Text

Inservice Testing Program, Fourth Ten-Year Interval Update
	ML052210081
Person / Time
Site:	Duane Arnold
Issue date:	08/01/2005
From:	Vanmiddlesworth G; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NG-05-0427
	Download: ML052210081 (144)
	v • d • e

NM Committed to Nuclear Excellence Duane Arnold Energy Center Operated by Nuclear Management Company, LLC August 1, 2005 NG-05-0427 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 Inservice TestinQ ProQram, Fourth Ten-Year Interval Update The Duane Arnold Energy Center (DAEC) Inservice Testing (IST) Program third ten-year interval will end on January 31, 2006. In accordance with 10 CFR 50.55a(f),

Nuclear Management Company, LLC (NMC) has updated the DAEC IST Program for the fourth ten-year interval. The IST Program for the fourth interval has been developed to the ASME Code for Operation and Maintenance of Nuclear Power Plants, 2001 Edition through 2003 Addenda. The updated IST Program is enclosed.

Requests for relief, included in this Program, are submitted for NRC review and approval in accordance with 10 CFR 50.55a. Approval is requested prior to the start of the fourth ten-year interval on February 1, 2006.

Gary Van Middlesworth Site Vice President, Duane Arnold Energy Center Nuclear Management Company, LLC Enclosure cc: Administrator, Region III, USNRC Project Manager, DAEC, USNRC Resident Inspector, DAEC, USNRC 3277 DAEC Road

Palo, Iowa 52324-9785 / Q Telephone: 319.851.7611 I l

ENCLOSURE to NG-05-00427

DAEC Station 4n' Interval Inservice Testing Program FOURTH TEN- YEAR INTERVAL PUMP AND VALVE INSERVICE TESTING PROGRAM FOR Duane Arnold Energy Center Commercial Service Date: February 1, 1975 (Docket no. 50-331) 3277 DAEC Road Palo, Iowa 52324 Revision 0 (Section 1 Page 1)

DAEC Station 4TH Interval Inservice Testing Program 1.0 INSERVICE TESTING PROGRAM PREPARATION AND APPROVAL Prepared By: Date: ?/Zz or Inservice Testi g Engineer/Specialist Reviewed By: 'tdate ia Date: 7-4?1o-a 1 upervisor I ec Materials Reviewed By: Date: 7/4C/o65

,ogram Engineering Concurred By: :- Date: -7, 6/ S Plperations Committeea Ie2 /

Approved By: 140, Plant Manager; Nuclear 43 Date:

Revision 0 (Section 1 Page 2)

DAEC Station 4n' Interval Inservice Testing Program 2.0 TABLE OF CONTENTS Section Number And Description 1.0 Inservice Testing ProgramPreparationandApproval 2.0 Table Of Contents 3.0 Revision Summary Sheet 4.0 Introduction andProgramDescription 5.0 Pump Testing ProgramDescription 6.0 Inservice Testing ProgramPump List 7.0 PumpReliefRequests 8.0 Valve Testing ProgramDescripton 9.0 Inservice Testing Program Valve List 10.0 Valve Relief Requests 11.0 Deferred Test Justifications- Valves 12.0 REFERENCEDOCUMENTS Revision 0 (Section 2 Page 1 of 1)

DAEC Station 4n' Interval Inservice Testing Program 3.0 REVISION

SUMMARY

SHEET Section Effected Pages Revision Date 1 0 2 0 3 0 4 0 5 0 76 0 8 0 9 0 10 0 11 __0 12 0 13 0 15 __0 16 __0 17 __0 Revision 0 (Section 3 Page 1 of 1)

DAEC Station 4n' Interval Inservice Testing Program

4.0 INTRODUCTION

AND PROGRAM DESCRIPTION 4.1 Introduction Under the provisions of 10 CFR 50.55a, inservice testing of safety related pumps and valves will be performed in accordance with the ASME Code for Operation and Maintenance of Nuclear Power Plants. As specified in 10 CFR 50.55a(b) (10- 1-04 edition),

the effective edition of OM Code with regard to this program is the 2001 Edition through 2003 addendum. This program identifies the pump and valve inservice testing that will be performed at Duane Arnold Energy Center to comply with the requirements of 10 CFR 50.55a.

This program applies to the IST Fourth Ten Year Interval beginning February 1, 2006 and ends on January 31, 2016. Note the Duane Arnold Energy Center's ISI program Third Ten Year Interval began on November 1, 1996 and will end on October 31, 2006.

