. A portion of the charging flow is directed to the RCPs through the seal water filter, to borate the reactor coolant system to achieve and maintain a safe shutdown [FSAR 9.3.4].

Additionally, the valves open to provide a flow path for RCP seal injection water from CVCS charging pumps the RCP seals. This function prevents RCP pump damage and degradation of the pump seals that could result because a blockage of RCP cooling water.

These valves must close to isolate containment from the CVCS system. The valves are closed by remote-manual control. These valves are required to provide containment isolation for penetration P-22 (8351B) / -39 (8351C) / -40 (8351D) /

-41 (8351A).

Justification Itis impracticable to exercise these valves during normal power operations or cold shutdown since interrupting RCP seal water return flow would damage the reactor coolant pump seals. Interruption of reactor coolant pump seal injection flow when the reactor coolant pumps are in operation would damage the pump seal and ultimately the pump.

Alternative Test These valves will be exercised during refueling outages when the reactor coolant pumps and seal water is not required to be in service.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-06 Valve Number System Class Category BBV0122 BB 3 C BBV0152 BB 3 C BBV0182 BB 3 C BBV0212 Bit 3 C BBV0474 BE 3 C BBV0476 BE 3 C BBV0479 BB 3 C BBV0480 BR 3 C Function These check valves must close to isolate the RCS from the component cooling water system in the event of a cooling coil tube leak.

These valves open to provide a cooling water supply flow path from the component cooling water system to the RCP thermal barrier cooling coil. This function prevents RCP pump damage and degradation of the pump seals that could result due to blockage of RCP cooling water. This function is not required for safe shutdown or accident mitigation since the reactor coolant pumps are not relied upon for safe shutdown.

Justification It is impracticable to exercise these check valves closed during normal power operations since interrupting thermal barrier cooling coil flow would damage the reactor coolant pump seals. Testing these check valves in the safety close direction requires isolating cooling water to the Reactor Coolant Pumps (RCP)

Thermal Barrier Cooling Coils and Motor Coolers. This function is required when the RCP are operating. Loss of RCP seal injection without Thermal Barrier Coolant would cause catastrophic RCP seal failure and a subsequent Small Break Loss of Coolant Accident. Loss of RCP motor cooling would result in catastrophic motor failure which would cause a loss of forced RCS flow. The cooling water to the RCPs is provided by a common header, therefore testing cannot be performed until all four RCPs are off, which does not occur except during reactor refueling outages.

Alternative Test These valves will be exercised closed during refueling outages when the reactor coolant pumps are not required to be in service.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-07 Valve Number System Class Category BG8440 BG 2 C Function This valve must open during the injection mode of ECCS to provide a minimum flow recirculation flow path through the seal water heat exchanger to protect the charging pumps while they are in recirculation operation. This mode will occur when the RWST is still the suction source and a safety injection signal is present.

Additionally, this check valve opens to provide a flow path from the volume control tank to the charging pump suction during normal plant operations. This function is not required for safe shutdown or accident mitigation.

This valve must close to prevent backflow and isolate the seal water heat exchanger piping during recirculation modes of ECCS. Valves BGLCV1 12B/C close to isolate the volume control tank and check valves BG8546A/B close to isolate the refueling water storage tank during hot and cold recirculation modes of ECCS while the charging pumps are supplied by the residual heat removal pumps.

BG8440 must close to prevent diversion of the residual heat removal flow and potentially lifting the seal water heat exchanger relief valve BG81 23.

Justification It is impracticable to exercise this check closed during normal power operations or during cold shutdowns. Exercising the valve requires the performance of a leakage or reverse flow test to verify the closed position.

To perform a leakage test or reverse flow test during normal operations or during cold shutdowns requires temporary test equipment to be installed to establish a differential pressure across the valve to verify closure. This test is impracticable to be performed during nonnal power operations or cold shutdowns since the charging and residual heat removal systems would be required to be drained/vented and out of service to perform a leakage test.

Alternative Test This valve will be exercised closed during refueling outages when the BG and EJ systems are not required to be in service. The open direction of this valve is verified using normal system flow during normal power operations.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-08 Valve Number Systern Class CategorV BG8481A BG 2 C BG8481B BG 2 C Function These check valves must open to provide a flow path from the charging pump to the reactor coolant system cold legs during injection and recirculation modes of ECCS operation.

The valves must close to prevent backflow through an idle pump during ECCS injection and recirculation modes of operation. Closure of this valve ensures adequate flow to the reactor coolant system in the event of a failure of the respective charging pump to start.

Justification It is impracticable to exercise these check valves open during normal power operations or cold shutdowns, since injection into the reactor coolant system during normal operations or cold shutdowns would cause a plant transient and potential reactor trip.

Exercising these valves open requires injection of borated water into the reactor coolant system. Performance of this test during normal plant operations would cause an increase in the reactor coolant boron inventory resulting in a potential reactor trip. Performing this test during cold shutdowns may result in a cold overpressurization of the reactor coolant system.

Alternative Test These valves will be exercised opened and closed during refueling outages when the reactor coolant system is not required to be in service.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-09 Valve Number System Class Category BG8546A BG 2 C BG8546B BG 2 C Function These check valves must open to provide a flow path from the refueling water storage tank to the charging pump suction. Opening of this valve is required to ensure a flow path from the refueling water storage tank to the charging pumps during the injection mode of ECCS. The valves must also open to provide a flow path from the refueling water storage tank to the charging pumps for automatic makeup to the reactor coolant system in the event of a minor leak when valves BNLCV0 l 12D/E open automatically upon receipt of a volume control tank Low-Low Level signal.

The valves must close to prevent back flow of the residual heat removal pumps discharge to the refueling water storage tank during the recirculation phase of ECCS operation. Closure of this valve ensures an adequate suction source for the charging and safety injection pumps.

Justification It is impracticable to exercise these check valves open during normal power operations or cold shutdowns since injection into the reactor coolant system during normal operations or cold shutdowns would cause a plant transient and potential trip of the reactor.

Exercising these valves open requires injection of borated water into the reactor coolant system. Performance of this test during normal plant operations would cause an increase in the reactor coolant boron inventory resulting in a potential trip of the reactor. Performing this test during cold shutdowns may result in a cold overpressurization of the reactor coolant system.

Alternative Test These valves will be exercised opened and closed during refueling outages when the reactor coolant system is not required to be in service.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-10 Valve Number System Class Category BGHV8100 BG 2 A BGHV8112 BG 2 A Function Valves BGHV8100/8112 are normally open motor operated valves which must close automatically upon receipt of a Phase A Containment Isolation signal to isolate containment from the reactor coolant pump seal water return line. These valves are considered a containment isolation valves for penetration P-24. The valves are open to provide a return flow path from the reactor coolant pump seals to the seal water heat exchanger during normal power operations. This function is not required for safe shutdown or accident mitigation since the reactor coolant pump seal water return along with the reactor coolant pumps are not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves during normal power operations or cold shutdown since interrupting RCP seal water return flow would damage the reactor coolant pump seals. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure along with a high potential for delaying plant startup due to the significant amount of piping required to be filled and vented. Additionally, interrupting reactor coolant pump seal injection flow when the reactor coolant pumps are in operation would damage the pump seal and ultimately the pump.

Alternative Test These valves will be exercised during refueling outages when the reactor coolant pumps and seal water is not required to be in service.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-1I Valve Number System Class Category EJ8958A EJ 2 C EJ8958B EJ 2 C Function These check valves must open to provide a flow path from the Refueling Water Storage Tank (RWST) to the Residual Heat Removal Pump (RHR) suction during ECCS Injection following a LOCA.

These valves must close during switchover to the Containment Sump during recirculation to prevent reverse flow from the Containment Sump to the RWST thereby ensuring a suction source for the RHR Pump.

Justification It is impracticable to exercise these valves open or closed during normal power operations or cold shutdowns since exercising the valves requires injection into the RCS.

Exercising these valves open during normal power operations would require injection by the RHR pump into the RCS to verify full flow. Since the RHR pump can not overcome the reactor coolant system pressure during normal power operations, this testing cannot be performed. These valves cannot be exercised during cold shutdowns due to insufficient expansion volume required by injection during cold shutdowns.

Alternative Test These valves will be exercised open and closed during refueling outages when the reactor coolant system is depressurized and injection is possible.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-12 Valve Number System Class Category EM8815 EM 1 AC Function This check valve must open to provide a flow path from the centrifugal charging pumps to the reactor coolant system cold legs during injection and recirculation modes of ECCS.

This check valve must close to isolate containment from the chemical and volume control system. The valve is considered a containment isolation valve for penetration P-88. This valve is also considered a Pressure Isolation Valve and must close to isolate the reactor coolant system from the chemical and volume control system.

Justification It is impracticable to exercise this valve open or closed during normal power operations or cold shutdowns since exercising the valves requires injection into the RCS.

Exercising these valves open during normal power operations or cold shutdowns would require injection by the charging pumps into the RCS to verify full flow.

This test cannot be performed during power operations since injection of borated water into the RCS cold legs would result in a decrease in reactor power resulting in a power transient and subsequent reactor trip. Additionally, injection during power operations would thermally shock the reactor coolant system piping.

During cold shutdown this valve cannot be exercised since injection into the RCS could result in low temperature overpressurization of the reactor coolant system.

Alternative Test This valve will be exercised open and closed during refueling outages when the reactor coolant system is depressurized and injection by the charging pumps into the RCS is possible.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-13 Valve Number System Class Category EM8922A EM 2 C EM8922B EM 2 C Function These check valves must open to provide a flow path from the safety injection pump to the reactor coolant system during ECCS injection and recirculation modes of operation.

The valves must close to prevent backflow through an idle pump during ECCS injection and recirculation modes of operation. Closure of this valve ensures adequate flow to the reactor coolant system in the event of a failure of the respective safety injection pump to start.

Justification It is impracticable to exercise these valves open or closed during normal power operations or cold shutdowns since exercising the valves requires injection into the RCS.

Exercising these valves open during normal power operations or cold shutdowns would require injection by the safety injection pumps into the RCS to verify full flow. This test cannot be performed during power operations since the safety injection pump cannot overcome reactor coolant system pressure. During cold shutdown these valves cannot be exercised since injection into the RCS could result in low temperature overpressurization of the reactor coolant system.

Alternative Test These valves will be exercised open and closed during refueling outages when the reactor coolant system is depressurized and injection by the safety injection pumps into the RCS is possible.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-14 Valve Number System Class Category EM8926A EM 2 C EM8926B EM 2 C Function These check valves must open to provide a flow path from the RWST to the safety injection pumps during the ECCS injection mode.

This valve must close to isolate the RWST from the safety injection pump suction piping during cold and hot leg recirculation modes of ECCS. This isolation provides a suction source from the RHR pump discharge to the safety injection pumps.

Justification It is impracticable to exercise this valve open or closed during normal power operations or cold shutdowns since exercising the valves requires injection into the RCS.

Exercising these valves open during normal power operations or cold shutdowns would require injection by the charging pumps into the RCS to verify full flow.

This test cannot be performed during power operations since the safety injection pump cannot overcome reactor coolant system pressure. During cold shutdown these valves cannot be exercised since injection into the RCS could result in low temperature overpressurization of the reactor coolant system.

Alternative Test These valves will be exercised open and closed during refueling outages when the reactor coolant system is depressurized and injection by the safety injection pumps into the RCS is possible.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-15 Valve Number System Class Category EMV0006 EM 2 AC Function This check valve must close to isolate containment from the safety injection system. This valve is considered a containment isolation valve for penetration P-58.

This valve does not have a safety function in the open direction since it opens only to facilitate maintenance and testing. This valve opens to fill the safety injection accumulators with borated water or adjust level during normal power operations or shutdown. This function is not required for safe shutdown or accident mitigation since the accumulator pressure and level is continuously monitored to assure they can perform their function.

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

To verify closure of this valve requires a backflow/leakage test. This testing requires entry into containment for test alignment and performance. During normal power operations and during cold shutdown periods this testing would result in an increase in personnel radiation exposure along with a high potential for delaying plant startup due: to the significant amount of piping required to be filled and vented. Additionally, during cold shutdowns, a failure of this valve to close could result in a rapid depressurization of the SI accumulator rendering it inoperable.

Alternative Test These valves will be exercised closed during refueling outages when the safety injection accumulators and fill lines are not required to be in service.

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Callaway Nuclear Plant IST Program Refuel Outage Justification RJ-16 Valve Number System Class Cateeory GTHZ0006 GT 2 A GTHZ0007 Gr 2 A GTHZOO08 GT 2 A GTHZ0009 Gr 2 A Function These normally closed air operated valves must close to isolate containment from the containment purge system. This valve closes automatically upon receipt of a containment purge isolation signal (CPIS). The CPIS is initiated by receipt of an SIS or by indication of high radioactivity levels in the purge exhaust system process effluents by one of the purge exhaust radiation monitors. These valves are required to provide containment isolation for penetration V-161. The valves fail closed upon loss of pneumatic supply or electrical power.

These valves are opened by remote manual operation to provide a flow path to/from the containment shutdown purge supply air unit to the containment atmosphere for containment purge during reactor outages. This function is not required for safe shutdown or accident mitigation.

Justification It is impracticable to exercise these valves closed during normal power operations or during cold shutdowns since exercising these valves requires them to be opened prior to the closure test. This testing places the plant in an undesirable configuration.

Exercising these valves closed, or partially closed during normal power operations or during cold shutdown periods would require the valves to be opened. Opening these valves is not permitted during Modes 1, 2, 3, or 4 since they are primary containment boundary valves. Opening these valves would allow the containment to be vented to atmosphere.

Alternative Test These valves will be exercised closed and fail safe tested during refueling outages when the containment boundary is not required.

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Callaway Nuclear Plant IST Program ATTACHMENT 8 Technical Position Index Technical Description Position No.

TP-01 l Bi-directional Testing of Check Valves TP-02 l Testing of Power Operated Valves with Both Active and Passive Safety l_ Functions TP-03 I Passive Valves Without Test Requirements TP-04 Fail Safe Testing of Valves TP-05 ]l Classification of Skid Mounted Components TP-06 Manual Valve Exercise Frequency TP-07 Method for Establishing Acceptance Criteria for Power Operated Valves TP-08 ll Check Valve Condition Monitoring TP-09 j Check Valves in Regular Use iTP-lO ]Categorization of 1ST Pumps (Group A or B)

TP-l II Non-intrusive Check ValveTesting .

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Callaway Nuclear Plant IST Program ATTACHMENT 9 Technical Positions Revision Date: 12/19/05 Page 72

Callaway Nuclear Plant IST Program Technical Position TP-01 (Page 1 of 3)

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

Applicability This Technical Position is applicable to testing of the non-safety function (direction) of check valves which are included in the Inservice Testing Program. This position applies to those check valves required to be tested in accordance with Subsection ISTC (ASME OM Code 2001 Edition through 2003 Addenda) and Appendix II - Condition Monitoring (ASME OM Code 2001 Edition through 2003 Addenda). This Technical Position does not apply to testing of the safety fiuction (direction) of check valves included in the Inservice Testing Program.

Background

The ASME OM Code 2001 through 2003 Addenda section ISTC-3550, "Valves in Regular Use", states:

"Valves that operate in the course of plant operation at a frequency that would satisfy the exercising requirements of this Subsection need not be additionally exercised, provided that the observations otherwise required for testing are made and analyzed during such operation and recorded in the plant record at intervals no greater than specified in ISTC-35 10."

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

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

"Check valves that have a safety function in only the open direction shall be exercised by initiating flow and observing that the obturator has traveled to either the full open position or to the position required to perform its intended function(s) (see ISTC- 1100), and verify closure."

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Callaway Nuclear Plant IST Program Technical Position TP-01 (Page 2 of 3)

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

"Check valves that have a safety function in only the close direction shall be exercised by initiating flow and observing that the obturator has traveled [to] at least the partially open poSition, 3 and verify that on cessation or reversal of flow, the obturator has traveled to the seat."

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

Normal or expected system flow may vary with plant configuration and alignment, however, the open "safety function" of a check valve typically requires a specified design accident flow rate. Since Callaway Nuclear Plant Operations staff is trained in recognizing normal plant conditions, Operator judgment is acceptable in determining the check valve non-safety direction by obtaining normal or expected flow rates for the plant operating condition.

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

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

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

Revision Date: 12/19/05 Page 74

Callaway Nuclear Plant IST Program Technical Position TP-01 (Page 3 of 3)

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

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

The open/closed non-safety function shall be recorded at a frequency required by ISTC-3510, nominally every 3 months, with exceptions as provided, in plant records such as Callaway Nuclear Plant Operating Logs, Electronic Rounds, chart recorders, automated data loggers, etc. Records as indicated above in 1 through 3 are satisfactory for the non-safety direction testing. Any issues regarding check valve operability are addressed using the Corrective Action Program.

Justification This Technical Position requires that the method of determining the non-safety position be established and documented in either the Condition Monitoring Plan or the IST Bases Document. The plant systems and operator actions provide for the observations and analysis that the valve is satisfying its non-safety function. Additionally, the recording of parameters which demonstrate valve position is satisfied at a frequency in accordance with ISTC-3510. These actions collectively demonstrate the non-safety position of Inservice Testing Program check valves in regular use as required by ISTC-3550.

Revision Date: 12/19/05 Page 75

Callaway Nuclear Plant IST Program Technical Position TP-02 (Page 1 of 2)

Testing of Power Operated Valves with Both Active and Passive Safety Functions Purpose The purpose of this Technical Position is to establish the testing requirements for power operated valves which have both an active and passive safety function.

Applicability This Technical Position is applicable to power operated valves which have an active safety function in one direction while performing a passive safety function in the other direction.

Background

The IST Program requires valves to be exercised to the position(s) required to fulfill their safety function(s). In addition, valves with remote position indication shall have their position indication verified. The Code does not restrict position indication to active valves.

Position Several valves included in the plant are designed to perform passive safety functions during accident conditions, and then based on plant accident response, are designed to change positions to perform another (active) function. Once in their final position, there exist no conditions (for certain valves) in which they would be required to be placed in their original passive position.

These valves are typically emergency core cooling system valves, which require changing position during different phases of the accident. After the original passive safety function (e.g. provide flow path) is performed, the valves are repositioned to perform the active safety function (e.g. provide containment isolation or to allow injection from another water source). The valves are not required to return to their original position.

Power operated valves with passive functions in one direction and active in the other, will be stroke timed in only their active position. If these valves have position indication, the position indication verification will include verification of both positions.

Revision Date: 12/19/05 Page 76

Callaway Nuclear Plant IST Program Technical Position TP-02 (Page 2 of 2)

Justification Code Interpretation 01-02 (response to inquiry OMI 99-07) addressed this issue.

Question: If a valve has safety functions in both the open and closed positions and is maintained in one of these positions, but is only required to move from the initial position to the other and is not required to return to the initial position, is stroke timing in both directions required?

Reply: No Revision Date: 12/19/05 - Page 77

Callaway Nuclear Plant IST Program Technical Position TP-03 (Page 1 of 2)

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

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

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

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

Position The Callaway Nuclear Plant Inservice Testing Program, Valve Tables - Attachment 11, will not list valves which meet the following criteria.

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

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

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

Revision Date: 12/19/05 Page 78

Callaway Nuclear Plant IST Program Technical Position TP-03 (Page 2 of 2)

Passive Valves Without Test Requirements Justification Valves which meet this position will not be listed in the Callaway Nuclear Plant Inservice Testing Program, Valve Tables - Attachment 11, however, the basis for categorization and consideration of active/passive functions shall be documented in the IST Program Basis Document.

Revision Date: 12/19/05 Page 79

Callaway Nuclear Plant IST Program Technical Position TP-04 (Page 1 of 1)

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

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

Background

The ASME OM Code 2001 through 2003 Addenda section ISTC-3560 requires; "Valves with fail-safe actuators shall be tested by observing the operation of the actuator upon loss of valve actuating power in accordance with the exercising frequency of ISTC-35 10."