4.2 Relationship with Technical Specifications Based on technical specification requirements, in the event of any conflicts between ASME OM requirements and the requirements of technical specifications, the plant technical specifications shall govern if more conservative. Duane Arnold Energy Center will meet all requirements of both ASME OM and plant technical specifications unless there is a specific conflict between the two. If any requirements of ASME OM cannot be met due to technical specification limitations, relief will be requested, or appropriate technical specification changes will be prepared.

4.3 Qualification of Test Personnel Personnel performing pump and valve testing per ASME OM, will be qualified in accordance with the Duane Arnold Energy Center's Quality Assurance Program.

4.4 Program Development Inservice testing (IST) of Class 1, 2, and 3 components is performed at Duane Arnold Energy Center in accordance with the provisions of 10 CFR 50.55a, "Codes and Standards". Where possible, testing is performed which at a minimum meets the requirements of the latest Code edition and addenda adopted in 10 CFR one year prior to the start of the current interval.

The scope of the program is that defined by subsection ISTA-1 100(a) and ISTA-1 100(b) of 2001 Edition through 2003 addendum of ASME OM code. ISTA(c) which, covers dynamic restraints (snubbers) will not be included in the IST program. 10 CFR50.55a required the use of the previously mentioned ASME OM edition and addenda, which will here-in be referred to as the Code.

In accordance with the Code, the following are required to be included in the testing program:

Pumps and Valves that are required to perform a specific function in:

1) Shutting down the reactor to the cold shutdown condition;

2) Maintaining the cold shutdown condition; or

3) Mitigating the consequences of an accident.

Pressure relief devices that protect systems or portions of systems which perform one or more required function in:

1) Shutting down the reactor to the cold shutdown condition;

,Revision 0 (Section 4 Page 1 of 3)

DAEC Station 4n' Interval Inservice Testing Program

2) Maintaining the cold shutdown condition; or

3) Mitigating the consequences of an accident.

In addition to the general Code requirements outlined above, there are other interpretations and positions that have come about as a result of past regulatory and licensee actions as listed in Section 4, References.

4.5 Initial Program Scope In the course of developing the Program scope, each of the significant safety systems (included within the ISI-class boundaries) were evaluated with respect to the function of each component and the need for its operability as it relates to the scope of the OM Code.

Supporting documents used include, Final Safety Analysis Report (FSAR);

Technical Specifications; Past program correspondence; Operating Procedures (Normal, Emergency and Off-Normal); and Plant System Descriptions.

The sequence followed during the development effort was as follows:

I. Each of the plant systems was subjected to an overview to determine any potential active safety function as described in the scope statement. Those systems with no obvious safety functions were then excluded from further consideration. Plant documents as well as operating staff inputs were utilized in this phase.

2. For the remaining systems, flow diagrams were studied and any component that could possibly have an active or passive safety function (other than simply maintaining the pressure boundary) were identified for further evaluation.

3. The function of each component identified in 2, above, was determined based on available documentation, staff input or general experience of the evaluator. Testing requirements were derived based on the component fuinction(s) and the applicable rule(s).

4. Available documents were reviewed and specific or implied component operational requirements were compared to the information derived in 3, above.

5. The results of Steps I through 4, above, were reviewed by several knowledgeable members of the plant staff and evaluated for accuracy and consistency. Based on this review, the final program scope was derived and the IST Program Plan developed.

4.6 Program Update During the fouth 10-year interval it is expected that the scope of the Program will occasionally be modified in response to unrelated activities including, but not limited to:

1) Plant design changes;

2) Changes in operating conditions (e.g. normal valve lineup);

3) Changes in accident mitigating procedures philosophy.

As a result, it is expected that the IST Program may be revised to ensure continued compliance with the Code requirements relating to the scope of the test program.

The procedures controlling the plant design change development process contain requirements to conduct a review for determination of potential impact on the IST Program.

If the results of that review indicate the potential for impact on the IST Program, the change Revision 0 (Section 4 Page 2 of 3)

DAEC Station 4 T"1 Interval Inservice Testing Program package shall be submitted to IST Engineer/Specialist for review. Additionally, the plant administrative procedures which control changes to plant documents, including procedures, require that changes potentially effecting the IST Program be reviewed by the IST Engineer/Specialist. Should a change require a program revision, the IST Engineer/Specialist would then implement the change to the program plan and the appropriate test procedure(s) in a timely manner.

Revision 0 (Section 4 Page 3 of 3)

DAEC Station 4n' Interval Inservice Testing Program 5.0 PUMP TESTING PROGRAM DESCRIPTION 5.1 Code Compliance This IST Program for pumps meets the requirements of Reference 12.8, subsection ISTB and any applicable interpretations or additional requirements imposed by Reference 12.9.