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

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

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

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

Revision Date: 12/19/05 Page 80

Callaway Nuclear Plant IST Program Technical Position TP-05 (Page 1 of 3)

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

Background

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

1, the NRC supports the designation of components as skid mounted:

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

In the 1996a addenda to the ASME OM Code (endorsed by 10CFR50.55(a) in October 2000), the term skid-mounted was clarified by the addition of ISTA paragraph 1.7:

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

Revision Date: 12/19/05 Page 81

Callaway Nuclear Plant IST Program Technical Position TP-05 (Page 2 of 3)

This definition was further clarified in the 1998 Edition of the ASME Code and is also stated in the 2001 Edition:

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

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

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

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

Revision Date: 12/19/05 Page 82

Callaway Nuclear Plant IST Program Technical Position TP-05 (Page 2 of 3)

Position The 2001 ASME OM Code definition of skid mounted should be used for classification of components in the Callaway Nuclear Plant Inservice Testing Program. In addition, for a component to be considered skid mounted:

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

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

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

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

Revision Date: 12/19/05 Page 83

Callaway Nuclear Plant IST Program Technical Position TP-06 (Page 1 of 1)

Manual Valve Exercise Frequency Purpose The purpose of this Technical Position is to establish the station position for the frequency of exercising those manual valves which are required to be exercised.

Applicability This Technical Position is applicable to the manual valves included in the Inservice Testing Program.

Backg~round The ASME OM Code 2001 through 2003 Addenda section ISTC-3540 states; "Manual valves shall be full-stroke exercised at least once every 5 years, except where adverse conditions may require the valve to be tested more frequently to ensure operational readiness."

2Harsh service environment, lubricant hardening, corrosive or sediment laden process fluid, or degraded valve components are some examples of adverse conditions.

In the Federal Register for the Proposed Rule Change dated October 2004, the NRC stated the following with regards to manual valve exercise frequency; "Section 50.55a(b)(3)(vi) is revised to clarify that manual valves must be exercised on a 2-year interval rather that the 5-year interval specified in paragraph ISTC-3540 of the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(3) of this section, provided that adverse conditions do not require more frequent testing."

Position Callaway Nuclear Plant will perform exercising of manual valves within the scope of the IST Program at a frequency not to exceed 2 years.

Justification The NRC Rule Change will be adopted for the frequency of exercising manual valves at least once every 2 years. This interval is more frequent than required by the Edition of the Code used by Callaway Nuclear Plant, therefore no other justification is required.

Revision Date: 12/19/05 Page 84

Callaway Nuclear Plant IST Program Technical Position TP-07 (Page 1 of 2)

Method for Establishing Acceptance Criteria for Power Operated Valves Purpose The purpose of this Technical Position is to establish the station position for establishing the stroke time acceptance criteria for power operated valves, including the Maximum/Limiting Stroke time.

Applicability Power Operated Valves Requiring Stroke Time Testing

Background

The IST Program requires that a valves' stroke time reference value be established in accordance with ASME OM Code 2001 through 2003 Addenda section ISTC-3300. In accordance with the definition in ISTA-2000, reference values are defined as follows:

"one or more values of test parameters measure when the equipment is known to be operating acceptably."

Acceptable ranges are then determined based on these reference values in accordance with ISTC-5114 for Power Operated Relief Valves, ISTC-5122 for Motor Operated Valves, ISTC-5 132 for Pneumatically Operated Valves, ISTC-5 142 for Hydraulically Operated Valves, and ISTC-5152 for Solenoid Operated Valves.

In accordance with the Valve Stroke Testing requirements for the various operator types,

-the maximum/limiting value(s) of full-stroke time of each valve shall be specified by the Owner. Subsection ISTC does not provide specific guidance on determining the limiting value(s). In accordance with NRC Generic Letter 89-04, "Guidance on Developing Acceptable Inservice Testing Programs" "the limiting value should be a reasonable deviation from this reference stroke time based on the valve size, valve type, and actuator type. The deviation should not be so restrictive that it results in a valve being declared inoperable due to reasonable stroke time variations. However, the deviation used to establish the limit should be such that corrective action would be taken for a valve that may not perform its intended function. When the calculated limiting value for a full-stroke is greater than a Technical Specification (TS) or safety analysis limit, the TS or safety analysis limit should be used as the limiting value of full-stroke time.

Revision Date: 12/19/05 Page 85

Callaway Nuclear Plant IST Program Technical Position TP-07 (Page 2 of 2)

Position Callaway Nuclear Plant will use Table TP-08-1 to establish Acceptable Ranges in accordance with ISTC-5114 for Power Operated Relief Valves, ISTC-5122 for Motor Operated Valves, ISTC-5132 for Pneumatically Operated Valves, ISTC-5142 for Hydraulically Operated Valves, and ISTC-5152 for Solenoid Operated Valves. Table TP-08-1 will also be used as general guidance to establish the Maximum/Limiting Value(s) for power-operated valves. Establishment of Acceptable Ranges and Maximum/Limiting Value(s) will be as follows:

• TRef is the reference value in seconds of a valve when it is known to be operating acceptably

• Reference values may be rounded off to the nearest tenth of a second. Acceptable Ranges may be rounded off to the nearest tenth of a second. Calculated IST Limiting Values may be rounded off to the nearest whole number. Standard rounding or conservative rounding techniques are both allowed.

• The most conservative maximum/limiting value between the IST calculated limit (as determined from Table TP-08-1), UFSAR limit, Technical Specification, or design drawing/specification limit should be used as the Maximum/Limiting stroke time.

Any deviations from this criteria will be evaluated.

• When a valve or its control system has been replaced, repaired, or has undergone maintenances that could affect the valve's performance, a new reference value shall be determined or the previous value reconfirmed by an inservice test run before it is returned to service or immediately if not removed from service.

Table TP-08-1 Valve Operator Reference Stroke Acceptable Range Limiting Stroke Time Time Motor 2 TRef> 10.0 0.8 5TRef - 1.15 TRef < 2.0Tp.f Motor TRef < 10.0 0.7 5TRef - 1.25TRef < 2.5Tpf 7 2 Pneumatic/H ydraulic/ TRf > 10.0 0. 5TRf - I. 5TRef < 2.OTpef Solenoid/PORV Pneumatic/Hydraulic/ TRef

• 10.0 0. 50TRef - 1.50TRef

• 2.5TRfe Solenoid/PORV All (Optional) TR:f < 2.0 < 2.0 2.0

'Adjustment of stem packing, limit switches, or control system valves, and removal of the bonnet, stem assembly, actuator, obturator, or control system components are examples of maintenance that could affect valve performance.

2 The maximum/limiting values for EJHV870 lA/B and BBPV8702A/B is 1.5 TRef.

Revision Date: 12/19/05 Page 86

Callaway Nuclear Plant IST Program Technical Position TP-08 (Page 1 of 4)

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

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

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

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

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

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

Revision Date: 12/19/05 Page 87

Callaway Nuclear Plant IST Program Technical Position TP-08 (Page 2 of 4)

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

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

b. Maintenance and modification history shall be reviewed.

c. Test history and results shall be reviewed.

d. System design shall be considered to determine potential flow instabilities, degree of disassembly, and the need for tolerance and dimensional measurements Analysis An analysis of the test and maintenance history shall be performed to establish the basis for specifying inservice testing, examination, and preventive maintenance activities. This analysis shall include the following:

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

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

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

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

Condition Monitoring Activities Valve obturator movement during applicable test or examination activities shall be sufficient to determine the bidirectional functionality of the moving parts. A full open exercise test, or an open test to the position required to perform its intended function is not required for this assessment.

a. Performance Improvement Activities

i. If sufficient information is not available or the results of the analysis performed above are not conclusive, an interim period not to exceed 5 years or 2 refueling outages, whichever is less, shall be established to determine the cause of the failure or maintenance patterns. The following activities shall be performed at sufficient intervals over the interim period.

Revision Date: 12/19/05 Page 88

Callaway Nuclear Plant IST Program Technical Position TP-08 (Page 3 of 4)

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

2. Identify interim examinations to evaluate potential degradation mechanisms.

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

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

5. Identify the interval of each activity.

ii. Identify attributes that will be trended. Trending and evaluation of existing data must be used as the bases to reduce or extend the time interval between tests or examinations.

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

iv. Perform these activities at their assigned intervals until:

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

2. Until the end of the interim period (2 refueling outages or 5 years, whichever is less).

v. After performance, a review shall be performed for each trended attribute along with results for each activity to determine if changes to the program are required. If changes are required, the program shall be revised before the next performance of the activity.

b. Optimization of Condition Monitoring Activities

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

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

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

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

Revision Date: 12/19/05 Page 89

Callaway Nuclear Plant IST Program Technical Position TP-08 (Page 4 of 4)

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

5. Identify the interval of each activity. Interval extensions shall be limited to one fuel cycle per extension. Intervals shall not exceed the maximum interval shown in Table II-4000-1. All valves in a group sampling plan must be tested or examined again, before the interval can be extended again, or until the maximum interval would be exceeded.

(Display Table II-4000-1) ii. Identify attributes that will be trended. Trending and evaluation of existing data must be used to reduce or extend the time interval between tests or examinations.

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

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

v. Review the results of the performance of each activity to determine if changes to the optimized condition monitoring program are required. Changes to IST intervals must consider plant safety and be supported by trending and evaluating both generic and plant-specific performance data to ensure the component is capable of performing its intended function(s) over the entire interval.

Corrective Maintenance If corrective maintenance is performed on a check valve, the analysis used to formulate the basis of the condition-monitoring activities for that valve and its associated valve group shall be reviewed to determine if any changes are required.

Documentation The condition monitoring program shall be documented in IST Manager or equivalent forms and shall contain as a minimum the following information:

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

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

c. Safety function of valve or valve group.

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

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

f. Condition monitoring activities including the trended attributes and the bases for the associated intervals for each valve or valve group.

Revision Date: 12/19/05 Page 90

Callaway Nuclear Plant IST Program Technical Position TP-09 (Page 1 of 2)

Check Valves in Regular Use Purpose The purpose of this Technical Position is to establish the station position for check valves that are in regular use during normal plant operations.

Applicability This Technical Position is applicable to the following check valves which are demonstrated to be open during routine operations. No additional open exercise testing is required.

Background

The ASME OM Code 2001 through 2003 Addenda section ISTC-3550, "Valves in Regular Use", states:

"Valves that operate in the course of plant operation at a frequency that would satisfy the exercising requirements of this Subsection need not be additionally exercised, provided that the observations otherwise required for testing are made and analyzed during such operation and recorded in the plant record at intervals no greater than specified in ISTC-35 10."

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

Normal or expected system flow may vary with plant configuration and alignment, however, the open "safety function" of a check valve typically requires a specified design accident flow rate. For the subject valves, the normal system flow is above the design accident flow rates. Since Callaway Nuclear Plant Operations staff is trained in recognizing normal plant conditions, Operator judgment is acceptable in determining the check valve open finction by obtaining normal or expected flow rates for the plant operating condition.

In summary, check valve open functions are satisfactorily demonstrated by verifying normal or expected flow as applicable.

Revision Date: 12/19/05 Page 91

Callaway Nuclear Plant IST Program Technical Position TP-09 (Page 2 of 2)

Position Callaway Nuclear Plant will verify the open position of these subject check valves by observing plant logs, computer systems, strip chart records, etc. during normal plant operations. The open/closed safety function shall be recorded at a frequency required by ISTC-35 10, nominally every 3 months, with exceptions as provided, in plant records such as Callaway Nuclear Plant Operating Logs, Electronic Rounds, chart recorders, automated data loggers, etc.

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

Revision Date: 12/19/05 Page 92

Callaway Nuclear Plant IST Program Technical Position TP-10 (Page 1 of 2)

Categorization of IST Pumps (Group A or B)

Position Callaway Nuclear Plant has categorized the pumps required to be included in the Inservice Testing Program as either Group A or B in accordance with the requirements of ISTB-1300/2000.

Group A pumps are pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations. The following pumps are categorized as Group A at Callaway Nuclear Power Plant:

Pump Number Class Group Type Function PBG02A 3 A Centrifugal Boric Acid Transfer PBG02B 3 A Centrifugal Boric Acid Transfer PEGOlA 3 A Centrifugal Component Cooling PEGOIB 3 A Centrifugal Component Cooling PEGOIC 3 A Centriffigal Component Cooling PEGOID 3 A Centrifugal Component Cooling PEJOlA 2 A Centrifugal Residual Heat Removal PEJOIB 2 A Centrifugal Residual Heat Removal PALOlA 3 A Centrifugal Auxiliary Feedwater PALOIB 3 A Centrifugal Auxiliary Feedwater PEFOlA 3 A Vertical Essential Service Water PEFOIB 3 A Vertical Essential Service Water Group B pumps are those pumps in standby systems that are not operated routinely except for testing. The following pumps are categorized as Group B at Callaway Nuclear Power Plant:

Pump Number Class Grfoup Type Function PAL02 3 B Centrifugal Auxiliary Feedwater PBG05A 2 B Centrifugal Charging PBGO5B 2 B Centrifugal Charging PEMOIA 2 B Centrifugal Safety Injection PEMOIB 2 B Centrifugal afet Injection PENOIA 2 B Centrifugal Containment Spray PENOIB 2 B Centrifugal Containment Spray Revision Date: 12/19/05 Page 93

Callaway Nuclear Plant IST Program Technical Position TP-10 (Page 2 of 2)

Group A Pump Tests - Group A tests are performed quarterly for each pump categorized as A. The following inservice test parameters are measured for each Group A pump test:

• Speed (if pump is variable speed)

• Differential Pressure Discharge Pressure, (for positive displacement pumps)

Flow Rate

• Vibration Group B Pump Tests - Group B tests are performed quarterly for each pump categorized as B. The following inservice test parameters are measured for each Group B pump test.

• Speed (if pump is variable speed)

• Differential Pressure(')

• Flow Rate(')

(I) For positive displacement pumps, flow rate shall be measured or determined, for all other pumps, differential pressure or flow rate shall be measured or determined.

Comprehensive Pump Tests - Comprehensive pump tests are performed biennially for all pumps in the Inservice Testing Program. The following inservice test parameters are measured for each Comprehensive pump test:

• Speed (if pump is variable speed)

Differential Pressure

• Discharge Pressure, (for positive displacement pumps)

• Flow Rate

• Vibration The following instrument accuracy requirements apply to each test type:

Parameter Group A Group B Comprehensive Pressure +/- 2.0% +/- 2.0% +/- 0.5%

Flow Rate +/- 2.0% +/- 2.0% +/- 2.0%

Speed +/- 2.0% +/- 2.0% +/- 2.0%

Vibration +/- 5.0% +/- 5.0% +/- 5.0%

Differential Pressure +/- 2.0% _ +/- 2.0% +/- 0.5%

Revision Date: 12/19/05 Page 94

Callaway Nuclear Plant IST Program Technical Position TP-11 (Page 1 of 3)

Non-Intrusive Check Valve Testing Purpose The purpose of this Technical Position is to document the acceptability of check valve non-intrusive testing (NIT).

Applicability This Technical Position is applicable to the following check valves:

Valves Non-intrusive test BB8378A,B Close BB8379A,B Close BB8948A,B,C,D Open BB8949B,C Len BBV0001,22,40,59 Open BBV0120,1,150,1,180,1,210,1 Close EJ8841A,B Oen EP8818A,B,C,D Open EP8956A,B,C,D Open

Background

The NRC previously determined that NIT methods appropriate for certain valve applications are acceptable to verify the capability of the valve to open, close, and fully stroke, provided that the licensee properly qualifies the testing methods used for the valve application in accordance with the, plant's quality assurance program requirements.

Position I of Generic Letter 89-04 lists the six criteria to be addressed and documented in the IST Program for the qualification of NIT. This Technical Position will address these six criteria.

References

1. GL 89-04, Guidance on Developing Acceptable Inservice Testing Program

2. NUREG 1482 Revision 1

3. NRC Information Notice (IN) 2000-21, Detached Check Valve Disc Not Detected by Use of Acoustic and Magnetic Nonintrusive test techniques Revision Date: 12/19/05 Page 95

Callaway Nuclear Plant IST Program Technical Position TP-1 1 (Page 2 of 3)

Position

• Impracticality of performing a full-flow test Callaway currently has several configurations where total flow to multiple leg injection lines, containing the subject check valves which require full open stroke testing, is measured. However, the individual leg flowrates are not measured because the individual lines do not have permanently installed flow measuring instrumentation. So, while a full flow test is possible, measuring the flowrate in each individual injection line is impractical.

• A description of the alternative technique used and a summary of the procedures being followed.

• A description of the instrumentation used and the maintenance and calibration of the instrumentation.

NIT at Callaway involved the use of Liberty Technology "QuickCheck" system (up to RFIO) and is currently using the Crane Nuclear "Viper" system. The Liberty QuickCheck system used accelerometers and a portable data acquisition unit, which had data analysis software, to collect and analyze test signatures. The Crane Viper system uses accelerometers, eddy current probes, and sound card technologies with a portable data acquisition unit to collect and analyze test signatures. In addition, other supporting test equipment used are accelerometer/eddy current mounting studs, adhesive, cables, and equipment to measure the accelerometer/eddy current probe locations.

The Liberty QuickCheck data acquisition equipment - accelerometers and data acquisition unit - was calibrated every 18 months. The Crane Viper data acquisition equipment - accelerometers, pre-arnps, and data acquisition unit - is calibrated annually based on vendor recommendations. Cables are inspected before every refueling outage.

Callaway administrative procedures being followed for NIT testing are EDP-ZZ-01 122, Check Valve Predictive Performance Manual and ETP-ZZ-01331, Crane Nuclear Diagnostic System for Testing Check Valves. In addition, the IST Program lists the applicable operations surveillance procedures (OSP) that test the subject check valves.

Revision Date: 12/19/05 Page 96

Callaway Nuclear Plant IST Program Technical Position TP-11 (Page 3 of 3)

• A description of the method and results of the program to qualify the alternative technique for meeting the ASME Code.

A description of the basis used to verify that the baseline data has been generated when the valve is known to be in good working order, such as recent inspection and maintenance of the valve internals (components).

The generic qualification of non-intrusive testing was done under the Nuclear Industry Check Valve Group (NIC) Phase 1 through 3 reports and the Check Valve Nonintrusive Analysis Guide, also prepared by NIC. Callaway's non-intrusive check valve testing is performed by trained and qualified personnel in data acquisition and analysis.

All of the check valves listed in this Technical Position are included in the Callaway Check Valve Condition Monitoring Program. The Condition Monitoring Program contains information on the valve grouping, valve grouping basis, and system flow condition tolerances.

Trained and qualified Callaway personnel continually evaluate the quality of the NIT test signatures to verify the quality of the test data. The Corrective Action Program is used to address and document deficiencies in the quality of the test data or adverse test data trends. The Condition Monitoring Program documents these reviews and based on the evaluated results may require changes to the Condition Monitoring Program.

In general, Callaway used disassembly and inspection and/or seat leakage testing to verify a check valve was known to be in good working order before NIT began. However, Callaway identified baseline deficiencies during a review of NRC IN 2000-21 (CAR 200003220). Deficiencies were corrected under CAR 200301844. The Corrective Action Program is used to address and document any deficiencies identified during inspection and maintenance activities. The Condition Monitoring Program documents these reviews of recent inspection and maintenance work and based on these evaluated results may require changes to the Condition Monitoring Program.

Revision Date: 12/19/05 Page 97

Callaway Nuclear Plant ISTr Program ATTACHMENT 10 Inservice Testing Pump Table Revision Date: 12/19/05 Page 98

Callaway

[ST Program Plan Pump Table Pump Safety Pump Nominal P&ID Test Relief Tech.

Location Class Pump Type Driver Speed P&ID Coor. Category Test Type Freq. Request Pos.

PAL01A 3 Centrifugal Motor N/A M-22AL01 D4 Group A DPa M3 DPc Y2 Qa M3 Qc Y2 Va M3 Vc Y2 Pump Name: MOTOR DRIVEN AUXILIARY FEEDWATER PUMP A PAL01B 3 Centrifugal Motor N/A M-22AL01 H4 Group A DPa M3 DPc Y2 Qa M3 Oc Y2 Va M3 Vc Y2 Pump Name: MOTOR DRIVEN AUXILIARY FEEDWATER PUMP B PAL02 3 Centrifugal Turbine 3850 M-22AL01 B4 Group B DPb M3 DPc Y2 Qc Y2 Vc Y2 Pump Name: TURBINE DRIVEN AUXILIARY FEEDWATER PUMP PBG02A 3 Centrifugal Motor N/A M-22BG-5 B-7 Group A DPa M3 DPc Y2 Oa M3 PR-03 Qc Y2 Va M3 Vc Y2 Pump Name: CVCS BORIC ACID TRANSFER PUMP A PBG02B 3 Centrifugal Motor N/A M.22BG05 A-7 Group A DPa M3 DPc Y2 Qa M3 PR-03 Qc Y2 Va M3 Vc Y2 Pump Name: CVCS BORIC ACID TRANSFER PUMP B Revision Date: 12/19/2005 Page 99

Callaway IST Program Plan Pump Table Pump Safety Pump Nominal P&ID Test Relief Tech.