Paragraph and table references in this section refer to specific paragraphs and tables in Reference 12.8. Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a(f)(5)(iii) and 12.9 (See Section 6).

The 10 CFR 50.55a specification of Class 1,2, and 3 components has been used as criteria for including pumps in this program. Non-class pumps judged important to safety are also listed. Testing of non-class pumps will be performed in accordance with Reference 12.8, subsection ISTB to the extent practical. Relief requests will not be submitted for non-class pumps if the Code requirements cannot be met.

5.2 Allowable Ranges of Test Quantities The allowable ranges for test parameters as specified in Reference 12.8, subsection ISTB, Table ISTB-3500-1 will be used for all measurements of pressure, flow, and vibration except as provided for in specific relief requests for Class 1, 2, and 3 pumps. Allowable ranges for test parameters of non-class pumps will be as specified in Reference 12.8, subsection ISTB, Table ISTB-3500-1 to the extent practical.

5.3 Testing Intervals The test frequency for pumps included in the Program will be as set forth in Reference 12.8, subsection ISTB-3400, Reference 12.9, Paragraph 5.1.2, and related relief requests.

An allowable extension, not to exceed +25 percent of the surveillance interval, may be applied to a test schedule as allowed by the Duane Arnold Energy Center Technical Specifications to provide operational flexibility. Note the +25 percent surveillance interval may be applied to testing frequencies doubled as required by Reference 12.8, subsection ISTB-6200, to also provide operational flexibility, as this surveillance interval was added to DAEC's improved technical specifications.

5.4 Pump Program Tables Section 6 lists those pumps included in the IST Program with references to parameters to be measured and applicable requests for relief. The drawing coordinate column contains 4 digit alphanumeric codes, which help locate the component on the flow diagram. The first number is the vertical column the component is illustrated in. The second number represents a further subdivision of that column by 10. The third digit is a letter representing the horizontal column. The fourth digit subdivides that column by 10. Thus 65A6 would be 5/1O's into vertical column 6 and 6/1O's into horizontal column 'A'.

5.5 Relief Requests for Pump Testing Relief requests are initiated per 10 CFR 50.55a where appropriate and are included in Section 7.

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DAEC Station 4 TH Interval Inservice Testing Program 6.0 INSERVICE TESTING PROGRAM PUMP LIST Parameters Pump Name P&ID Coord Group Safety S P dP F V Notes Class IP022A RHR SERVICE 146 86AI A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 WATER PUMP IP022B RHR SERVICE 146 61AI A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 WATER PUMP IP022C RHR SERVICE 146 80AI A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 WATER PUMP IP022D RHR SERVICE 146 56AI A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 WATER PUMP I P099A EMERGENCY 146 73AI A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 SERVICE WATER PUMP I P099B EMERGENCY 146 68A1 A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 SERVICE WATER PUMP IP1 17A RIVER WATER 129 74C3 A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 SUPPLY PUMP IP117B RIVER WATER 129 47C3 A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 SUPPLY PUMP IP1 17C RIVER WATER 129 64C3 A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 SUPPLY PUMP IP1 17D RIVER WATER 129 37C3 A 3 N/A N/A Q/2Y Q/2Y Q/2Y 1,2 SUPPLY PUMP IP211A CORESPRAY 121 35CI B 2 N/A N/A Q/2Y Q/2Y 2Y PUMP IP211B CORE SPRAY 121 49CI B 2 N/A N/A Q/2Y Q/2Y 2Y I PUMP IP216 HPCI PUMP 123 24D0 B 2 Q/2Y N/A Q/2Y Q/2Y 2Y PR-01 IP226 RCIC PUMP 125 47C8 B N Q/2Y N/A Q/2Y Q/2Y 2Y 3 1P229A RHR PUMP 120 42A7 A 2 N/A N/A Q/2Y Q/2Y Q/2Y I I P229B RHR PUMP 119 68A6 A 2 N/A N/A Q/2Y Q/2Y Q/2Y I IP229C RHR PUMP 120 29A9 A 2 N/A N/A Q/2Y Q/2Y Q/2Y IP229D RHR PUMP 119 82A6 A 2 N/A N/A Q/2Y Q/2Y Q/2Y I IP230A SBLC 126 54CI B 2 N/A Q/2Y N/A Q/2Y 2Y I INJECTION PR-02 PUMP Revision O (Section 6 Page 1 of 2)

DAEC Station 4n' Interval Inservice Testing Program Parameters Name P&ID Coord Group Safety S P dP F V

_ _ ___ _ ___ __ ___ ___ C lass_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

OB SBLC 126 53B3 B 2 N/A Q/2Y N/A Q/2Y 2Y INJECTION PR-O0 PUMP LEGEND FOR PUMP TABLES PUMP NO / Pump name indicated on the respective flow diagram, and description.

NAME P&TD Pump Drawing Number Dwg Coor Flow Diagram drawing coordinates for the pump. See Section 5.4 for further information on how to interpret the 4 alphanumeric characters.

Group Group classification of each pump.

Safety Class ISI Classification of the pump.

Parameters The table indicates whether a test parameter is measured and at what frequency as well as any applicable Relief Requests. The abbreviations refer as follows:

S - Speed V - Vibration P - Discharge Pressure N/A - Not applicable, or not obtained dP - Differential Pressure Q - quarterly F - Flow Rate 2Y - once every two years Notes I. This pump is driven by a squirrel-cage induction motor operating at essentially constant speed; therefore, speed measurements are not required.

2. The value of suction pressure used to calculate pump differential pressure is derived indirectly from a measurement of pump submergence beneath the surface of liquid in a pit or tank.

3. This pump is located outside of the ISI-code boundaries. Testing of this pump will be performed in accordance with the Code to the extent practical. Relief requests will not be submitted for this pump if the Code requirements cannot be met.

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DAEC Station 4 T11 Interval Inservice Testing Program 7.0 PUMP RELIEF REQUESTS Revision 0 (Section 7 Page 1 of 5)

DAEC Station 4TH Interval Inservice Testing Program Pump Relief Request - PR-O 1 Proposed Alternative Limits for HPCI Pump Vibration In Accordance with 10 CFR 50.55a(a)(3)(ii)

Svstems: High Pressure Coolant Injection PUMP: IP216 HIGH PRESSURE COOLANT INJECTION PUMP Class: 2 Function: Injects Coolant into the reactor vessel independent of AC power.

Test Requirement: Table ISTB-5100-1; Comprehensive pump test vibration alert limit of 0.325 in/sec Bases for Relief:

The HPCI pump consists of a centrifugal main pump, a separate centrifugal booster pump, a speed reducing gear for the booster pump, and a Terry drive train. Therefore , there are four independently balanced and aligned rotating assemblies that are coupled together. As a result, the normal (baseline) vibration readings in the horizontal direction on the main pump is approximately 0.4 in/sec. Application of a 0.325 in/sec alert limit would require DAEC to enter accelerated test frequency each time the pump was tested because one or more of these points measured would exceed this limit.

Prior to the fourth ten-year interval, pump vibration was measured in displacement instead of velocity. DAEC has determined measuring pump vibration in velocity for this pump train will provide improved ability to detect degradation, since the normal pump speed is approximately 3600 rpm. DAEC has many years of in-service test data showing that baseline vibrations of 0.4 in/sec represent acceptable pump operation and that vibration levels have not been trending up.

DAEC has had these vibration levels analyzed by an Engineering consultant that specialized in vibration analysis. Their analysis shows that this pump can operate at vibration levels up to 0.700 in/sec.

Implementing the alert limit of 0.325 in/sec would require DAEC to constantly have the HPCI pump on accelerated test frequency. The intent of increased test frequency is to closely monitor a pump that is deteriorating from its baseline values. In this case, the pump would be operating at its normal vibration range and no change would be seen. The additional annual test would require a significant amount of time and resources and only create additional maintenance due to normal wear of the system. Modifications to try and reduce the vibration levels, such as installing new shafts and impellers, are extremely expensive and may not reduce the vibration levels.

Therefore, requiring an alert limit of 0.325 in/sec on the HPCI pump is an extreme hardship without a compensating increase in public safety. An appropriate alert limit for these vibration data points is 0.500 in/sec. This is based on previous test history, a review of industry data and at the vibration analysis performed.

Revision 0 (Section 7 Page 2 of 5)

DAEC Station 4 T1 Interval Inservice Testing Program Relief is requested in accordance with 10 CFR 50.55a(a)(3)(ii). Compliance with the specified code requirements of the listed sections Would result in a hardship without a corresponding increase in the level of quality or safety.

Alternative Testing:

A vibration alert limit of 0.500 in/sec will be used for the pump horizontal vibration data points.

Table ISTB-5 100-1 required action limit of 0.700 in/sec would be adhered to.

Status:

This is a new relief Request for DAEC. Monticello has a similar relief previously granted by the NRC.