Location Class Pump Type Driver Speed PID Coor. Category Test Type Freq. Request Pos.

PBGO5A 2 Centrfugal Motor N/A W22BG03 B-5 Group B DPb M3 PR-02 DPc Y2 Qc Y2 Vc Y2 Pump Name: CENTRIFUGAL CHARGING PUMP A PBGO5B 2 Centrifugal Motor N/A M-22BG03 C-5 Group B DPb M3 PR-02 DPc Y2 oc Y2 Vc Y2 Pump Name: CENTRIFUGAL CHARGING PUMP B PEF01A 3 Vertical Line Shaft Motor NIA M-U2EF01 G-6 Group A DPa M3 DPc Y2 Qa M3 Qc Y2 Va M3 Vc Y2 Pump Name: ESSENTIAL SERVICE WATER PUMP A PEF01B 3 Vertical Line Shaft Motor N/A M-U2EF01 D-6 Group A DPa M3 MPc Y2 Qa M3 oc Y2 Va M3 Vc Y2 Pump Name: ESSENTIAL SERVICE WATER PUMP B PEGOIA 3 Centrifugal Motor N/A M-22EG01 G4 Group A DPa M3 DPc Y2 Qa M3 Qc Y2 Va M3 Vc Y2 Pump Name: COMPONENT COOLING WATER PUMP A Revision Date: 12/19/2005 Page 100

Callaway IST Program Plan Pump Table Pump - w1, Pump Nominal P&ID Test Relief Tech.

Locatiom - Pump Type Driver Speed P&ID Coor. Category Test Type Freq. Request Pos.

PEG01' Centrifugal Motor N/A M-22EG01 D4 Group A DPa M3 DPc Y2 Qa M3 Qc Y2 Va M3 Vc Y2 nu; . Name: COMPONENT COOLING WATER PUMP B PEG01iC Centrifugal Motor N/A M-22EG01 E4 Group A DPa M3 DPc Y2 Qa M3 Qc Y2 Va M3 Vc Y2 Pump Name: COMPONENT COOLING WATER PUMP C PEG-1 D 3 Centrifugal Motor N/A M22EG01 B-4 Group A DPa M3 DPc Y2 Qa M3 Qc Y2 Va M3 Vc Y2 Pump Name: COMPONENT COOLING WATER PUMP D 2 Centrifugal Motor N/A M-22EJ01 G-6 Group A DPa M3 PR-01 DPc Y2 Qa M3 Qc Y2 Va M3 Vc Y2 Pump Name: RESIDUAL HEAT REMOVAL PUMP A Centrifugal Motor N/A M-22EJ01 C(6 Group A DPa M3 PR-01 DPc Y2 Qa M3 Qc Y2 Va M3 Vc Y2 Pump Name: RESIDUAL HEAT REMOVAL PUMP B Revision Date: 12/19/2005 Page 101

Callaway iST Program Plan Pump Table Pump Safety Pump Nominal P&ID Test Relief Tech.

Location Class Pump Type Driver Speed P&ID Coor. Category Test Type Freq. Request Pos.

PEM01A 2 Centrifugal Motor N/A M-22EM01 E-6 Group B DPb M3 DPc Y2 Qc Y2 Vc Y2 Pump Name: SAFETY INJECTION PUMP A PEM01B 2 Centrifugal Motor N/A M-22EM01 D-6 Group B DPb M3 DPc Y2 oc Y2 Vc Y2 Pump Name: SAFETY INJECTION PUMP B PEN01A 2 Centrifugal Motor N/A M-22EN01 G-6 Group B DPb M3 DPc Y2 Qc Y2 Vc Y2 Pump Name: CONTAINMENT SPRAY PUMP A PEN01B 2 Centrifugal Motor N/A MI22ENO1 B-6 Group B DPb M3 DPc Y2 oc Y2 Vc Y2 Pump Name: CONTAINMENT SPRAY PUMP B Revision Date: 12/19/2005 Page 102

Callaway Nuclear Plant IST Program ATTACHMENT 1 1 Inservice Testing Valve Table Revision Date: 12/19/05 Page 103

Callaway IST Program Plan Main Steam (AB) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Locaiion P&ID Coor. Class Cat Size Type Type Passive Posifton Position Type Freq. Request Just. Pos.

ABHV0005 M-22AB02 D4 2 B 4.0 GB AO Active C 0 BTO M3 FO M3 TP-04 PIT Y2 Valve Name: TDAFP STM SPLY FROM MS LOOP 2 ABHV0006 M-22AB02 C-4 2 B 4.0 GB AO Active C 0 BTO M3 FO M3 TP-04 PIT Y2 Valve Name: TDAFP STM SPLY FROM MS LOOP 3 ABHV0011 M-22AB02 G-3 2 B 28.0 GT HO Active 0 C BTC Cs CSJ-01 PIT Y2 Vaive Name: SG D MSIV ABHVW9i2 M-22AB02 G-3 2 B 2.0 GB AO Passive C C PIT Y2 Valve Name: SG D MS LOOP 4 ABHV0011BYP ISO HV ABF!'A 1MA M-22AB02 F-3 2 B 28.0 GT HO Active 0 C BTC CS CSJ-41 PIT Y2 Valve Name: SG A MSIV

,ic3,:- i 22AB02 v., F-3 2 B 2.0 GB AO Passive C C PIT Y2 Valve Name: SG A MS LOOP 1 ABHV0014 BYP ISO HV f PI-V0017 M-22AB02 D-3 2 B 28.0 GT HO Active 0 C BTC CS CSJ-01 PIT Y2 Valve Name: SG B MSIV AbHVU0118 M-22AB02 D-3 2 B 2.0 GB AO Passive C C PIT Y2 Valve Name: SG B MS LOOP 2 ABHV0017 BYP ISO HV

,BHV0020 M-22AB02 C-3 2 B 28.0 GT HO Active 0 C BTC CS CSJ-01 PIT Y2 Valve Name: SG C MSIV ABHV0021 M-22AB02 C-3 2 B 2.0 GB AO Passive C C PIT Y2 Valve Name: SG C MS LOOP 3 ABHV0020 BYP ISO HV Revision Date: 12/19/2005 Page 104

Callaway IST Program Plan Main Steam (AB) Valve Table P&ID Safety Valve Act. Active l Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

ABHVOU48 M-22AB02 D-4 2 B 1.0 GB AO A 0 C BTC M3 FC M3 TP.04 PIT Y2 Valve Name: MS LOOP 2 WARMUP STM SPLY TO TDAFP ISO HV ABHV0049 M22AB02 C4 2 B 1.0 GB AO A 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: MS LOOP 3 WARMUP STM SPLY TO TDAFP ISO HV ABLVO007 M-22AB02 B4 2 B 2.0 GB AO Active C C BTC 113 FC M3 TP-04 PIT Y2 Valve Name: MS LOOP 3 LO PNT DRN LCV ABLVO008 M-22AB02 D-5 2 B 20 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: MS LOOP 2 LO PNT DRN LCV ABLVO009 M22AB02 E4 2 B 2.0 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: MS LOOP 1 LO PNT DRN LCV MEavVoVIo M22AB02 G4 2 B 2.0 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: MS LOOP 4 LO PNT DRN LCV ABPV00011 M22AB01 G-3 2 B 8.0 GB AO Active C O/C BTC CS CSJ02 BTO CS CSJ-02 FC CS CSJ-02 TP04 PIT Y2 Valve Name SG A MS TO ATMS PORV Revision Date: 12/19/2005 Page 105

Callaway IST Program Plan Main Steam (AB) Valve Table P&D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

ABPV0002 M-22AB01 C-3 2 B 8.0 GB AO Active C O/C BTC CS CSJ-02 BTO CS CSJ-02 FC CS CSJ-02 TP-04 PIT Y2 Valve Name: SG B MS TO ATMS PORV ABPV0003 M-22AB01 C-6 2 B 8.0 GB AO Active C O/C BTC CS CSJ-02 BTO CS CSJ-02 FC CS CSJ-02 TP-04 PIT Y2 Valve Name: SG C MS TO ATMS PORV ABP'J0004 M-22AB01 G-6 2 B 8.0 GB AO Actve C O/C BTC CS CSJ-02 BTO CS CSJ-02 FC CS CSJ-02 TP-04 PIT Y2 Valve Name: SG D MS TO ATMS PORV ABV0007 M-22AB01 G-6 2 B 10.0 GT MA Active LO O/C BTC Y2 TP-06 BTO Y2 TP-06 Valve Name: SG D MS PORV MAN ISO ABV0018 M-22A801 G-3 2 B 10.0 GT MA Aclive LO O/C BTC Y2 TP-06 BTO Y2 TP-06 Valve Name: SG A MS PORV MAN ISO ABV0029 M-22AB01 C-6 2 B 10.0 GT MA Active LO O/C BTC Y2 TP-06 BTO Y2 TP-06 Valve Name: SG C MS PORV MAN ISO ABV0O40 M-22AB01 C-2 2 B 10.0 GT MA Active LO O/C BTC Y2 TP-06 BTO Y2 TP-06 Valve Name: SG B MS PORV MAN ISO ABV0045 M-22AB02 H-7 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 4 SFTY RLF ABV0046 M-22AB02 H-7 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 4 SFTY RLF Revision Date: 12/19/2005 . Page 106

Callaway IST Program Plan Main Steam (AB) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

ABV0047 M-22AB02 H-4 2 C 6.0 RV SA Active C 0/C RT Y5 Valve Name: MS LOOP 4 SFTY RLF ABV0048 M-22AB02 H-5 2 C 6.0 RV SA Active C 0/C RT Y5 Valve Name: MS LOOP 4 SFTY RLF ABV0049 M-22AB02 H-5 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 4 SFTY RLF ABV0055 M-22AB02 F-7 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP I SFTY RLIF ABV0056 M-22AB02 F-7 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP I SFTY RLF ABV0057 M-22AB02 F46 2 C 6.0 RV SA Active C 0/C RT Y5 Valve Name: MS LOOP I SFTY RLIF ABV0058 M-22AB02 F-5 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 1 SFTY RLF ARVO059 M-22AB02 F-5 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP I SFTY RLF ABV0065 M-22AB02 D-7 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 2 SFTY RLF ABV0066 W22AB02 D-7 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 2 SFTY RLF ABV0067 M-22AB02 D-6 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 2 SFTY RLF e 8V0068 M-22AB02 D-5 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 2 SFTY RLF ABV0069 M-22AB02 D-5 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 2 SFTY RLF ABV0075 M-22AB02 C-7 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 3 SFTY RLF Revision Date: 12/19/2005 Page 107

Callaway IST Program Plan Main Steam (AB) Valve Table P&ID Safety Valve AcL Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

ABV0076 M-22AB02 C-7 2 C 6.0 RV SA Active C 0UC RT Y5 Valve Name: MS LOOP 3 SFTY RLF ABV0077 M-22AB02 C-6 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 3 SFTY RLF ABV0078 M-22AB02 C-5 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 3 SFTY RLF ABV0079 M-22AB02 C-S 2 C 6.0 RV SA Active C O/C RT Y5 Valve Name: MS LOOP 3 SFTY RLF ABV0085 M-22AB02 D4 2 B 4.0 GT MA Active LO O/C BTC Y2 TP-06 Valve Name: TDAFP STM SPLY FROM MS LOOP 2 MAN ISO ABV0087 M-22AB02 CA 2 8 4.0 GT MA Active LO O/C BTC Y2 TP-06 Valve Name: TDAFP STM SPLY FROM MS LOOP 3 MAN ISO ABV0345 M-22AB01 H-2 NC C 0.75 CK SA Active SYS 0 CC CS CSJ402 TP-41 CO CS CSJ42 Valve Name: N2 SPLY CHECK VLV TO ABPVOOO1 ABV0346 M-22AB01 H-2 NC C 0.75 CK SA Active SYS C CC M3 CO CS CSJ-02 TP401 Valve Name: AIR SPLY CHECK VLV TO ABPV0001 AEV0347 M-22AB01 D-2 NC C 0.75 CK SA Active SYS 0 CC CS CSJ402 TP-01 CO Cs CSJ402 Valve Name: N2 SPLY CHECK VLV TO ABPV0002 ABV0348 M-22AB01 D-2 NC C 0.75 CK SA Active SYS C CC M3 CO CS CSJ42 TP-01 Valve Name: AIR SPLY CHECK VLV TO ABPVD002 ABV0349 M-22AB01 D-5 NC C 0.75 CK SA Active SYS 0 CC CS CSJ-02 TP-01 CO CS CSJ-02 Valve Name: N2 SPLY CHECK VLV TO ABPV0003 ABV0350 M-22AB01 D-5 NC C 0.75 CK SA Active SYS C CC M3 CO CS CSJ-02 TP-01 Valve Name: AIR SPLY CHECK VLV TO ABPV0003 Revision Date: 12119/2005 Page 108

Callaway

[ST Program Plan Main Steam (AB) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&Dl Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

ABV0351 M-22AB01 H-5 NC C 0.75 CK SA Active SYS 0 CC Cs CSJ-02 TP-01 CO CS CSJ-02 Valve Name: N2 SPLY CHECK VLV TO ABPV0004 ABV0352 M-22AB01 H-5 NC C 0.75 CK SA Active SYS C CC M3 CO CS CSJ-02 TP-01 Valve Name: AIR SPLY CHECK VLV TO ABPVO004 Page 109 Revision Date:

Reitision Date: 12119/2005 12119/2005 Page 109

Callaway IST Program Plan Feedwater (AE) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

AEFCV0510 M-22AE01 F-7 NC B 14.0 ANG AO Active 0 C BTC CS CSJ-27 PIT Y2 Valve Name: SGAIMFW REGVLV AEFCV0520 M-22AE01 C-7 NC B 14.0 ANG AO Active 0 C BTC CS CSJ-27 PIT Y2 Valve Name: SG B MFW REG VLV AEFCVW530 M-22AE01 A-7 NC B 14.0 ANG AO Active 0 C BTC CS CSJ-27 PIT Y2 Valve Name: SG C MFW REG VLV AEFCV0540 M-22AE01 G-7 NC B 14.0 ANG AO Active 0 C BTC CS CSJ-27 PIT Y2 Valve Name: SG D MFW REG VLV AEFCV0550 M-22AE01 E-7 NC B 6.0 GB AO Passive C C BTC CS CSJ-27 FC CS CSJ-27 PIT Y2 Valve Name: SG A MFW REG VLV BYP VLV AERMWO560 M-22AE01 C-7 NC B 6.0 GB AO Passive C C BTC CS CSJ-27 FC CS CSJ-27 PIT Y2 Valve Name: SG B MFW REG VLV BYP VLV AFFCV0570 M-22AE01 A-7 NC B 6.0 GB AO Passive C C BTC CS CSJ-27 FC CS CSJ-27 PIT Y2 Valve Name: SG C MFW REG VLV BYP VLV

..'580 M-22AE01 G-7 NC B 6.0 GB AO Passive C C BTC CS CSJ-27 FC CS CSJ-27 Y2 Y2 Valve Name: SG D MFW REG VLV BYP VLV AEFV0039 M-22AE02 G-3 2 B 14.0 GT SA Active 0 C BTC CS CSJ-03 FC CS CSJ-03 TP-04 PIT Y2 Valve Name: SG A FW SPLY ISO FV Revision Date: 12/1912005 - Page 110

Callaway

[ST Program Plan Feedwater (AE) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

AEFV0040 M-22AE02 D-3 2 B 14.0 GT SA Active 0 C BTC CS CSJ-03 FC CS CSJ403 TP-04 PIT Y2 Valve Name: SG B FW SPLY ISO FV AEFV0041 M-22AE02 D-6 2 B 14.0 GT SA Active 0 C BTC CS CSJ-03 FC CS CSJ-03 TP-04 PIT Y2 Valve Name: SG C FW SPLY ISO FV AEFV0042 M-22AE02 H-6 2 B 14.0 GT SA Active 0 C BTC CS CSJ-03 FC CS CSJ-03 TP-04 PIT Y2 Valve Name: SG D FW SPLY ISO FV AEV0120 M-22AE02 C4 2 C 14.0 CK SA Active SYS O/C CC RR RJ-01 CO OP TP-09 Valve Name: SG B FW SPLY CHECK AEV0121 M-22AE02 F-4 2 C 14.0 CK SA Active SYS O/C CC RR RJ-01 CO OP TP-09 Valve Name: SG A FW SPLY CHECK AEV0122 M-22AE02 F-7 2 C 14.0 CK SA Active SYS O/C CC RR RJ-01 CO OP TP-09 Valve Name: SG D FW SPLY CHECK AFV'123 M-22AE02 C-7 2 C 14.0 CK SA Active SYS O/C CC RR RJ-01 CO OP TP-09 Valve Name: SG C FW SPLY CHECK AEV0124 M-22AE02 C-3 2 C 4.0 CK SA Active SYS O/C CCD CM TP-08 CCT CM TP48 COD CM TP48 COF CM TP-08 Valve Name: SG B AUX FW SPLY CHECK Revision Date: 12/19/2005 Page 111

Callaway

[ST Program Plan Feedwater (AE) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

AEV0125 M-22AE02 F-3 2 C 4.0 CK SA Active SYS O/C CCD CM TP-08 CCT CM TP08 COD CM TP-08 COF CM TP-08 Valve Name: SG A AUX FW SPLY CHECK AEVW126 M-22AE02 F-6 2 C 4.0 CK SA Active SYS OC CCD CM TP-08 CCT CM TP-08 COD CM TP-08 COF CM TP-08 Valve Name: SG D AUX FW SPLY CHECK AEV0127 M-22AE02 C4 2 C 4.0 CK SA Active SYS O/C CCD CM TP-08 CCT CM TP-08 COD CM TP-08 COF CM TP-08 Valve Name: SG C AUX FW SPLY CHECK Page 112 Revision Date:

Revision Date: 12/19/2005 12/19/2005 Page 112

Callaway IST Program Plan Auxiliary Feedwater (AL) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

ALFV0030 M-22AL01 H-5 2 C 6.0 CK SA Active SYS 01C CC CS CSJ-04 CO CS CSJ-04 Valve Name: MD AFP B DISCH AUTO RECIRC CONTROL CHECK VLV ALFV0042 M-22AL01 D-5 2 C 6.0 CK SA Active SYS O/C CC CS CSJ-04 CO CS CSJ-04 Valve Name: MD AFP A DISCH AUTO RECIRC CONTROL CHECK VLV ALHV0005 M-22AL01 H-6 2 B 4.0 GB MO Active 0 OIC BTC M3 BTO M3 PIT Y2 Valve Name: MDAFP B TO SIG D HV ALHV0006 M-22AL01 G-6 2 S 4.0 GB AO Actve 0 01C BTOCM3 BTO M3 FO M3 TP-04 PIT Y2 Valve Name: TDAFP TO SIG D HV ALHV0007 M-22AL01 F-6 2 B 4.0 GB MO Active 0 01C BTC M3 BTO M3 PIT Y2 Valve Name: MDAFP B TO SIG A HV ALHV0008 M-22AL01 E-6 2 B 4.0 GB AO Active 0 01C 8TC M3 BTO M3 FO M3 TP-04 PIT Y2 Valve Name: TDAFP TO SIG A HV ALHV009 M-22AL01 D-6 2 B 4.0 GB MO Active 0 OIC BTC M3 BTO M3 PIT Y2 Valve Name: MDAFP TO SIG B HV ALHV0010 M-22AL01 D-6 2 B 4.0 GB AO Active 0 OC BTC M3 BTO M3 FO M3 TP-04 PIT Y2 Valve Name: TDAFP TO SIG B HV Revision Date: 12/19/2005 Page 113

Callaway IST Program Plan Auxiliary Feedwater (AL) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Ske Type Type Passive Position Position Type Freq. Request Just. Pos.

ALHV0011 M-22AL01 C-6 2 B 4.0 GB MO Active 0 OIC BTC M3 BTO M3 PIT Y2 Valve Name: MDAFP TO SIG C HV ALHV0012 M-22AL01 B-6 2 B 4.0 GB AO Active 0 OIC BTC M3 BTO M3 FO M3 TP-04 PIT Y2 Valve Name: TD AFP TO SIG C HV ALHVW030 M-22AL01 F-3 3 B 6.0 BF MO Active C 0 BTO M3 PIT Y2 Valve Name: ESW TO MD AFP B HV ALHV0031 M-22AL01 E-3 3 B 6.0 BF MO Active C 0 BTO M3 PIT Y2 Valve Name: ESW TO MD AFP A HV ALHVO032 M-22AL01 C-3 3 B 8.0 BF MO Active C 0 BTO M3 PIT Y2 Valve Name: ESW TO TD AFP HV ALHV0033 M-22AL01 B-3 3 B 8.0 BF MO Active C 0 BTO M3 PIT Y2 Valve Name: ESW TO TD AFP HV ALHV0034 M-22AL01 H-3 3 B 8.0 GT MO Active 0 C BTC M3 PIT Y2 Valve Name: CST TO MD AFP B HV AL :V0035 M-22AL01 D-3 3 B 8.0 GT MO Active 0 C BTC M3 PIT Y2 Valve Name: CST TO MD AFP A HV ALHV0036 M-22ALO1 B-3 3 B 10.0 GT MO Active 0 C BTC M3 TP-02 PIT Y2 Valve Name: CST TO TD AFP HV Revision Date: 1211912005 Page 114

Callaway IST Program Plan Auxiliary Feedwater (AL) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&D Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

ALV0001 M-22AL01 B4 3 C 10.0 CK SA A SYS O/C CC M3 Co M3 Valve Name: CST TO TD AFP CHECK VLV ALVD006 M-22AL01 F4 3 C 6.0 CK SA Acfive SYS 0 CC M3 TP-01 Co M3 Valve Name: ESW TO MD AFP B CHK VLV ALV0009 M-22AL01 E4 3 C 6.0 CK SA Active SYS 0 CC M3 TP-01 CO M3 Valve Name: ESW TO MD AFP A CHK VLV ALVO012 M-22AL01 C4 3 C 8.0 CK SA Acive SYS O/C CC M3 CO M3 Valve Name: ESW TO TD AFP CHK VLV ALVO015 M-22AL01 BA 3 C 8.0 CK SA Active SYS O/C CC M3 CO M3 Valve Name: ESW TO TD AFP CHK VLV ALVO033 M-22AL01 F-7 2 C 4.0 CK SA Active SYS O/C CCF CM TP-08 COF CM TP-08 Valve Name: MDAFP B TO SIG A CHECK VLV ALWV036 M-22AL01 H-7 2 C 4.0 CK SA Acfive SYS OIC CCF CM TP408 COF CM TP-08 Valve Name: MDAFP B TOSIG D CHECK VLV ALVO045 M-22AL01 C-7 2 C 4.0 CK SA Active SYS O/C CCF CM TP48 COF CM TP-08 Valve Name: MDAFP A TO SIG C CHECK VLV

-.1048 M-22AL01 D-7 2 C 4.0 CK SA Active SYS O/C CCF CM TP-08 COF CM TP-48 Valve Name: MDAFP A TO SIG B CHECK VLV ALVO054 M-22AL01 B-5 2 C 6.0 CK SA Actve SYS O/C CC CS CSJ-05 CO CS CSJ-05 Valve Name: TD AFP DISCH CHECK VLV Revision Date: 12119/2005 Page 115

Callaway

[ST Program Plan Auxiliary Feedwater (AL) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&8D Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

ALVO057 M-22AL01 E-7 2 C 4.0 CK SA Active SYS OIC CCF CM TP-08 COF CM TP-08 Valve Name: TDAFP TO SIG A CHECK VLV ALVO062 M-22AL01 G-7 2 C 4.0 CK SA Active SYS O/C CCF CM TP-08 COF CM TP-08 Valve Name: TDAFP TO SIG D CHECK VLV ALV0067 M-22AL01 D-7 2 C 4.0 CK SA Active SYS O/C CCF CM TP-08 COF CM TP-08 Valve Name: TDAFP TO S/G B CHECK VLV ALVOW72 M-22AL01 B-7 2 C 4.0 CK SA Active SYS 0/C CCF CM TP-08 COF CM TP-08 Valve Name: TDAFP TO S/G C CHECK VLV ALVOI48 M-22AL01 G-6 NC C CK SA Active SYS 0 CC M3 TP-01 CO M3 Valve Name: N2 SPLY CHECK VLV TO ALHV0006 ALVO149 M-22AL01 G-6 NC C CK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: AIR SPLY CHECK VLV TO ALHV0006 ALVOI50 M-22AL01 F4- NC C CK SA Active SYS 0 CC M3 TP-01 CO M3 Valve Name: N2 SPLY CHECK VLV TO ALHV0008 ALVOI51 M-22AL01 F-4 NC C eK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: AIR SPLY CHECK VLV TO ALHV0008 Al V0152 M-22AL01 D-6 NC C CK SA Active SYS 0 CC M3 TP-01 Co M3 Valve Name: N2 SPLY CHECK VLV TO ALHV0010 ALV0153 M-22AL01 D4- NC C CK SA Active SYS C CC W CO M3 TP-01 Valve Name: AIR SPLY CHECK VLV TO ALHV0010 Revision Date: 12119/2005 Page 116

Callaway IST Program Plan Auxiliary Feedwater (AL) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

ALVO154 M-22AL01 B-6 NC C CK SA Active SYS 0 CC M3 TP-01 CO W3 Valve Name: N2 SPLY CHECK VLV TO ALHV0O12 ALVOI55 M-22AL01 B-6 NC C CK SoA Active SYS C CC M3 CO M3 TP-01 Valve Name: AIR SPLY CHECK VLV TO ALHV0012 Page 117 Date:

Revision Date: 12/1912005 12/19/205 Page il7

• Callaway IST Program Plan Reactor Coolant (BB) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Loccation P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BB8O10A M-22BB02 G-7 1 C 6.0 RV SA Active C O/C RT Y5 Valve Name: RCS PZR SF1Y RLF A 8B8010B M-22BB02 G-6 I C 6.0 RV SA Active C O/C RT Y5 Valve Name: RCS PZR SFTY RLF B BB8010C M-22BB02 G-5 I C 6.0 RV SA Active C O/C RT Y5 Valve Name: RCS PZR SFTY RLF C BB8378A M-22BB01 E4 1 C 3.0 CK SA Active SYS C CC RR RJ-02 CO RR RJ42 TP401 Valve Name: RCS LOOP 1 COLD LEG CVCS REGEN HX CHG LINE DNSTRM CHECK BB8378B M-22BB01 E4 1 C 3.0 CK SA Active SYS C CC RR RJ-02 CO RR RJ-02 TP-01 Valve Name: RCS LOOP I COLD LEG CVCS REGEN HX CHG LINE UPSTRM CHECK BB8379A M-22BB01 E-7 1 C 3.0 CK SA Active SYS C CC RR RJ-02 CO RR RJ-02 TP.01 Valve Name: RCS LOOP 4 COLD LEG CVCS REGEN HX CHG LINE DNSTRM CHECK BB8379B M-22BB01 E-7 1 C 3.0 CK SA Active SYS C CC RR RJ-02 CO RR RJ402 TP401 Valve Name: RCS LOOP 4 COLD LEG CVCS REGEN HX CHG LINE UPSTRM CHECK BB8948A M-22BB01 E-4 1 AC 10.0 CK SA Actve SYS 01C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: RCS LOOP I COLD LEG Si ACC CHECK BB8948B M-22BB01 D-4 1 AC 10.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP408 COF CM TP-08 Valve Name: RCS LOOP 2 COLD LEG Si ACC CHECK BB8948C M-22BB01 D-6 1 AC 10.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-8 Valve Name: RCS LOOP 3 COLD LEG SI ACC CHECK Revision Date: 12/19/2005 Page 118

Callaway Reactor Coolant(BB) IST Program Plan Reactr Colant(BB)Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BB8948D M-22BB01 E-6 1 AC 10.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: RCS LOOP 4 COLD LEG SI ACC CHECK BB8949B M-22BB01 C-5 1 AC 6.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COA CM TP-08 Valve Name: RCS LOOP 2 HOT LEG SI/RHR PMPS CHECK BB8949C M-22B801 C-6 1 AC 6.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COA CM TP-08 Valve Name: RCS LOOP 3 HOT LEG SIIRHR PMPS CHECK BB8949D M-22B801 G-6 1 AC 6.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: RCS LOOP 4 HOT LEG SI PMPS CHECK BB8949E M-22BB01 E-5 I AC 2.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: RCS LOOP 1 HOT LEG SI PMPS CHECK BBHV0013 M-22BB03A C-2 3 B 3.0 GT MO Active 0 C BTC RR RJ-03 PIT Y2 Valve Name: RCP A THRM BAR COOL COIL COOL WTR OUT HV 9BHV0014 M-22BB03B C-2 3 B 3.0 GT MO Active 0 C BTC RR RJ-03 PIT Y2 Valve Name: RCP B THRM BAR COOL COIL COOL WTR OUT HV

-1J0015 M-22BB03C C-2 3 B 3.0 GT MO Active 0 C BTC RR RJ-03 PIT Y2 Valve Name: RCP C THRM BAR COOL COIL COOL WTR OUT HV BBHVW016 M22BB03D C-2 3 B 3.0 GT MO Active 0 C BTC RR RJ-03 PIT Y2 Valve Name: RCP D THRM BAR COOL COIL COOL WTR OUT HV Revision Date: 12/19/2005 Page 119

Callaway IST Program Plan Reactor Coolant (BB) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BBHV8000A M-22BB02 E-7 1 B 3.0 GT MO Active 0 O/C BTC M3 RJ-04 BTO M3 RJ-04 PIT Y2 Valve Name: RCS PZR OUT PWR OPER RLF HV BBHV8000B M-22BB02 E-7 1 B 3.0 GT MO Active O O/C BTC M3 RJ-04 BTO M3 RJ-04 PIT Y2 Valve Name: RCS PZR OUT PWR OPER RLF HV BBHV8001A M-22BB04 F4 2 B 1.0 GB SO Active C O/C BTC CS CSJ-06 BTO CS CSJ-06 FC CS CSJ-06 TP-04 PIT Y2 Valve Name: RCS RV HEAD VENT PROT A UPSTRM HV BBHO0018 M-22BB04 E-4 2 B 1.0 GB SO Active C O/C BTC CS CSJ.06 BTO CS CSJ-06 FC CS CSJ-06 TP-04 PIT Y2 Valve Name: RCS RV HEAD VENT PROT B UPSTRM HV BRHV8002A M-22BB04 F-3 2 B 1.0 GB SO Active C O/C BTC CS CSJ-06 BTO CS CSJ-06 FC CS CSJ-06 TP-04 PIT Y2 Valve Name: RCS RV HEAD VENT PROT A UPSTRM HV BBHV8002B M-22BB04 E-3 2 B 1.0 GB SO Active C O/C BTC CS CSJ-06 BTO CS CSJ-06 FC CS CSJ-06 TP-04 PIT Y2 Valve Name: RCS RV HEAD VENT PROT B UPSTRM HV BBHV8026 M-22BB02 E-3 2 A 1.0 Dl AO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RCS PRT N2/SERV GAS SPLY DNSTRM ISO HV Revision Date: 12/19/2005 Page 120

Callaway

[ST Program Plan Reactor Coolant (BB) Valve Table

• P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

BBHV8027 M-22BB02 E-3 2 A 1.0 Dl AO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RCS PRT N2/SERV GAS SPLY UPSTRM ISO HV BBHV8157A M-22BB02 E-1 2 B 1.0 GB SO Active C 0 BTO M3 PIT Y2 Valve Name: PRT TO EX LTDN HX PROT A ISO HV BBHV8157B M-22BB02 D-1 2 B 1.0 GB SO Adcive C 0 BTO M3 PIT Y2 Valve Name: PRT TO EX LTDN HX PROT B ISO HV BBHV8351A M-22BB03A C-5 2 A 2.0 GB MO Active 0 O/C AT4-1 AppJ BTC RR RJ-05 BTO RR RJ-05 PIT Y2 Valve Name: RCP A SEAL WTR SPLY ISO HV BBHV8351B M-22BB03B C-5 2 A 2.0 GB MO Active 0 0/C AT-01 App-J BTC RR RJ-05 BTO RR RJ-05 PIT Y2 Valve Name: RCP B SEAL WTR SPLY ISO HV BBHV8351C M-22BB03C C-5 2 A 2.0 GB MO Acfive 0 . O/C AT-01 AppJ BTC RR RJ-05 BTO RR RJ-05 PIT Y2 Valve Name: RCP C SEAL WTR SPLY ISO HV BBHV8351D M-22BB03D C-5 2 A 2.0 GB MO Active 0 0/C AT-01 App-J BTC RR RJ-05 BTO RR RJ-05 PIT Y2 Valve Name: RCP D SEAL WTR SPLY ISO HV Revision Date: 12/19/2005 Page 121

Callaway IST Program Plan Reactor Coolant (BB) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BBPCV0455A M-22BB02 E-7 1 B 3.0 GB SO Active C Ole STC CS CSJ-07 BTO CS CSJ-07 FC CS CSJ-07 TP-04 PIT Y2 Valve Name: RCS PRESSURIZER POWER OPERATED RELIEF VALVE BBPCVW456A M-22BB02 E-8 1 B 3.0 GB SO Active C 01C BTC CS CSJ-07 BTO CS CSJ-07 FC CS CSJ-07 TP-04 PIT Y2 Valve Name: RCS PRESSURIZER POWER OPERATED RELIEF VALVE BBPV8702A M-22BB01 E-4 1 A 12.0 GT MO Passive C O/C AT-02 Y2 BTC CS CSJ-08 BTO CS CSJ-08 PIT Y2 Valve Name: RCS LOOP I HOT LEG TO RHR PMPS PCV ISO BBPV8702B M-22BB01 H-6 1 A 12.0 GT MO Passive C O/C AT-02 Y2 BTC CS CSJ-08 BTO CS CSJ-08 PIT Y2 Valve Name: RCS LOOP 4 HOT LEG TO RHR PMPS PCV ISO BBV0001 M-22BB01 D-5 1 AC 1.5 CK SA Active SYS 0/C AT-02 Y2 CCL CM TP-08 COA CM TP-08 COF CM TP-08 Valve Name: RCS LOOP I COLD LEG St BIT CHECK BBV0022 M-22BB01 D4 1 AC 1.5 CK SA Active SYS 01C AT-02 Y2 CCL CM TP-08 COA CM TP-08 COF CM TP-08 Valve Name: RCS LOOP 2 COLD LEG SI BIT CHECK Revision Date: 12119/2005 Page 122

Callaway IST Program Plan Reactor Coolant (BB) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief

• Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

BBV0040 M-228B01 D-6 1 AC 1.5 CK SA Active SYS 0/C AT-02 Y2 CCL CM TP-08 COA CM TP-08 COF CM TP-08 Valve Name: RCS LOOP 3 COLD LEG SI BIT CHECK BBV0059 M-221B01 E-6 1 AC 1.5 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COA CM TP-08 COF CM TP-08 Valve Name: RCS LOOP 4 COLD LEG SI BIT CHECK BBV0118 M-22BB03A C-5 2 AC 2.0 CK SA Active SYS O/C AT-01 Appo CCL CM TP-08 COF CM TP-08 Valve Name: RCP A SEAL WTR SPLY ISO BBV0119 UPSTRM CHECK BBV0120 M-22BB03A C4 1 C 2.0 CK SA Active SYS O/C CCA CM TP-08 COF CM TP-08 Valve Name: RCP A SEAL WTR SPLY ISO BBV01 19 DNSTRM CHECK BBV0121 M-22BB03A C4 1 C 2.0 CK SA Acfive SYS O/C CCA CM TP-08 COF CM TP-08 Valve Name: RCP A SEAL WTR SPLY CHECK BBV0122 M-22BB03A C4 3 C 1.5 CK SA Active SYS C CC RR RJ-06 Co OP TP-01 Valve Name: CCW TO RCP A THERMAL BARRIER SPLY CK VLV PBV0148 M-22BB03B C-5 2 AC 2.0 CK SA Active SYS 0/C AT-01 App-J CCL CM TP-48 COF CM TP-08 Valve Name: RCP B SEAL WTR SPLY ISO BBV0149 UPSTRM CHECK BBV0150 M-22BB03B C4 1 C 2.0 CK SA Active SYS O/C CCA CM TP-08 COF CM TP-08 Valve Name: RCP B SEAL WTR SPLY ISO B13V0149 DNSTRM CHECK BBV0151 M-22B803B C4 1 C 2.0 CK SA Active SYS O/C CCA CM TP-08 COF CM TP-08 Valve Name: RCP B SEAL WTR SPLY CHECK Revision Date: 12/19/2005 Page 123

Callaway IST Program Plan Reactor Coolant (BB) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Loci ation P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BBV0152 M-22BB03B C4 3 C 1.5 CK SA Active SYS C CC RR RJ-06 CO OP TP-01 Valve Name: CCW TO RCP B THERMAL BARRIER SPLY CK VLV 88V0178 M-22BB03C C-5 2 AC 2.0 CK SA Active SYS 01C AT-01 App-J CCL CM TP-08 COF CM TP-08 Valve Name: RCP C SEAL WTR SPLY ISO 3BV0179 UPSTRM CHECK BBV018O M-22BB03C CA 1 C 2.0 CK SA Active SYS 01C CCA CM TP-08 COF CM TP-08 Valve Name: RCP C SEAL WTR SPLY ISO BBV0179 DNSTRM CHECK BBVO181 M-22BB03C CA 1 C 2.0 CK SA Acive SYS 0/C CCA CM TP-08 COF CM TP-08 Valve Name: RCP C SEAL WTR SPLY CHECK 8PVC182 M-22BB03C CA 3 C 1.5 CK SA Active SYS C CC RR RJ-06 CO OP TP-01 Valve Name: CCW TO RCP C THERMAL BARRIER SPLY CK VLV BBV0208 M-22BB03D C-5 2 AC 2.0 CK SA Active SYS O/C AT-01 App-i CCL CM TP-08 COF CM TP-08 Valve Name: RCP D SEAL WTR SPLY SO BEBV0209 UPSTRM CHECK BBVO210 M-22B03D CA4 1 C 2.0 CK SA Active SYS O/C CCA CM TP-08 COF CM TP-08 Valve Name: RCP D SEAL WTR SPLY ISO BBV0209 DNSTRM CHECK BBV0211 M-22BB03D C4 1 C 2.0 CK SA Active SYS O/C CCA CM TP-08 COF CM TP-08 Valve Name: RCP D SEAL WTR SPLY CHECK BOV0212 M-22BB03D CA 3 C 1.5 CK SA Active SYS C CC RR RJ-06 CO OP TP-01 Valve Name: CCW TO RCP D THERMAL BARRIER SPLY CK VLV BBV0474 M-22BB03A C-5 3 C 1.5 CK SA Active SYS C CC RR RJ-06 CO OP TP-01 Valve Name: CCW TO RCP A THERMAL BARRIER SPLY CK VLV Revision Date: 12/19/2005 Page 124

Callaway IST Program Plan Reactor Coolant (B8) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BBV0476 M-22B8036 C-5 3 C 1.5 CK SA Active SYS C CC RR RJ-06 CO OP TP-41 Valve Name: CCW TO RCP B THERMAL BARRIER SPLY CK VLV BBV0479 M-22BB03C C-5 3 C 1.5 CK SA Active SYS C CC RR RJ-06 CO OP TP-01 Valve Name: CCW TO RCP C THERMAL BARRIER SPLY CK VLV BBVO480 M-22BB03D C-5 3 C 1.5 CK SA Active SYS C CC RR RJ-06 CO OP TP-01 Valve Name: CCW TO RCP D THERMAL BARRIER SPLY CK VLV Date: 1211912005 Page 125 Revision Date:

Revision 12119/2005 Page 125

Callaway IST Program Plan Chemical and Volume Control (BG) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BG8121 M-228G01 D-3 2 C 2.0 RV SA Active C O/C RT YIO Valve Name: SEAL WTR RTN HDR PRESS RELIEF BG8123 M-22BG03 H-3 2 C 2.0 RV SA Active C O/C RT Y10 Valve Name: CVCS SEAL WTR HX IN HDR PRESS RELIEF BG8124 M-22BG03 C-7 2 C 0.75 RV SA Active C 0 RT Y10 Valve Name: CCP A & B SUCTION PRESS RELIEF BG8381 M-22BG01 F4 2 AC 3.0 CK SA Active SYS C AT-01 App-J CCL CM TP-08 COF CM TP-08 Valve Name: CCP A & B TO REGEN HX CHECK BG8440 M-22BG03 E-6 2 C 4.0 CK SA Active SYS O/C CC RR RJ-07 CO OP TP-09 Valve Name: VCT TO NCPICCP HDR CHECK BG8481A M-22BG03 C4 2 C 4.0 CK SA Active SYS O/C CC RR RJ-08 CO RR RJ-08 Valve Name: CVCS CCP A DISCH CHECK BG8481B M-22BG03 B4 2 C 4.0 CK SA Active SYS O/C CC RR RJ-08 CO RR RJ-08 Valve Name: CVCS CCP B DISCH CHECK BG8497 M-22BG03 E-4 2 C 3.0 . CK SA Active SYS C CC M3 CO OP TP401 Valve Name: CVCS NCP DISCH CHECK BG8546A M-22BG03 C-7 2 C 8.0 CK SA Active SYS 0/C CC RR RJ-09 CO RR RJ-09 Valve Name: RWST TO CCP A SUCT CHECK BG8546B M-22BG03 B-7 2 C 8.0 CK SA Active SYS O/C CC RR RJ-09 CO RR RJ-09 Valve Name: RWST TO CCP B SUCT CHECK Revision Date: 12119/2005 Page 126

Callaway IST Program Plan Chemical and Volume Control (BG) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

BGHV8100 M-22BG01 D-2 2 A 2.0 GB MO Active 0 C AT-01 Appo BTC RR RJ-10 PIT Y2 Valve Name: SEAL WTR RTN OUTER CTMT ISO BGHV8104 M-22BG05 A4 2 B 2.0 GB MO Active C 0 BTO M3 PIT M3 Valve Name: EMERG BORATE TO CCP A & B HDR ISO HV BGHV8105 M-22BG03 E-2 2 A 3.0 GT MO Active 0 C AT-Ot Appo BTC CS CSJ-09 PIT Y2 Valve Name: CVCS CHARGING HDR TO REGEN HX OUTER CTMT ISO VLV BGHV8106 M-22BG03 E-2 2 B 3 GT MO Active 0 C BTC CS CSJ-09 PIT Y2 Valve Name: CVCS CHARGING HDR TO REGEN HX OUTER CTMT ISO VLV BGHV8110 M-22BG03 E-3 2 B 2.0 GB MO Active 0 O/C BTC M3 BTO M3 PIT Y2 Valve Name: A CCP DISCH MINIFLOW TO SEAL WTR HX ISO BGHV8111 M-22BG03 E4 2 B 2.0 GB MO Active 0 O/C BTC M3 BTO M3 PIT Y2 Valve Name: CCP B DISCH MINIFLOW ISO VLV BGHV8112 M-22BG01 D-2 .2 A 2.0 GB MO Active 0 C AT-01 App-J BTC RR RJ-10 PIT Y2 Valve Name: SEAL WTR RTN INNER CTMT ISO HV BGHV8152 M-22BG01 F-2 2 A 3.0 GB AO Active 0 C AT-01 App-J BTC CS CSJ-10 FC CS CSJ-10 TP-04 PIT Y2 Valve Name: CVCS LTDN SYS OUT CTMT ISO HV Revision Date: 112/19/2005 Page 127

Callaway IST Program Plan Chemical and Volume Control (BG) Valve Table P&ID Safety Valve Act. Active I Nonmal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BGHV8153A M-22BG01 D-7 1 B 1.0 GB SO Acfive C 0/C BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: RCS TO CVCS EX LTDN HX DNSTRM ISO PROT A HV BGHV8153B M-22BG01 D-7 1 8 1.0 GB SO Active C O/C BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: RCS TO CVCS EX LTDN HX DNSTRM ISO PROT B HV BGHV8154A M-22BG01 D-8 1 B 1.0 GB SO Active C OIC BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: RCS TO CVCS EX LTDN HX UPSTRM ISO PROt A HV BGHV8154B M-22BG01 D-8 1 B 1.0 GB SO Acfive C O/C BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: RCS TO CVCS EX LTDN HX UPSTRM ISO PROT B HV I

BGHV8160 M-22BG01 F-3 2 A 3.0 GB AO Active 0 C AT-01 App-J sTC Cs Csi-10 FC CS CSJ-10 TP-04 PIT Y2 Valve Name: CVCS LTDN SYS INNER CTMT ISO HV BGHV8357A M-22BG03 CA 2 B 1.0 GB MO Acfive C 0/C BTC M3 BTO M3 PIT Y2 Valve Name: CVCS CCP A DISCH TO RCP SEALS THROTTLE VLV BGHV8357B M-22BG03 BA 2 B 1.0 GB MO Acfive C OIC BTC M3 BTO M3 PIT Y2 Valve Name: CVCS CCP B DISCH TO RCP SEALS THROTTLE VLV Revision Date: 12/19/2005 Page 128

Callaway IST Program Plan Chemical and Volume Control (BG) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred .Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BGLCV01i2B M-22E3G03 F-6 2 B 4.0 GT MO Active 0 C BTC CS CSJ-11 PIT Y2 Valve Name: CVCS VCT OUT UPSTRM ISO BGLCV0112C M-22BG03 F-4 2 B 4.0 GT MO Acfive 0 C BTC CS CSJ-11 PIT Y2 Valve Name: CVCS VCT OUT DNSTRM. ISO BGLCV0459 M-22BG01 G-7 I 8 3.0 GB AO Active 0 C BTC CS CSJ-12 FC CS CSJ-12 TP-04 PIT Y2 Valve Name: RCS LOOP 3 LTDN TO REGEN HIX DNSTRM LCV BGLCV0460 M-22BG01 G-7 1 B 3.0 GB AO Active 0 C BTC CS CSJ-12 FC CS CSJ-12 TP-04 PIT Y2 Valve Name: RCS LOOP 3 LTDN TO REGEN HX UPSTRM LCV BGVW091 M-22BG03 E4 2 C 2.0 CK SA Active SYS 0 CC M3 TP-01 CO M3 Valve Name: CCP A DISCH TO SEAL WTR HX CHECK BGV0095 M-22BG03 E4 2 C 2.0 CK SA Active SYS 0 CC M3 TP-01 CO M3 Valve Name: CCP B DISCH TO SEAL WTR HX CHECK BGV0135 M-22BG01 D-3 2 AC 0.75 CK SA Aclive SYS O/C AT-01 App-J CCL CM TP-08 COF CM TP-08 Valve Name: SEAL WTR RTN INNER CTMT BGHV8112 DRN CHECK BGV0147 M-22BG05 B-6 3 C 3.0 CK SA Active SYS O/C CC OP CO CS CSJ-13 Valve Name: CVCS BA XFR PMP A DISCH CHECK BGV0155 M-22BG05 B-4 3 C 0.75 CK SA Acbive SYS 0 CCF CM TP-08 COF CM TP408 Valve Name: CVCS BA XFR PMP A DISCH TO BAT A CHECK Revision Date: 12V19/2005 Page 129

Callaway IST Program Plan Chemical and Volume Control (BG) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BGV0165 M-22BG05 A-6 3 C 3.0 CK SA Active SYS 0OC CC OP CO CS CSJ-13 Valve Name: CVCS BA XFR PMP B DISCH CHECK BGV0167 M-22BG05 B-6 3 C 0.75 CK SA Active SYS 0 CCF CM TP-08 COF CM TP-08 Valve Name: CVCS BA XFR PMP B DISCH TO BAT B CHECK BGV0174 M-22BG05 A4 2 C 3.0 CK SA Active SYS O/C CC CS CSJ-13 CO CS CSJ-13 Valve Name: CVCS EMERG BORATE TO CCP A & B HDR CHECK BGV0589 M-22BG03 B4 2 C 1.0 CK SA Active SYS O/C CC M3 CO M3 Valve Name: CCP B DISCH TO SEAL WTR IN FLTRS HDR CHECK BGV0590 M-22BG03 C4 2 C 1.0 CK SA Active SYS O/C CC M3 Co M3 Valve Name: CCP A DISCH TO SEAL WTR INJ FLTRS HDR CHECK BGV0605 M-22BG03 C-3 2 C 3.0 CK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: CCP B DISCH BGFCV0121 UPSTREAM CHECK BGV0606 M-22BG03 D-3 2 C 3.0 CK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: CCP A DISCH BGFCV0121 UPSTREAM CHECK BGV0645 M-22BG03 D4 2 C 3.0 CK SA Active SYS C CC M3 CO OP TP-01 Valve Name: CVCS NCP DISCH UPSTRM CHECK Revision Date: 12/19/2005 Page 130

Callaway IST Program Plan Reactor Makeup Water (BL) Valve Table P&ID Safety Valve Act Active / Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BL8046 M22BL01 B-3 2 AC 3.0 CK SA Active SYS C AT-01 Appo CCL CM TP-08 COF CM TP-08 Valve Name: RX M/U WTR SPLY INNER CTMT CHECK BLHV8047 M-22BL01 B4 2 A 3.0 Dl AO Active SYS C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RX MIU WTR OUTER CTMT HV ISO Page 11 Revision Date:

Date: 1211912005 12/1912005 Page 131

Callaway IST Program Plan Steam Generator Blowdown (BM) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

BMHV0001 M-22BM01 F-5 2 B 4.0 GB AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG A BID ISO VLV BMHV0002 M-22BM01 E-5 2 B 4.0 GB AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG B BID ISO VLV BMHV0003 M-22BM01 C-5 2 B 4.0 GB AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG C BID ISO VLV BMHV0004 M-22BM01 A-5 2 B 4.0 GB AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG D BID ISO VLV BMHV0019 M-22BM01 G-7 2 B 1.0 GB SO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG A BID NUC SAMP SYS UP LINE ISO CTRL VLV BMHV0020 M-22BM01 E-7 2 B 1.0 GB SO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG B BID NUC SAMP SYS UP LINE ISO CTRL VLV BMHV0021 M-22BM01 D-7 2 B 1.0 GB SO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG C BID NUC SAMP SYS UP LINE ISO CTRL VLV BMHVO022 M-22BM0 1 B-7 2 B 1.0 GB SO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG D BID NUC SAMP SYS UP LINE ISO CTRL VLV Revision Date: 12119/2005 Page 132

Callaway IST Program Plan Steam Generator Blowdown (BM) Valve Table P&ID Safety Valve Act. Active i Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BMHV0035 M-22BM01 G-7 2 B 1.0 GB SO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG A BID NUC SAMP SYS LWR LINE ISO CTRL VLV BMHV0036 M-228M01 E-7 2 8 1.0 GB SO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG B BID NUC SAMP SYS LWR LINE ISO CTRL VLV BMHV0037 Ik22BM01 C-7 2 B 1.0 GB SO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG C BID NUC SAMP SYS LWR LINE ISO CTRL VLV BMHV0038 M-22BM01 B-7 2 B 1.0 GB SO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG D BID NUC SAMP SYS LWR LINE ISO CTRL VLV BMHV0065 M-22BM01 G-6 2 B 1.0 GB SO Active 0 C BTC M FC M3 TP-04 PIT Y2 Valve Name: SG A BID NUC SAMP SYS LINE ISO UPSTRM HV BMHV0066 M-22BM01 E-6 2 B 1.0 GB SO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG B BID NUC SAMP SYS LINE ISO UPSTRM HV BMHV0067 M-22BM01 C4 2 B 1.0 GB SO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG C BID NUC SAMP SYS LINE ISO UPSTRM HV BMHV0068 M-22BM01 B4 2 B 1.0 GB SO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SG D BID NUC SAMP SYS LINE ISO UPSTRM HV Revision Date: 12/1912005 Page 133

Callaway IST Program Plan Steam Generator Blowdown (BM) Valve Table P&ID Safety Valve Act Active I Normal Safety

• Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

BMV0045 M-22BM01 A4 2 A 3.0 GT MA Passive LC C AT-01 App-J Valve Name: SG DRN PMPS SUCT HDR INNER CTMT ISO BMV0046 M-22BM01 A-3 2 A 3.0 GT MA Passive LC C AT-01 App-J Valve Name: SG DRN PMPS SUCT HDR OUTER CTMT ISO Page 134 Revislon Date:

Revision Date: 12119/2005 12/19/2005 Page 134

Callaway IST Program Plan Borated Refueling Water Storage (BN) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

BN8717 W22BN01 B-5 2 A 8.0 GT MA Passive LC C AT-03 Y2 PIT Y2 Valve Name: RHR SPLY TO RWST ISO (3.0.3)

BNHCV8800A M-22BN01 E-5 2 B 3.0 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RWST TO RFP DNSTRM HV BNHCV8800B M-22BN01 E-5 2 B 3.0 GB AO Actve C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RWST TO RFP UPSTRM HV BNHV0003 M-22BN01 C-3 2 B 12.0 GT MO Active 0 OIC BTC M3 TP-02 PIT Y2 Valve Name: RWST TO CTMT SPRY PMP B HV BNHV0004 M-22BN01 A-3 2 B 12.0 GT MO Active 0 O/C BTC M3 TP-02 PIT Y2 Valve Name: RWST TO CTMT SPRY PMP A HV BNHV8806A M-22BN01 B-5 2 B 8.0 GT MO Active 0 O/C BTC M3 TP-02 PIT Y2 Valve Name: Si PMP A SUCT FROM RWST ISO BNHV8806B M-22BN01 E-3 2 B 8.0 GT MO Acfive 0 O/C BTC M3 TP-02 PIT Y2 Valve Name: Si PMP B SUCT FROM RWST ISO BNHV8812A M-22BN01 B-3 2 B 14.0 GT MO Active 0 O/C BTC M3 TP-02 PIT Y2 Valve Name: RWST TO RHR PMP A SUCT ISO VLV BNHV8812B M-22BN01 D-3 2 B 14.0 GT MO Acfive 0 O/C BTC M3 TP-02 PIT Y2 Valve Name: RWST TO RHR PMP B SUCT ISO VLV Revision Date: 12/19/2005 Page 135

Callaway Borated Refueling Water Storage (BN) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

BNHV8813 M-22BN01 8-7 2 A 2.0 GB MO Active 0 C AT-03 Y2 BTC CS CSJ-14 PIT Y2 Valve Name: Si PMPS MINIFLOW TO RWST ISO VLV (3.0.3)

BNLCV0112D M-22BN01 A-5 2 B 8.0 GT MO Active C O/C BTC M3 BTO M3 PIT Y2 Valve Name: CCP A SUCT FROM RWST ISO VLV BNLCV0112E M-22BN01 E-3 2 8 8.0 GT MO Active C O/C BTC M3 BTO M3 PIT Y2 Valve Name: CCP B SUCT FROM RWST ISO VLV BNV0011 M-22BN01 F4 2 B 24.0 GT MA Passive LO 0 PIT Y2 Valve Name: RWST OUT ISO (3.0.3)

Revision Date: 12119/2005 Page 136

Callaway IST Program Plan Fuel Pool Cooling and Cleanup (EC) Valve Table P&UD Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

ECHV0011 M-22EC01 H-5 3 B 12 BF MO Active 0 C BTC M3 PIT Y2 Valve Name: FUEL POOL HX A SHELL SIDE CCW OUT ISO ECHV0012 M-22EC01 F-5 3 B 12 BF MO Active 0 C BTC M3 PIT Y2 Valve Name: FUEL POOL HX B SHELL SIDE CCW OUT ISO ECV0083 M-22EC02 C-5 2 A 6 GT MA Passive LC C AT-01 App-J Valve Name: FUEL POOL CLN-UP DEMIN TO REFUEL POOL OUTER CTMT ISO ECV0084 M-22EC02 C-6 2 A 6 GT MA Passive LC C AT-01 App-J Valve Name: FUEL POOL CLNIU DEMIN TO RFP INNER CTMT ISO ECV0087 M-22EC02 D-7 2 A 6 GT MA Passive IC C AT-01 AppJ Valve Name: RFP TO SFP INNER CTMT ISO ECV0088 M-22EC02 D-7 2 A 6 GT MA Passive LC C AT-01 App-J Valve Name: REFUEL POOL TO SFP OUTER CTMT ISO ECV0095 M-22EC02 B-5 2 A 3 GT MA Passive LC C AT-I1 App-J Valve Name: FUEL POOL SKIMMER PUMP SUICT INNER CTMT ISO ECVW096 M-22EC02 B-5 2 A 3 GT MA Passive LC C AT-I1 App-J Valve Name: REFUEL POOL SKIMMER PMP SUCT OUTER CTMT ISO Revision Date: 12/19/2005 Page 137

Callaway IST Program Plan Essential Service Water (EF) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location PKID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EFHV0023 M-22EF01 F-7 3 B 30.0 BF MO Active 0 C BTC M3 PIT Y2 Valve Name: SERV WTR TO ESW TRN A UPSTRM HV EFHV0024 M-22EF01 E-7 3 B 30.0 BF MO Active 0 C BTC M3 PIT Y2 Valve Name: SERV WTR TO ESW TRN B UPSTRM HV EFHV0025 M-22EF01 F-7 3 B 30.0 BF MO Active 0 C BTC M3 PIT Y2 Valve Name: SERV WTR TO ESW TRN A DNSTRM HV EFHVW026 M-22EF01 E-7 3 B 30.0 BF MO Active 0 C BTC M3 PIT Y2 Valve Name: SERV WTR TO ESW TRN B DNSTRM HV EFHVD031 M-22EF02 G-7 2 A 14.0 BF MO Active 0 O/C AT-01 AppoJ BTC M3 BTO M3 PIT Y2 Valve Name: ESW TRN A TO CTMT AIR CLRS OUTER CTMT NV EFHV0032 M-22EF02 B-7 2 A 14.0 BF MO Active 0 0/C AT-01 App-J BTC M3 8TO M3 PIT Y2 Valve Name: ESW TRN B TO CTMT AIR CLRS OUTER CTMT HV EFHV0033 M-22EF02 G-7 2 A 14.0 BF MO Active 0 O/C AT-01 App-J BTC M3 8TO M3 PIT Y2 Valve Name: ESW TRN A TO CTMT AIR CLRS INNER CTMT NV EFHV0034 M-22EF02 8-7 2 A 14.0 BF MO Active 0 O/C AT-01 AppJ BTC M3 BTO M3 PIT Y2 Valve Name: ESW TRN B TO CTMT AIR CLIRS INNER CTMT HV Revision Date: 12/19/2005 Page 138

Callaway IST Program Plan Essential Service Water (EF) Valve Table PKID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

EFNV0037 M-22EF02 G-2 3 B 30.0 BF MO Active C 0 BTO M3 PIT Y2 Valve Name: ESW TRN A TO UHS HV EFHVW038 M-22EF02 C-2 3 B 30.0 BF MO Active C 0 BTO M3 PIT Y2 Valve Name: ESW TRN B TO UHS HV EFHV0039 W22EF02 F-2 3 B 30.0 BF MO Active 0 C BTC M3 PIT Y2 Valve Name: ESW TRN A TO SERV WTR UPSTRM HV EFHV0040 M-22EF02 0-2 3 B 30.0 BF MO Acbve 0 C BTC M3 PIT Y2 Valve Name: ESW TRN B TO SERV WTR UPSTRM HV EFHV0041 M-22EF02 E-2 3 B 30.0 BF MO Active 0 C BTC M3 PIT Y2 Valve Name: ESW TRN A TO SERV WTR DNSTRM HV EFHVOO42 M-22EF02 0-2 3 B 30.0 BF MO Achve 0 C BTC M3 PIT Y2 Valve Name: ESW TRN B TO SERV WTR DNSTRM HV EFHV0043 M-22EF02 E-7 3 B 2.0 GB AO Aclive 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: ESW TRN A TO SERV AIR CMPSR A ISO EFHV0044 M-22EF01 8-7 3 B 2.0 GB AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: ESW TRN B TO SERV AIR CMPSR B ISO EFHV0045 M-22EF02 G-6 2 A 14.0 BF MO Aclive 0 OIC AT-01 App-J BTC M3 BTO M3 PIT Y2 Valve Name: ESW TRN A FROM CTMT AIR CLRS INNER CTMT HV Revision Date: 12/1912005 Page 139

Callaway IST Program Plan Essential Service Water (EF) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test - Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EFHV0046 M-22EF02 B-6 2 A 14.0 BF MO Active 0 0/C AT-4l App-J BTC M3 BTO M3 PIT Y2 Valve Name: ESW TRN B FROM CTMT AIR CLRS INNER CTMT HV EFHV0047 M-22EF02 G-6 2 A 10.0 BF MO Active 0 C AT-01 App-J BTC M3 PIT Y2 Valve Name: ESW TRN A FROM CTMT AIR CLRS BYP ISO HV EFHV0048 M-22EF02 C-6 2 A 10.0 BF MO Active 0 C AT-01 App-J BTC M3 PIT Y2 Valve Name: ESW TRN B FROM CTMT AIR CLRS BYP ISO HV EiHV0049 M-22EF02 G-4 2 A 14.0 BF MO Active C O/C AT-01 App-J BTC M3 BTO M3 PIT Y2 Valve Name: ESW TRN A FROM CTMT AIR ClRS OUTER CTMT HV EFHV0050 M-22EF02 B-6 2 A 14.0 BF MO Active C O/C AT-01 App-J BTC M3 BTO M3 PIT Y2 Valve Name: ESW TRN B FROM CTMT AIR ClRS OUTER CTMT HV EFHV0051 M-22EF02 G4 3 B 24.0 BF MO Active 0/C 0 STO M3-PIT Y2 Valve Name: ESW TRN A TO CCW HX A HV

{ H V0052 M-22EF02 C4 3 B 24.0 BF MO Active O/C 0 BTO M3 PIT Y2 Valve Name: ESW TRN B TO CCW HX B HV EFHVW059 M-22EF02 G-3 3 B 24.0 BF MO Active O/C O/C BTC M3 BTO M3 PIT Y2 Valve Name: ESW TRN A FROM CCW HX A HIV Revision Date: 12/19/2005 Page 140

Callaway IST Program Plan Essential Se~rvice Water (EF) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

EFHV060 M-22EF02 C-3 3 B 24.0 BF MO Active O/C OC BTC M3 BTO M3 PIT Y2 Valve Name: ESW TRN B FROM CCW HX B HV EFHV0065 M-U2EF01 B-6 3 B 30.0 BF MO Active 0 O/C BTC M3 BTO M3 PIT Y2 Valve Name: ESW UHS COOL-1WR TRN A B"P HV EFHV0066 M-U2EF01 B-3 3 B 30.0 BF MO Active 0 O/C BTC M3 BTO M3 PIT Y2 Valve Name: ESW UHS COOL-TWR TRN B BYP HV EFHV0097 M-U2EF01 F-6 3 B 3.0 GT MO Acfive 0 OC BTC M3 TP-02 PIT Y2 Valve Name: ESW PMP A DISCH RECIRC HV EFHV0098 M-U2EF01 D-6 3 B 3.0 GT MO Active 0 O/C BTC M3 TP-02 PIT Y2 Valve Name: ESW PMP B DISCH RECIRC HV EFPDVO019 M-U2EF01 F.4 3 B 3.0 GT MO Active C OIC BTC M3 BTO M3 PIT Y2 Valve Name: ESW S-C STR A DRN DP CTRL VLV EFPDVO020 M-U2EF01 D4 3 B 3.0 GT MO Active C OIC BTC M3 BTO M3 PIT Y2 Valve Name: ESW S-C STR B DRN DP CTRL VLV EFVW001 M-U2EF01 G-5 3 C 30.0 CK SA Active SYS 0 CC M3 TP-01 CO M3 Valve Name: ESW PMP A DISCH CHECK EFV0004 M-U2EF01 D-5 3 C 30.0 CK SA Active SYS 0 CC M3 TP-01 CO M3 Valve Name: ESW PMP B DISCH CHECK Revision Date: 12/19/2005 Page 141

Callaway IST Program Plan Essential Service Water (EF) Valve Table P&ID Safety Valve Act. Active / Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EFV0G46 M-22EF02 E-6 3 C 2.5 CK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: ESW TRN A FROM SERV AIR CMPSR CHECK VALVE EFV0076 W22EF01 B-6 3 C 2.5 CK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: ESW TRN B FROM SERV AIR CMPSR CHECK VLV l-'age 142 Revision Date:

Revision 12/19/2005 12V19t2005 Page 142

Callaway IST Program Plan Component Cooling Water (EG) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EGHV0011 M-22EG01 F-8 3 B 1.5 GB MO Active C 0 BTO M3 PIT Y2 Valve Name: ESW TO CCW TRN A UPSTRM HV EGHV0012 M-22EG01 C-8 3 8 1.5 GB MO Active C 0 STO M3 PIT Y2 Valve Name: ESW TO CCW TRN B UPSTRM HV EGHV0013 W22EG01 F-7 3 B 1.5 GB MO Active C 0 BTO M3 PIT Y2 Valve Name: ESW TO CCW TRN A DNSTRM HV EGHV0014 M-22EG01 C-7 3 B 1.5 GB MO Active C 0 BTO M3 PIT Y2 Valve Name: ESW TO CCW TRN B DNSTRM HV EGHV0015 M-22EG01 D-6 3 B 18.0 BF MO Active 0 OC BTC M3 BTO M3 PIT M3 Valve Name: CCW TRN A SPLY/RTN ISO HV EGHV0016 M-22EG01 D-6 3 B 18.0 BF MO Aclive 0 O/C BTC M3 BTO M3 PIT M3 Valve Name: CCW TRN B SPLY/RTN ISO HV EGHV0053 M-22EG02 G-5 3 B 18.0 BF MO Active 0 O/C BTC M3 BTO M3 PIT Y2 Valve Name: CCW TRN A SPLY ISO HV

!"'054 M-22EG02 E-5 3 B 18.0 BF MO Active 0 O/C BTC M3 BTO M3 PIT Y2 Valve Name

CCW TRN B SPLY ISO HV EGHV0058 M-22EG03 H-5 2 A 12.0 GT MO Active 0 C AT-01 App-J BTC M3 PIT Y2 Valve Name: CCW TO CTMT OUTER ISO HV Revision Date: 12119/2005 Page 143

Callaway IST Program Plan Component Cooling Water (EG) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EGHV0059 M-22EG03 C-5 2 A 12.0 GT MO Active 0 C AT-01 AppJ BTC M3 PIT Y2 Valve Name: CCW FROM CTMT OUTER ISO VLV EGHV0060 M-22EG03 B-5 2 A 12.0 GT MO Active 0 C AT-01 App-J BTC M3 PIT Y2 Valve Name: CCW FROM RCS IN CTMT ISO HV EGHV0061 M-22EG03 C-4 2 A 4.0 GT MO Active 0 C AT-01 App-J BTC M3 PIT Y2 Valve Name: CCW FROM RCP THRM BAR OUTER CTMT ISO EGHV0062 M-22EG03 BA4 2 A 4.0 GT MO Active 0 C AT-01 App-J BTC M3 PIT Y2 Valve Name: CCW FROM RCS IN CTMT ISO NV EGHV0069A M-22EG03 F-8 3 B 14.0 BF AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CCW TO RW PROT A SPLY ISO NV EGHV0069B M-22EG03 F-6 3 B 14.0 BF AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CCW FROM RW PROT A RTN ISO NV EGHV0070A M-22EG03 F-8 3 B 14.0 BF AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CCW TO RW PROT B SPLY ISO NV EGHV0070B M-22EG03 F-6 3 B 14.0 BF AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CCW FROM RW PROT B RTN ISO HV Revision Date: 12/19/2005 Page 144

Callaway IST Program Plan Component Cooling Water (EG) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EGHV0101 M-22EG02 G-4 3 B 18.0 BF MO Acfive C O/C BTC M3 BTO M3 PIT Y2 Valve Name: CCW TO RHR HX A ISO EGHV0102 M-22EG02 C-4 3 B 18.0 BF MO Active C O/C BTC M3 BTO M3 PIT Y2 Valve Name: CCW TO RHR HX B ISO EGHV0127 M-22EG03 G-5 2 A 12.0 GT MO Passive C C AT-01 App-J PIT Y2 Valve Name: CCW TO CTMT BYP ISO HV EGHV0130 M-22EG03 B-5 2 A 12.0 GT MO Passive LC C AT-01 App-J PIT Y2 Valve Name: CCW FROM RCS CTMT EGHV0060 BYP ISO HV EGHV0131 M-22EG03 C-5 2 A 12.0 GT MO Passive LC C AT-01 App-J PIT Y2 Valve Name: CCW FROM CTMT EGHV0059 BYP ISO EGHV0132 M-22EG03 BA 2 A 4.0 GT MO Passive LC C AT-01 App-J PIT Y2 Valve Name: CCW FROM RCS CTMT EGHV0062 BYP ISO HV EGHV0133 M-22EG03 C-5 2 A 4.0 GT MO Passive LC C AT-01 App PIT Y2 Valve Name: CCW FROM RCP THRM BAR EGHV0061 BYP ISO EGLV0001 M-22EG01 G-7 3 B 3.0 GB AO Active C C BTC W FC M3 TP-04 PIT Y2 Valve Name: Dl WTR TO CCW SRG TK A LV EGLVO002 M-22EG01 C-7 3 B 3.0 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: Dl WTR TO CCW SRG TK B LV Revision Date: 12/19/2005 Page 145

Callaway IST Program Plan Component Cooling Water (EG) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EGRV0009 M-22EG01 G-6 3 B 2.0 GB AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CCW SRG TK A VENT CTRL VLV EGRV0010 M-22EG01 C-6 3 B 2.0 GB AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CCW SRG TK B VENT CTRL VLV EGTV0029 M-22EG02 G-6 3 B 20.0 BF AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CCW HX A CCW BYP TV EGTVO030 M-22EG02 C-6 3 8 20.0 BF AO Active 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CCW HX B CCW BYP TV EGV0003 M-22EG01 G-3 3 C 20.0 CK SA Active SYS O/C CC M3 CO M3 Valve Name: CCW PMP A DISCH CHECK EGV0007 M-22EG01 E-3 3 C 20.0 CK SA Active SYS O/C CC M3 CO M3 Valve Name: CCW PMP C DISCH CHECK EGV0012 M-22EG01 D-3 3 C 20.0 CK SA Active SYS O/C CC M3 CO M3 Valve Name: CCW PMP B DISCH CHECK FGVOW16 M-22EG01 C-3 3 C 20.0 CK SA Active SYS O/C CC M3 CO M3 Valve Name: CCW PMP D DISCH CHECK EGV0159 M-22EG01 G-6 3 C 2.0 RV SA Active C O/C RT Y10 Valve Name: CCW SRG TK A RELIEF EGV0170 M-22EG01 C-4 3 C 2.0 RV SA Active C O/C RT Y10 Valve Name: CCW SRG TK B RELIEF Revision Date: 12/19/2005 Page 146

Callaway iST Program Plan Component Cooling Water (EG) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EGV0204 M-22EG03 H-4 2 AC 12.0 CK SA Active SYS C AT-41 App-J CCL CM TP-08 COF CM TP-08 Valve Name: CCW TO RCS IN CTMT CHECK EGV0305 M-22EG01 G4 3 C 1.0 RV SA Active C OIC RT Y4 Valve Name: CCW SRG TK A VAC BRK EGV0306 M-22EG01 C-6 3 C 1.0 RV SA Acve C O/C; RT Y4 Valve Name: CCW SRG TK B VAC BRK Page 147 Revislon Date:

Revision Date: 12/19/2005 Page 147

Callaway IST Program Plan Residual Heat Removal System (EJ) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EJ8708A M-22EJ01 F-7 2 C 3.0 RV SA Active C O/C RT Y10 Valve Name: RHR PUMP A SUCT PRESS RLF EJ87088 M-22EJ01 C-7 2 C 3.0 RV SA Active C O/C RT Y10 Valve Name: RHR PUMP B SUCT PRESS RLF EJ8730A M-22EJ01 G-4 2 C 10.0 CK SA Active SYS O/C CC Cs CSJ-15 CO CS CSJ-15 Valve Name: RHR HX A OUTLET CHECK VLV EJ8730B M-22EJ01 CA 2 C 10.0 CK SA Active SYS O/C CC CS CSJ-15 CO CS CSJ-15 Valve Name: RHR HX B OUTLET CHECK VLV EJ8841A M-22EJ01 E-2 1 AC 6.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COA CM TP-08 Valve Name: RHR TRNS SIS HOT LEG LOOP 2 RECIRC SPLY HDR CHECK EJ8841B M-22EJ01 D-2 1 AC 6.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP48 COA CM TP-08 Valve Name: RHR TRNS SIS HOT LEG LOOP 3 RECIRC SPLY HDR CHECK EJ8842 M-22EJ01 D-3 2 C 0.75 RV SA Active C O/C RT Y10 Valve Name: RHR TRNS A & B Si SYS HOT LEG RECIRC SPLY HDR PRESS RELIEF LJ8856A M-22EJI01 G-3 2 C 0.75 RV SA Active C O/C RT Y10 Valve Name: RHR TRN A ACC INJ SPLY HDR RELIEF jJijS6B M-22EJ01 B-3 2 C 0.75 RV SA Active C O/C RT Y10 Valve Name: RHR TRN B ACC INJ SPLY HDR RELIEF EJ8958A M-22EJ01 F-6 2 C 14.0 CK SA Active SYS O/C CC RR RJ-11 CO RR RJ-1 Valve Name: RHR PUMP A SUCT FROM RWST CHECK VLV EJ8958B M-22EJI01 B-6 2 C 14.0 CK SA Active SYS O/C CC RR RJ-11 CO RR RJ-1 Valve Name: RHR PUMP B SUCT FROM RWST CHECK VLV Revision Date: 12/19/2005 Page 148

Callaway IST Program Plan Residual Heat Removal System (EJ) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

EJ8969A M-22EJ01 H4 2 C 8.0 CK SA Active SYS 0 CCF CM TP-08 COF CM TP-08 Valve Name: RHR TRN A CHARGING PUMPS SPLY HDR CHECK VLV EJ8969B M-22EJ01 A-4 2 C 8.0 CK SA Active SYS 0 CCF CM TP-08 COF CM TPa8 Valve Name: RHR TRN B SAFETY INJ PUMPS SPLY HDR CHECK VLV EJFCV0610 M-22EJ01 H-4 2 B 3.0 GT MO Active 0 O/C BTC M3 BTO M3 PIT Y2 Valve Name: RHR PUMP A MINIMUM FLOW CTRL VLV EJFCV0611 M-22EJ01 A-5 2 B 3.0 GT MO Active 0 OIC BTC M3 BTO M3 PIT Y2 Valve Name: RHR PUMP B MINIMUM FLOW CTRL VLV EJFV/0618 M-22EJ01 F-5 2 B 8.0 BF AO Passive C C PIT Y2 Valve Name: RHR HX A BYP FLOW CTRL VLV EJFCV0619 M-22EJ01 B-5 2 B 8.0 BF AO Passive C C PIT Y2 Valve Name: RHR HX B BYP FLOW CTRL VLV EJHCV0606 M-22EJ01 G-4 2 B 10.0 BF AO Passive 0 0 PIT Y2 Valve Name: RHR HX A OUTLET FLOW CTRL VLV EJHCV0607 M-22EJ01 C4 2 B 10.0 BF AO Passive 0 0 PIT Y2 Valve Name: RHR HX B OUTLET FLOW CTRL VLV L-,n. ;'8825 M-22EJ01 E-2 2 A 0.75 GB AO Passive C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RHR TRN A&B SIS HOT LEG RECIRC SIS TEST LINE ISO EJHCV8890A M22EJ01 F-2 2 A 0.75 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RHR TRN A ACC INJ SIS TEST LINE ISO Revision Date: 12119/2005 Page 149

Callaway IST Program Plan Residual Heat Removal System (EJ) Valve Table PoID Safety Valve Act. Actie I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

EJHCV8890B M-22EJ01 C-2 2 A 0.75 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RHR TRN B ACC INJ SIS TEST LINE ISO EJHVW014 M-22EJ01 H-5 2 B 1.0 GB SO Passive C C PIT Y2 Valve Name: RHR PMP A MIN FLOW TO NUCLEAR SAMP SYS ISO EJHV0015 M-22EJ01 A-5 2 B 1.0 GB SO Passive C C PIT Y2 Valve Name: RHR PMP B MIN FLOW TO NUCLEAR SAMP SYS ISO EJHV8701A M-22EJ01 F-8 I A 12.0 GT MO Active C C AT-02 Y2 BTC CS CSJ-16 PIT Y2 Valve Name: RHR PUMP A SUCT ISO

[J:V8701B M-22EJ01 B-8 1 A 12.0 GT MO Active C C AT-02 Y2 BTC CS CSJ-16 PIT Y2 Valve Name: RHR PUMP B SUCT ISO EJHV8716A M-22EJ01 E4 2 B 10.0 GT MO Active 0 O/C BTC CS CSJ-17 BTO CS CSJ-17 PIT Y2 Valve Name: RHR TRN A Si SYS HOT LEG RECIRC ISO EJHV8716B M-22EJ01 D.4 2 B 10.0 GT MO Active 0 O/C BTC CS CSJ-17 BTO CS CSJ-17 PIT Y2 Valve Name: RHR TRN B Si SYS HOT LEG RECIRC ISO

.rV88O4A M-22EJ01 G-4 2 B 8.0 GT MO Active C O/C BTO CS CSJ-18 TP42 PIT Y2 Valve Name: RHR TRN A CHARGING PUMPS SPLY ISO EJHV8804B M-22EJ01 A-4 2 B 8.0 GT MO Active C O/C BTO CS CSJ-18 TP-02 PIT Y2 Valve Name: RHR TRN B SI PUMPS SPLY ISO Revision Date: 1211912005 Page 150

Callaway IST Program Plan Residual Heat Removal System (EJ) Valve Table P&ID Safety Valve Act Active I Normal -Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

EJHV8809A M-22EJ01 G-3 2 B 10.0 GT MO Active 0 0/C BTC CS CSJ-18 TP-02 PIT Y2 Valve Name: RHR TRN A ACC INJ SPLY ISO EJHV8809B M-22EJ01 C-3 2 B 10.0 GT MO Active 0 01C BTC CS CSJ-18 TP-02 PIT Y2 Valve Name: RHR TRN B ACC INJ SPLY ISO EJHV8811A M-22EJ01 E-7 2 B 14.0 GT MO Active C O/C BTC CS CSJ-20 BTO CS CSJ-20 PIT Y2 Valve Name: CTMT RECIRC SUMP A TO RHR PUMP A SUCT ISO EJHV88i1B M-22EJ01 D-7 2 B 14.0 GT MO Active C 0/C BTC CS CSJ-20 BTO CS CSJ-20 PIT Y2 Valve Name: CTMT RECIRC SUMP B TO RHR PUMP B SUCT ISO EJHV8840 M-22EJ01 E-3 2 B 10.0 GT MO Active C O/C BTO CS CSJ-21 TP-02 PIT Y2 Valve Name: RHR TRAIN A & B Si SYS HOT LEG RECIRC ISO Revision Date: 12/19/2005 Page 151

Callaway IST Program Plan High Pressure Coolant Injection (EM) Valve Table P&8D Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EM8815 M-22EM02 D-3 1 AC 3 CK SA Active SYS O/C AT-02 Y2 CC RR RJ-12 CO RR RJ-12 Valve Name: BORON INJ HDR OUT CHECK EM8851 M-22EM01 C4 2 C 0.75 RV SA Acive C O/C RT Y4 Valve Name: SI PMPS DISCH TO COLD LEGS INJ PRESS RELIEF EM8853A M-22EM01 F-5 2 C 0.75 RV SA Act've C , O/C RT Y4 Valve Name: SI PMP A DISCH PRESS RELIEF EM88538 M-22EM01 E-5 2 C 0.75 RV SA Active C O/C RT Y4 Valve Name: SI PMP B DISCH PRESS RELIEF!

EM8858A M-22EM01 E-7 2 C 0.75 RV SA Active C O/C RT Y4 Valve Name: SI PMP A SUCT PRESS RELIEF EM88588 M-22EM01 D-7 2 C 0.75 RV SA Active C O/C RT Y4 Valve Name: SI PMP B SUCT PRESS RELIEF EM8922A M-22EM01 E-5 2 C 4.0 CK SA Active SYS O/C CC RR RJ-13 CO RR RJ-13 Valve Name: SI PMP A DISCH CHECK EM8922B M-22EM01 D-5 2 C 4.0 CK SA Active SYS O/C CC RR RJ-13 CO RR RJ-13 Valve Name: SI PMP B DISCH CHECK EM8926A M-22EM01 E-7 2 C 8.0 CK SA Active SYS O/C CC RR RJ-14 CO RR RJ-14 Valve Name: SI PMPS SUCT CHECK A 1!8926B M-22EM01 D-7 2 C 8.0 CK SA Active SYS O/C CC RR RJ-14 CO RR RJ-14 Valve Name: SI PMPS SUCT CHECK B EMHV8801A M-22EM02 D4 2 B 4 GT MO Active C 01C BTO M3 TP-02 PIT Y2 Valve Name: BORON INJ HDR TRAIN A OUT TO COLD LEGS ISO Revision Date: 12/19/2005 Page 152

Callaway IST Program Plan High Pressure Coolant Injection (EM) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EMHV8801B M-22EM02 D-4 2 B 4 GT MO Active C O/C BTO M3 TP-02 PIT Y2 Valve Name: BORON INJ HDR TRAIN B OUT TO COLD LEGS ISO EMHV8802A W22EM01 E-4 2 B 4 GT MO Acbive C O/C BTO M3 TP-02 PIT Y2 Valve Name: Si PMP A DISCH TO HOT LEG INJ ISO (3.0.3)

EMHV8802B M-22EM01 D-4 2 B 4 GT MO Active C O/C BTO M3 TP-02 PIT Y2 Valve Name: Si PMP B DISCH TO HOT LEG INJ ISO (3.0.3)

EMHV8803A M-22EM02 C-7 2 B 4 GT MO Active C 0 BTO M3 PIT Y2 Valve Name: BORON INJ HDR SPLY FROM CCP A ISO EMHV8803B M-22EM02 A-7 2 B 4 GT MO Active C 0 BTO M3 PIT Y2 Valve Name: BORON INJ HDR SPLY FROM CCP B ISO EMHV8807A M-22EM01 G-7 2 B 6 GT MO Active C O/C STO M3 TP-02 PIT Y2 Valve Name: RHR HX A TO Si PMPS SUCT DNSTRM ISO VLV A EMHV8807B M-22EM01 F-7 2 B 6 GT MO Active C O/C BTO M3 TP-02 PIT Y2 Valve Name: RHR HX A TO Si PMPS SUCT DNSTRM ISO VLV B EMHV8814A M-22EM01 B-4 2 A 1.5 GB MO Aclive 0 O/C AT-02 Y2 BTC M3 TP-02 PIT Y2 Valve Name: SI PMP A RECIRC TO RWST ISO EMHV8814B M-22EW1I B-5 2 A 1.5 GB MO Active 0 O/C AT-02 Y2 BTC M3 TP-02 PIT Y2 Valve Name: Si PMP B RECIRC TO RWST ISO EMHV8821A M-22EM01 E-4 2 B 4 GT MO Active 0 O/C BTC M3 TP-02 PIT Y2 Valve Name: Si PMP A DISCH TO COLD LEG INJ ISO Revision Date: 12/19/2005 Page 153

Callaway IST Program Plan High Pressure Coolant Injection (EM) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EMHV8821B M-22EM01 D4 2 B 4 GT MO Active 0 0/C BTC M3 TP-02 PIT Y2 Valve Name: SI PMP B DISCH TO COLD LEG INJ ISO EMHV8823 M-22EM01 C-4 2 B 0.75 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SI/ACC INJ TEST LINE ISO HV EMHV8824 M-22EM01 D-3 2 B 0.75 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SI PMP B DISCH TEST LINE ISO HV EMHV8835 M-22EM01 B-4 2 B 4.0 GT MO Active 0 0/C BTC CS CSJ-22 TP-02 PIT Y2 Valve Name: SI PMPS DISCH TO COLD LEG INJ ISO (3.0.3)

EMHV8843 M-22EM02 C-4 2 B 0.75 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: BORON INJ HDR OUT UPSTRM TEST LINE ISO HV EMHV8871 M-22EM01 G-5 2 A 0.75 GB AO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SI SYS IN CTMT TEST LINE ISO HV EMHV8881 M-22EM01 G4 2 B 0.75 GB AO Active C C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SI PMP A DISCH TEST LINE ISO HV EMHV8882 M-22EM02 C-3 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: BORON INJ HDR OUT DNSTRM TEST LINE ISO HV Revision Date: 12/19/2005 Page 154

Callaway IST Program Plan High Pressure Coolant Injection (EM) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EMHV8883 M-22EM01 F-6 2 A 1.0 GB AO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: ACC TKS FILL LINE FROM SI PMPS ISO EMHV8889A M-22EM01 G-2 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: SI PMP B LOOP 1 HOT LEG TEST LINE ISO NV EMHV8889B M-22EM01 G-3 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: SI PMP A LOOP 2 HOT LEG TEST LINE ISO HV EMHV8889C M-22EM01 G-2 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: SI PMP A LOOP 3 HOT LEG TEST LINE ISO HV EMHV8889D M-22EM01 G-2 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: SI PMP B LOOP 4 HOT LEG TEST LINE ISO HV EMHV8923A M-22EM01 E-7 2 B 6.0 GT MO Passive 0 0 PIT Y2 Valve Name: RWST TO SI PMP A SUCT ISO HV (3.0.3)

EMHV8923B M-22EM01 D-7 2 B 6.0 GT MO Passive 0 0 PIT Y2 Valve Name: RWST TO SI PMP B SUCT ISO HV EMHV8924 M-22EM01 F-8 2 B 6 GT MO Passive 0 0 PIT Y2 Valve Name: RHR HX A TO SI PMPS SUCT UP STRM ISO (3.0.3)

EMHV8964 M-22EM01 G-6 2 A 0.75 GB AO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: SI SYS OUT CTMT TEST LINE ISO EMV0001 M-22EM01 F-3 1 AC 2.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COA CM TP-08 COF CM TP-08 Valve Name: SI PMP A DISCH TO HOT LEG LOOP 2 UPSTRM CHECK Revision Date: 12119/2005 Page 155

Callaway IST Program Plan High Pressure Coolant Injection (EM) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EMV0002 M-22EM01 E-3 I AC 2.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COA CM TP-08 COF CM TP-8 Valve Name: Si PMP A DISCH TO HOT LEG LOOP 3 UPSTRM CHECK EMV0003 M-22EM01 D-3 1 AC 2.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COA CM TP-8 COF CM TP-08 Valve Name: Si PMIP B DISCH TO HOT LEG LOOP I UPSTRM CHECK EMV0004 M-22EM01 C-3 1 AC 2.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COA CM TP-08 COF CM TP-08 Valve Name: Si PMP B DISCH TO HOT LEG LOOP 4 UPSTRM CHECK EMV0005 M-22EM01 A-4 2 C 1.5 CK SA Active SYS 0 CC M3 TP-01 CO M3 Valve Name: Si PMP A DISCH TO RWST CHECK Ev0006 M-22EM01 F-6 2 AC 1 CK SA Active SYS C AT-01 App-J CC RR RJ-15 CO OP TP-01 Valve Name: Si PMPS ACC TKS FILL UNE CHECK EMV0007 M-22EM01 A-5 2 C 1.5 CK SA Active SYS 0 CC M3 TP-01 CO M3 Valve Name: Si PMP B DISCH TO RWST CHECK Revision Date: 12/19/2005 Page 156

Callaway IST Program Plan Containment Spray (EN) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

ENHVW001 M-22EN01 G-7 2 B 12.0 GT MO Active C O/C BTC CS CSJ-23 TP-02 BTO CS CSJ-23 TP-02 PIT Y2 Valve Name: CTMT RECIRC SMP TO CTMT SPRY PMP A HV ENHV0006 M-22EN01 G4 2 B 10.0 GT MO Active C O/C BTC M3 BTO M3 PIT Y2 Valve Name: CTMT SPRY PMP A DISCH- HV ENHV0007 M-22EN01 B-7 2 B 12.0 GT MO Active C O/C BTC CS CSJ-23 BTO CS CSJ-23 PIT Y2 Valve Name: CTMT RECIRC SMP TO CTMT SPRY PMP B HV ENHV0012 M-22EN01 B4 2 B 10.0 GT MO Active C OIC BTC M3 BTO M3 PIT Y2 Valve Name: CTMT SPRY PMP B DISCH HV ENVO002 M-22EN01 G-7 2 C 12.0 CK SA Active SYS 0 CCD CM TP-08 COD CM TP-08 Valve Name: CTMT SPRY ISO VLV ENCAP A OUT CHECK ENVO003 M-22EN01 G-7 2 C 12.0 CK SA Active SYS O/C CCD CM TP-08 COD CM TP-08 Valve Name: RWST TO CTMT SPRY PMP A CHECK ENV004 M-22EN01 G-6 2 C 10.0 CK SA Active SYS 0 CCD CM TP-08 COD CM TP-08 Valve Name: CTMT SPRY PMP A DISCH CHECK tNV0008 M-22EN01 B-7 2 C 12.0 CK SA Active SYS 0 CCD CM TP-08 COD CM TP-08 Valve Name: CTMT SPRY ISO VLV ENCAP B OUT CHECK ENV0009 M-22EN01 B-7 2 C 12.0 CK SA Active SYS O/C CCD CM TP-08 COD CM TP-08 Valve Name: RWST TO CTMT SPRAY PMP B CHECK Revision Date: 12/19/2005 Page 157

Callaway IST Program Plan Containment Spray (EN) Valve Table P&6D Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

ENVO010 M-22EN01 8-5 2 C 10.0 CK SA Active SYS 0 CCD CM TPO8 COD CM TP-08 Valve Name: CTMT SPRY PMP B DISCH CHECK ENVO013 M-22EN01 G4 2 C 10.0 CK SA Active SYS O/C CCD CM TP-08 COD CM TP-08 Valve Name: CTMT SPRY PMP A DISCH IN CTMT CHECK ENVO017 M-22EN01 84 2 C 10.0 CK SA Active SYS OIC CCD CM TP48 COD CM TP-08 Valve Name: CTMT SPRY PMP B DISCH IN CTMT CHECK Page 158 Revision Date:

Revision Date: 12/19/2005 1211912005 Page 158

Callaway IST Program Plan Accumulator Safety Injection (EP) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

EP8818A M-22EP01 G 1 I3 AC 6.0 CK SA Active SYS O/C AT-02 Y2 CCD CM TP-08 CCL CM TP408 COD CM TP-08 Valve Name: RHR PMPS TO RCS COLD LEG LOOP I CHECK EP8818B M-22EP01 F-3 1 AC 6.0 CK SA Active SYS CvC AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: RHR PMPS TO RCS COLD LEG LOOP 2 CHECK EP8818C M-22EP01 D-3 1 AC 6.0 CK SA Active SYS OIC AT-02 Y2 CCL CM TP48 COF CM TP-08 Valve Name: RHR PMPS TO RCS COLD LEG LOOP 3 CHECK EPB818D M-22EP01 C-3 1 AC 6.0 CK SA Active SYS 0/C AT-02 Y2 CCD CM TP-08 CCL CM TP-08 COD CM TP-08 Valve Name: RHR PMPS TO RCS COLD LEG LOOP 4 CHECK EP8855A M-22EP01 H-7 2 C 1.0 RV SA Active C O/C RT Y10 Valve Name: Si ACC TK A PRESS RELIEF EP8855B M-22EP01 E-7 2 C 1.0 RV SA Acfive C OC RT Y1O Valve Name: Si ACC TK B PRESS RELIEF EP8855C M-22EP01 D-7 2 C 1.0 RV SA Active C 0/C RT Y10 Valve Name: Si ACC TK C PRESS RELIEF

-088550 M-22EP01 C-7 2 C 1.0 RV SA Active C O/C RT Y10 Valve Name: SI ACC TK D PRESS RELIEF EP8956A M-22EP01 G4 1 AC 10.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: Si ACC TK A OUT UPSTRM CHECK Revision Date: 12/19/2005 Page 159

Callaway IST Program Plan Accumulator Safety Injection (EP) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

EP8956B M-22EP01 E-4 1 AC 10.0 CK SA Active SYS OIC AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: SI ACC TK B OUT UPSTRM CHECK EP8956C M-22EP01 C4 1 AC 10.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: SI ACC TK C OUT UPSTRM CHECK EP8956D M-22EP01 B4 1 AC 10.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: SI ACC TK D OUT UPSTRM CHECK EPHV8808A M-22EP01 G-5 2 B 10.0 GT MO Active 0 O/C BTC CS CSJ-24 TP-02 PIT Y2 Valve Name: SI ACC TK A OUT ISO EPHV8808B M-22EP01 E-5 2 B 10.0 GT MO Passive 0 0 PIT Y2 Valve Name: SI ACC TK B OUT ISO EPHV8808C M-22EP01 C-5 2 B 10.0 GT MO Passive 0 0 PIT Y2 Valve Name: SI ACC TK C OUT ISO tiFhV8808D M-22EP01 B-5 2 B 10.0 GT MO Active 0 OIC BTC CS CSJ-24 TP-02 PIT Y2 Valve Name: SI ACC TK D OUT ISO EPHV8875A M-22EP01 G-6 2 8 1.0 GB AO Passive C C PIT Y2 Valve Name: SI ACC TK A N2 SPLY HV EPHV8875B M-22EP01 F-6 2 B 1.0 GB AO Passive C C PIT Y2 Valve Name: SI ACC TK B N2 SPLY HV EPHV8875C M-22EP01 D46 2 B 1.0 GB AO Passive C C PIT Y2 Valve Name: SI ACC TK C N2 SPLY HV EPHV8875D M-22EP01 B-6 2 B 1.0 GB AO Passive C C PIT Y2 Valve Name: SI ACC TK D N2 SPLY HV Revision Date: 12/19/2005 Page 160

Callaway IST Program Plan Accumulator Safety Injection (EP) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EPHV8877A M-22EP01 F4 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: Si ACC A OUT UPSTRM CHECK TEST LINE ISO EPHV8877B M-22EP01 E4 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: Si ACC B OUT UPSTRM CHECK TEST LINE ISO EPHV8877C M-22EP01 C4 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: Si ACC C OUT UPSTRM CHECK TEST LINE ISO EPHV8877D M-22EP01 A4 2 8 0.75 GB AO Passive C C PIT Y2 Valve Name: SI ACC D OUT UPSTRM CHECK TEST LINE ISO FPHV8878A M-22EP01 G-5 2 B 1.0 GB AO Passive C C PIT Y2 Valve Name: Si ACC TK A FILL LINE ISO HV EPHV8878B M-22EP01 E-5 2 B 1.0 GB AO Passive C C PIT Y2 Valve Name: Si ACC TK B FILL LINE ISO HV L.PV'878C M-22EP01 D-5 2 B 1.0 GB AO Passive C C PIT Y2 Valve Name: Si ACC TK C FILL LINE ISO HV EPHV8878D M-22EP01 B-5 2 B 1.0 GB AO Passive C C PIT Y2 Valve Name: SI ACC TK D FILL LINE ISO HV EPHV8879A M-22EP01 G4 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: Si ACC A OUT DNSTRM CHECK TEST LINE ISO F.PHV8879B M-22EP01 E4 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: Si ACC B OUT DNSTRM CHECK TEST LINE ISO nDM8f79c( M-22EP01 D4 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: Si ACC C OUT DNSTRM CHECK TEST LINE ISO

iV8879D M-22EP01 C-2 2 B 0.75 GB AO Passive C C PIT Y2 Valve Name: Si ACC D OUT DNSTRM CHECK TEST LINE ISO

.3880 J M-22EP01 A-3 2 A 1.0 GB AO Passive C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: Si ACC TKS N2 SPLY HV Revision Date: 12/19/2005 Page 161

Callaway IST Program Plan Accumulator Safety Injection (EP) Valve Table P&ID Safety Valve Act. - Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&8D Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EPHV8950A M-22EP01 H-8 2 B 1.0 GB SO Active C 0 BTO CS CSJ-25 PIT Y2 Valve Name: Si ACC TK A VENT HV EPHV8950B M-22EP01 F-8 2 8 1.0 GB SO Active C 0 BTO CS CSJ-25 PIT Y2 Valve Name: Si ACC TK B VENT HV EPHV8950C M-22EP01 F-7 2 B 1.0 GB SO Active C 0 BTO CS CSJ-25 PIT Y2 Valve Name: SI ACC TK B VENT HV EPHV8950D M-22EP01 D-8 2 B 1.0 GB SO Active C 0 BTO CS CSJ-25 PIT Y2 Valve Name: Si ACC TK C VENT NV EPHV8950E M-22EP01 D-7 2 B 1.0 GB SO Active C 0 BTO CS CSJ-25 PIT Y2 Valve Name: SI ACC TK C VENT HV EPHV895OF M-22EP01 C-8 2 B 1.0 GB SO Active C 0 BTO CS CSJ-25 PIT Y2 Valve Name: SI ACC TK D VENT HV EPV0010 M-22EP01 G-3 1 AC 2.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM JP-08 Valve Name: Si PMPS TO RCS COLD LEG LOOP I CHECK EPV0020 M-22EP01 F-3 1 AC 2.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: SI PMPS TO RCS COLD LEG LOOP 2 CHECK EPV0030 M-22EP01 D-3 1 AC 2.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: Si PMPS TO RCS COLD LEG LOOP 3 CHECK Revision Date: 12119/2005 Page 162

Callaway IST Program Plan Accumulator Safety Injection (EP) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

EPV0040 M-22EP01 C-3 1 AC 2.0 CK SA Active SYS O/C AT-02 Y2 CCL CM TP-08 COF CM TP-08 Valve Name: Si PMPS TO RCS COLD LEG LOOP 4 CHECK EPV0046 M-22EP01 A,5 2 AC 1.0 CK SA Active SYS C AT41 App-J CCL CM TP-08 COF CM TP-08 Valve Name: Si ACC TKS N2 SPLY CHECK Page 163 Revision Date: 12/19/2005 12/19/2005 Page 163

Callaway IST Program Plan AFW Pump Turbine (FC) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

FCFV0310 M-22FC02 D-7 3 B 1.0 GB AO Acdive 0 C BTC M3 FC M3 TP-04 PIT Y2 Valve Name: AFP TURB STMLINE DRN FLOW VLV FCHV0312 M-22FC02 F-5 3 B 4.0 GB MO Active C 0 BTO M3 TP-05 Valve Name: AFP TURB MECH TRIPtTHROT HV FCV0001 M-22FC02 G-6 2 C 4.0 CK SA Active SYS O/C CCD CM TP-08 COD CM TP-08 Valve Name: MS LOOP 2 TO AFP TURB UPSTRM CHECK FCV0002 M-22FC02 G-6 2 C 4.0 CK SA Active SYS O/C CCD CM TP-08 COD CM TP-08 Valve Name: MS LOOP 3 TO AFP TURB UPSTRM CHECK PCV0024 M-22FC02 G-6 2 C 4.0 CK SA Active SYS O/C CCD CM TP-08 COD CM TP-08 Valve Name: MS LOOP 2 TO AFP TURB DNSTRM CHECK FCV0025 M-22FC02 G-6 2 C 4.0 CK SA Active SYS O/C CCD CM TP-08 COD CM TP-08 Valve Name: MS LOOP 3 TO AFP TURB DNSTRM CHECK Revision Date: 12/19/2005 Page 164

Callaway IST Program Plan Control Building HVAC (GK) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

SGK04AV1 N/A 3 C 1.0 RV SA Active C O/C RT Y10 Valve Name: CTRL RM AIR CNDR UNIT A REFRIG PRESS RELIEF SGK04BV1 N/A 3 C 1.0 RV SA Active C O/C RT Y10 Valve Name: CTRL RM AIR CNDR UNIT B REFRIG PRESS RELIEF SGKOSAV1 N/A 3 C 1.0 RV SA Active C O/C RT Y10 Valve Name: ELEC EQUIP AIR CNDR UNIT A REFRIG PRESS RELIEF SGK05BVI N/A 3 C 10 RV SA Active C O/C RT Y10 Valve Name: ELEC EQUIP AIR CNDR UNIT B REFRIG PRESS RELIEF Revision Date: 12119/2005 Page 165

Callaway IST Program Plan Containment Hydrogen Control (GS) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

GSHV0003 M-22GS01 E-6 2 A 1.0 GT SO Active C OC AT-01 App-J BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: H2 ANALYZER B SPLY OUTER CTMT ISO NV GSHV0004 M-22GS01 E-5 2 A 1.0 GT SO Active C O/C AT-01 App-J BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: H2 ANLZ B SPLY IN CTMT ISO HV GSHV0005 M-22GS01 D-5 2 A 1.0 GT SO Active C O/C AT-01 App-J BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: H2 ANALYZER B SPLY INNER CTMT ISO NV GSHV0008 M-22GS01 B-6 2 A 1.0 GT SO Active C O/C AT-01 App-J BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: H2 ANALYZER B RTN OUTER CTMT ISO NV GSHV009 M-22GS01 B-6 2 A 1.0 GT SO Active C 0/C AT-01 App-J BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: H2 ANLZ B RTN IN CTMT ISO HV Revision Date: 12/1912005 Page 166

Callaway IST Program Plan Containment Hydrogen Control (GS) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request JusL Pos.

GSHV0012 M-22GS01 E4 2 A 1.0 GT SO Active C O/C AT-01 AppJ BTC M3 BTO M43 FC M3 TP-04 PIT Y2 Valve Name: H2 ANALYZER A SPLY OUTER CTMT ISO HV GSHV0013 M-22GS01 E-5 2 A 1.0 GT SO Active C O/C AT-01 App-J BTC M3 BTO M3 FC M3 TP.04 PIT Y2 Valve Name: H2 ANLZ A SPLY IN CTMT ISO HV CSHVW014 M-22GS01 D-5 2 A 1.0 GT SO Active C O/C AT-01 AppJ BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: H2 ANLZ A SPLY IN CTMT ISO HV GSHV0017 M-22GS01 B4 2 A 1.0 GT SO Active C O/C AT-01 App4 BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: H2 ANALYZER A RTN OUTER CT1MT ISO HV GSHV0018 M-22GS01 B-5 2 A 1.0 GT SO Active C O/C AT-01 App-J BTC M3 BTO M3 FC M3 TP-04 PIT Y2 Valve Name: H2 ANLZ A RTN IN CTMT ISO HV GSHV0020 M-22GS01 F-5 2 A 6.0 BF MO Passive C C AT-01 App4J BTC M3 PIT Y2 Valve Name: H2 PURGE IN CTMT ISO HV Revislon Date: 12/19/2005 Page 167

Callaway IST Program Plan Containment Hydrogen Control (GS) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

GSHV0021 U22GS01 F4 2 A 6.0 BF MO Passive C C AT-01 App-J BTC M3 PIT Y2 Valve Name: H2 PURGE OUTER CTMT ISO RV GSHV0031 M-22GS01 D4 2 A 1.0 GT SO Active 0 C AT-01 App4 BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT ATMS MON SPLY IN CTMT ISO HV GSHV0032 M-22GS01 D-3 2 A 1.0 GT SO Active 0 C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT ATMS MON SPLY OUTER CTMT ISO HV GSHV0033 M-22GS01 C4 2 A 1.0 GT SO Active 0 C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT ATMS MON RTN OUTER CTMT ISO HV GSHV0034 M-22GS01 C4 2 A 1.0 GT SO Active 0 C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT ATMS MON RTN IN CTMT ISO HV GSHV0036 M-22GS01 D-6 2 A 1.0 GT SO Active 0 C AT-01 App-4 BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT ATMS MON SPLY IN CTMT ISO HV GSHV0037 M-22GS01 D-7 2 A 1.0 GT SO Active 0 C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT ATMS MON SPLY OUTER CTMT ISO HV Revision Date: 12/19/2005 Page 168

Callaway

[ST Program Plan Containment Hydrogen Control (GS) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

GSHV0038 M-22GS01 C-4 2 A 1.0 GT SO Active 0 C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT ATMS MON RTN OUTER CTMT ISO HV GSHV0039 W22GS01 C-4 2 A 1.0 GT SO Active 0 C AT-01 App-J BTC M3 FC M3 TP-04 jIT Y2 Valve Name: CTMT ATMS MON RTN IN CTMT ISO HV

• Page 169 Revision Date:

Revision Date: 12/19/2005 12/19/2005 Page 169

Callaway IST Program Plan Containment Purge (GT) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

GTHZ0004 W22GT01 D-4 2 A 18.0 BF AO Active SYS C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT MINI PURGE AIR SPLY OUTER CTMT DMPR GTHZ0005 Mr22GT01 A-5 2 A 18.0 BF AO Active SYS C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT MINI PURGE AIR SPLY INNER CTMT UPSTRM DMPR GTHZ0006 M-22GT01 C-4 2 A 36.0 BF AO Active C C AT-01 Appo BTC RR RJ-16 FC RR RJ-16 TP-04 PIT Y2 Valve Name: CTMT SID PURGE AIR SPLY OUTER CTMT DMPR GTHZ0007 M-22GT01 C-5 2 A 36.0 BF AO Active C C AT-01 App-J BTC RR RJ-16 FC RR RJ-16 TP-04 PIT Y2 Valve Name: CTMT SID PURGE AIR SPLY INNER CTMT DMPR GTHZOD08 M-22GT01 C-6 2 A 36.0 BF AO Active C C AT-01 AppJ BTC RR RJ-16 FC RR RJ-16 TP-04 PIT Y2 Valve Name: CTMT SID PURGE EXH INNER CTMT DMPR GTHZ0009 M-22GT01 C-7 2 A 36.0 BF AO Active C C AT-01 App-J BTC RR RJ-16 FC RR RJ-16 TP-04 PIT Y2 Valve Name: CTMT SID PURGE EXH OUTER CTMT DMPR Revision Date: 12/19/2005 Page 170

Callaway iST Program Plan Containment Purge (GT) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

GTHZ0011 M-22GT01 A-6 2 A 18.0 BF AO Acbive SYS C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT MINI PURGE EXH INNER CTMT DNSTRM DMPR GTHZ0012 M-22GT01 A-7 2 A 18.0 BF AO Active SYS C AT-01 Appo BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT MINI PURGE EXH OUTER CTMT DMPR i cew

. . Da e i r--

-- - -P ge-1 7 Revision Date: 1Z/1912005 Page 171

Callaway IST Program Plan Liquid Radwaste (HB) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

HBHV7126 M-22HB01 G-6 2 A 0.75 Di AO Active 0 C AT-01 Appo BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RCDT TO GRW CMPSR IN CTMT HV HBHV7136 M-22HB01 F-3 2 A 3.0 Dl AO Active 0 C AT41 Appo BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RCDT HX OUT HDR OUTER CTMT HV HBI'V7150 M-22HB01 G-6 2 A 0.75 Di AO Active 0 C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RCDT OUT TO GRW SYS OUTER CTMT HV HBHWI7T76 M-22HB01 F-3 2 A 3.0 Di AO Active 0 C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: RCDT HX OUT HDR IN CTMT ISO HV Date: 1211912005 Page 172 Revi.ion Date:

Revision 12/1912005 Page 172

Callaway IST Program Plan Decontamination (HD) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

HDVO016 W22HDO1 B-7 2 A 2.0 GB MA Passive LC C AT-01 App-J Valve Name: RX HEAD DECON AUX STM SPLY OUTER CTMT ISO HDVO017 M-22HD01 B-7 2 A 2.0 GB MA Passive LC C AT-01 App-J Valve Name: RX HEAD DCON AUX STEAM SPLY IN CTMT ISO Page 173 Date:

Revision Date: 12119,2005 12t19/2005 Page 173

Callaway IST Program Plan Emergency Fuel Oil (JE) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

JEV0085 M-22JE01 H-5 3 C 2.0 CK SA Active SYS 0 CO M3 TP-05 Valve Name: EMERG F.O. DAY TK A IN CHECK JEV0086 M-22JE01 -5 3 C 2.0 CK SA Active SYS 0 CO M3 TP-05 Valve Name: EMERG F.O. DAY TK B IN CHECK Page 174 Revision Date:

Revision Date: 12/19(2005 12/1912005 Page 174

Callaway IST Program Plan Compressed Air (KA) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

KAFV0029 M-22KA01 B-1 2 A 2.0 GB AO Active 0 C AT-01 App-J BTC CS CSJ-26 FC CS CSJ-26 TP-04 PIT Y2 Valve Name: RX BLD INST AIR SPLY FLOW CTRL VLV KAV0039 M-22KA02 D-6 2 AC 4.0 CK SA Passive C C AT-01 App-Valve Name: RX BLD SERV AIR HDR SPLY CHECK KAV0118 M-22KA02 D-6 2 A 4.0 GB MA Passive LC C AT-01 App-J Valve Name: RX BLD SERV AIR HDR SPLY OUTER CTMT ISO KAV0204 M-22KA01 B-1 2 AC 1.5 CK SA Acdive SYS C AT-01 App-J CCL CM TP-08 COF CM TP-08 Valve Name: RX BLD INST AIR SPLY CHECK KAV0648 M-22KA05 G46 3 AC 0.75 CK SA Active SYS C AT-03 Y2 CC M3 CO OP TP-01 Valve Name: SG A AFW CTRL/MS ATMS RELIEF VLVS N2 SPLY ACC IN KAV0649 M-22KA05 F45 3 AC 0.75 CK SA Active SYS C AT-03 Y2 CC M3 CO OP TP-01 Valve Name: SG C AFW CTRLIMS ATMS RELIEF VLVS N2 SPLY ACC IN KAV0650 M-22KA05 D-6 3 AC 0.75 CK SA Active SYS C AT-03 Y2 CC M3 CO OP TP-01 Valve Name: SG B AFW CTRLUMS ATMS RELIEF VLVS N2 SPLY ACC IN 0AV0651 M-22KA05 B-5 3 AC 0.75 CK SA Active SYS C AT-03 Y2 CC M3 CO OP TP-01 Valve Name: SG D AFW CTRUMS ATMS RELIEF VLVS N2 SPLY ACC IN KAV0703 M-22KA05 H-7 3 C 0.75 RV SA Active C O/C RT Y10 Valve Name: SG A AFW CTRUMS RLF VLV N2 SPLY ACC PRESS REUEF Revision Date: 12/19/2005 Page 175

Callaway IST Program Plan Compressed Air (KA) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

KAV0704 M-22KA05 F-4 3 C 0.75 RV SA Active C O/C RT Y10 Valve Name: SG C AFW CTRUMS RLF VLV N2 SPLY ACC PRESS RELIEF KAV0705 M-22KA05 D-7 3 C 0.75 RV SA Active C O/C RT YIO Valve Name: SG B AFW CTRLUMS RLF VLV N2 SPLY ACC PRESS RELIEF KAVON76 M-22KA05 B-6 3 C 0.75 RV SA Active C O/C RT Y10 Valve Name: SG D AFW CTRUMS RLF VLV N2 SPLY ACC PRESS REUEF KAV0710 M-22KA05 H-8 3 C 0.75 RV SA Active C 0OC RT Y10 Valve Name: SG A AFW CTRUMS RLF VLV N2 SPLY ACC OUT RELIEF KAV0711 M-22KA05 F-7 3 C 0.75 RV SA Active C O/C RT Y10 Valve Name: SG C AFW STRUMS RLF VLV N2 SPLY ACC OUT RELIEF KAV0712 M-22KA05 D-8 3 C 0.75 RV SA Active C 0OC RT Y10 Valve Name: SG B AFW CTRL/MS RLF VLV N2 SPLY ACC OUT RELIEF

'AV0713 M-22KA05 B-7 3 C 0.75 RV SA Active C 0C RT Y10 Valve Name: SG D AFW CTRUMS RLF VLV N2 SPLY ACC OUT RELIEF Revision Date: 1211912005 Page 176

Callaway IST Program Plan Breathing Air for Tasks (KB) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

KBV0001 M-22K801 A-1 2 A 2.0 GB MA Passive LC C AT-01 AppJ Valve Name: BRTH AIR SYS IN CTMT ISO KBV0002 M-22KB0O A-2 2 A 2.0 GB MA Passive LC C AT-01 App-J Valve Name: BRTH AIR SYS OUT CTMT ISO 12/1920O5 Page 177 Date:

Revision Date: 12119/2005 Page 177

Callaway IST Program Plan Fire Protection (KC) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

KCHV0253 M-22KC02 B-6 2 A 4.0 GT MO Passive C C AT-01 App-J PIT Y2 Valve Name: F-PROT LOOP TO RX BLD OUTER CTMT DNSTRM ISO KCV0478 M-22KC02 B-6 2 AC 4.0 CK SA Active SYS C AT-01 App-J CCL CM TP-08 COF CM TP-08 Valve Name: FIRE PROT LOOP TO RX BLD IN CTMT CHECK Revision Date: . 12/19/2005 Page 178

Callaway IST Program Plan Standby Diesel Generator (KJ) Valve Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just Pos.

KJPVOO01A M-22KJ02 F-3 NC B 0.375 3W SO Active C 0 BTO M3 TP-05 Valve Name: DG A STARTING AIR SPLY PRESS CTRL VLV A KJPV0001B M-22KJ02 F-3 NC B 0.375 3W SO Active C 0 BTO M3 TP-05 Valve Name: DG A STARTING AIR SPLY PRESS CTRL VLV B KJPV0008 M-22KJ02 F4 NC B 3W SO Passive DE C BTC M3 TP-05 Valve Name: DG A FUEL RACK AIR SPLY PRESS CTRL VLV KJPVW101A M-22KJ05 F-3 NC B 0.375 3W SO Active C 0 BTO M3 TP-05 Valve Name: DG B STARTING AIR SPLY PRESS CTRL VLV A KJPV0101B M-22KJ05 F-3 NC B 0.375 3W SO Active C 0 BTO M3 TP-05 Valve Name: DG B STARTING AIR SPLY PRESS CTRL VLV B KJPV0108 M-22KJ05 F4 NC B 3W SO Passive DE C BTC M3 TP-05 Valve Name: DG B FUEL RACK AIR SPLY PRESS CTRL VLV KJV0711A M-22KJ02 C-2 NC C 0.75 CK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: DG STARTING AIR TK A SPLY CHECK KJV0711B M-22KJ05 B-2 NC C 0.75 CK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: DG STARTING AIR TK C SPLY CHECK KJV0712A M-22KJ02 D-5 NC C 0.75 CK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: DG STARTING AIR TK B SPLY CHECK KJV0712B M-22KJ05 D-5 NC C 0.75 CK SA Active SYS C CC M3 CO M3 TP-01 Valve Name: DG STARTING AIR TK D SPLY CHECK KJV0716A M-22KJ02 C-2 NC C 0.75 RV SA Active C O/C RT Y10 Valve Name: DG STARTING AIR TK A PRESS RELIEF KJV0716B M-22KJ05 C-2 NC C 0.75 RV SA Active C O/C RT Y10 Valve Name: DG STARTING AIR TR C PRESS RELIEF Revision Date: 12119/2005 Page 179

Callaway IST Program Plan Standby Diesel Generator (KJ) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Tett Relief Deferred Tech.

Valve Loca tion P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

KJV0717A M-22KJ02 C4 NC C 0.75 RV SA Active C O/C RT Y10 Valve Name: DG STARTING AIR TK B PRESS RELIEF KJV0717B M-22KJ05 C4 NC C 0.75 RV SA Active C O/C RT Y10 Valve Name: DG STARTING AIR TK D PRESS REUEF KJV0757A M-22KJ02 G-2 NC C 1.5 CK SA Active SYS 0 CC M3 TP-05 CO M3 TP-05 Valve Name: DG A ENGINE DR FIO PMP DISCH CHECK VLV KJV0757B M-22KJ05 G-2 NC C 1.5 CK SA Active SYS 0 CC M3 TP-05 CO M3 TP-05 Valve Name: DG B ENGINE DR F/O PMP DISCH CHECK VLV KJV0771A M-22KJ01 G-3 NC C 0.75 RV SA Active C O/C RT Y10 Valve Name: DG A JACKET WTR HTR OUT PRESS RELIEF KJV0771B M-22KJ04 G-3 NC C 0.75 RV SA Active C O/C RT Y10 Valve Name: DG B JACKET WTR HTR OUT PRESS RELIEF K(JV0773A M-22K101 F-3 NC C 1.5 CK SA Active SYS 0 CC M3 TP405 CO M3 TP-05 Valve Name: DG A JACKET WTR HTR OUT CHECK KJV0773B M-22KJ04 F-3 NC C 1.5 CK SA Active SYS 0 CC M3 TP-05 CO M3 TP-05 Valve Name: DG B JACKET WTR HTR OUT CHECK KJVO779A M-22KJ01 F-6 NC C 5.0 CK MA N/A SYS 0 CC M3 TP-05 CO M3 TP-05 Valve Name: DG A ENGINE DRIVEN JACKET WTR PMP DISCH CHECK Kj,0779B M-22KJ04 F-6 NC C 5.0 CK MA N/A SYS 0 CC M3 TP-05 CO M3 TP-5 Valve Name: DG B ENGINE DRIVEN JACKET WTR PMP DISCH CHECK KJV0818A M-22KJ03 C-3 NC C 2.0 CK SA Active SYS O/C CC M3 TP-05 CO M3 TP-05 Valve Name: DG A LUBE OIL FILTER OUT CHECK Revision Date: 12119/2005 Page 180

Callaway IST Program Plan

-Standby Diesel Generator (KJ) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&D Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

KJV0818B M-22KJ06 C-3 NC C 2.0 CK SA Active SYS O/C CC M3 TP-05 CO M3 TP-05 Valve Name: DG B LUBE OIL FILTER OUT CHECK KJV0820A M-22KJ03 C-3 NC C RV SA Active C 0 RT Y10 Valve Name: DG A AUX L-O PMP PRESS RLF VLV KJVW820B M-22KJ06 D-3 NC C RV SA Active C 0 RT Y10 Valve Name: DG B AUX LO PMP PRESS RLF VLV KJVW877A M-22KJ03 D-6 NC C RV SA Active C 0 RT Y10 Valve Name: DG A ENGINE DRIVEN L-O PMP PRESS RLF KJV0877B M-22KJ06 D-6 NC C RV SA Active C 0 RT Y10 Valve Name: DG B ENGINE DRIVEN L-0 PMP PRESS RLF Revision Date: 12/19/2005 Page 181

Callaway IST Program Plan Rx Bldg and Hot Machine Shop Floor and Equip Drain (LF) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just. Pos.

LFFV0095 M-22LF09 F-2 2 A 6.0 GT MO Active 0 C AT-01 App-J BTC M3 PIT Y2 Valve Name: CTMT NORM SMP PMPS DISCH HDR CTMT FV LFFV0096 M-22LF09 F-2 2 A 6.0 GB AO Adve C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: CTMT NORM SMP PMPS DISCH IIDR AUX BLD FCV LFHV0105 M-22LF03 C-5 3 B 6.0 GT MO Active 0 C BTC M3 PIT Y2 Valve Name: DRW SMPS DISCH HDR DNSTRUI HV LFHV0106 M-22LF03 C-5 3 B 6.0 GT MO Adve 0 C BTC M3 PIT Y2 Valve Name: DRW SMPS DISCH HDR UPSTRll HV Revision Date: 12/19/2005 Page 182

Callaway IST Program Plan Nuclear Sampling (SJ) Valve Table P&ID Safety Valve Act Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat Size Type Type Passive Position Position Type Freq. Request Just. Pos.

SJHVOOO5 M-22SJ04 F-4 2 A 1.0 GB SO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: PASS HOT LEG I SAMP IN CTMT DNSTRM ISO HV SJHVY006 M-22SJ04 F-4 2 A 1.0 GB SO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: PASS HOT LEG I SAMP OUT CTMT ISO TRN A HV SJHV0012 M-22SJ01 F-7 2 A 1.0 GB SO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: PZR VAPOR SAMP IN CTMT ISO HV SJHV0013 M-22SJ01 E-7 2 A 1.0 GB SO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: PZR VAPOR SAMP OUT CTMT ISO HV SJtfivail M-22SJ01 G-3 2 A 1.0 GB SO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: ACC SAMP IN CTMT ISO HV "4Y0019 M-22SJ01 F-3 2 A 1.0 GB SO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: ACC SAMP OUT CTMT ISO HV Revision Date: 12/19/2005 Page 183

Callaway IST Program Plan Nuclear Sampling (SJ) Valw Table P&ID Safety Valve Act. Active I Normal Safety Test Test Relief Deferred Tech.

Valve Location P&ID Coor. Class Cat. Size Type Type Passive Position Position Type Freq. Request Just Pos.

SJHV0127 M22SJ04 F-6 2 A 1.0 GB SO Active C C AT-41. AppJ BTC M3 FC W TP-04 PIT Y2 Valve Name: PASS HOT LEG I SAMP OUT CTMT ISO TRN B.HV SJHV0128 M-22SJ04 H-6 2 A 1.0 GS SO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: PASS PZR & RCS SAMP IN CTMT ISO HV SJHVC129 W22SJ04 H-5 2 A 1.0 GB SO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: PASS PZR & RCS SAMP OUT CTMT ISO TRN B HV SJHV0130 M-22SJ04 G-5 2 A 1.0 GB SO Active C C AT-01 App-J BTC M3 FC M3 TP-04 PIT Y2 Valve Name: PASS PZR & RCS SAMP OUT CTMT ISO TRN A HV Revision Date: 121191200S Page 184