Re-vision 0 (Section 7 Page 3 of 5)

DAEC Station 4 n' Interval Inservice Testing Program Pump Relief Request - PR-02 Proposed Alternative for SBLC Pump Vibration Instruments In Accordance with 10 CFR 50.55a(a)(3)(i)

Systems: Standby Liquid Injection PUMP: IP230A AND IP230B STANDBY LIQUID CONTROL INJECTION PUMPS Class: 2 Function: To inject liquid poison into the reactor.

Test Requirement: ISTB-35 10(e); General, Frequency Response Range; The frequency response range of the vibration measuring transducers and their readout system shall be from one-third minimum pump shaft rotational speed to at least 1000 Hz.

Bases for Relief:

The nominal shaft rotational speed of these pumps is 242 RPM which is equivalent to approximately 4 Hz. Based on this frequency and Part 6, Para. 4.6.1.6, the required frequency response range of instruments used for measuring pump vibration is 1.33 to 1000 Hz.

Procurement and calibration of instruments to cover this range to the lower extreme (1.33 Hz) is impractical due to the limited number of vendors supplying such equipment and the level of sophistication and cost of the equipment.

These are of a simplified reciprocating (piston) positive displacement design with rolling element bearings, Model Number TD-60, manufactured by Union Pump Corporation. Union Pump Corp.

has performed an evaluation of the pump design and has determined that there are no probable sub-synchronous failure modes associated with these pumps under normal operating conditions.

Furthermore, there are no known failure mechanisms that would be revealed by vibration at frequencies below that related to shaft speed (4 Hz); thus no useful information is obtained below this frequency nor will indication of pump degradation be masked by instrumentation unable to collect data below this frequency.

The requirement to measure vibration with instruments with response to 1/3 shaft speed stems from the need to detect oil whip or oil whirl associated with journal bearings. In the case of these pumps, there are no journal bearings to create these phenomena, thus satisfying the frequency response range criteria would serve no significant purpose. The significant modes of vibration with respect to equipment monitoring are as follows:

1-Times Crankshaft Speed - An increase in vibration at this frequency may be an indication of rubbing between a single crankshaft cheek and rod end, cavitation at a single valve, or coupling misalignment.

Revision 0 (Section 7 Page 4 of 5)

DAEC Station 4e' Interval Inservice Testing Program

2-Times Crankshaft Speed - An increase in vibration at this frequency may be an indication of looseness at a single rod bearing or crosshead pin, a loose valve seat in the fluid cylinder, a loose plunger/crosshead stub connection, or coupling misalignment.

Other Multiples of Shaft Speed - An increase in vibration at other frequencies may be indications of cavitation at several valves, looseness at multiple locations, or bearing degradation.

Based on the foregoing discussion, it is clear that monitoring pump vibration within the frequency range of 4 to 1000 Hz will provide adequate information for evaluating pump condition and ensuring continued reliability with respect to the pumps' function. Compliance with the Code requirement would result in a significant hardship and cost without any compensating increase in

,pump performance or plant safety.

Alternative Testine:

Vibration levels of the Standby Liquid Control Pumps will be measured in accordance with the applicable portions of Part 6, Paragraph 4.6 with the exception of the lower frequency response limit for the instrumentation (Para. 4.6.1.6). In this case the lower response limit of the vibration measuring equipment will be 4.03 Hz or less.

Status:

Approval of similar relief was previously granted to DAEC by the NRC in May 29,1997.

Revision 0 (Section 7 Page 5 of 5)

DAEC Station 4n' Interval Inservice Testing Program 8.0 VALVE TESTING PROGRAM DESCRIPTON 8.1 Code Compliance This IST Program for valves meets the requirements of Reference 12.8, subsection ISTC, Mandatory Appendix I and any appropriate interpretations or additional requirements imposed by Reference 12.9. Paragraph and table references in this section refer to specific paragraphs and tables in Reference 12.8. Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a(f)(5)(iii) and Reference 12.9.

Non-class valves judged important to safety are also listed. Testing of non-class valves will be performed in accordance with Reference 12.8, subsection ISTC and Mandatory Appendix 1,to the extent practical. Relief requests will not be submitted for non-class valves if Code requirements cannot be met.

8.2 Stroke Time Acceptance Criteria When required, the acceptance criteria for the stroke times of power-operated valves will be as set forth in Reference 12.8 subsection ISTC.

83 Check Valve Testing Where required, full-stroke exercising of check valves to the open position using system flow requires that a test be performed whereby the predicted full accident condition flow through the valve be verified and measured or full stroke of the obturator is verified by appropriate methods as discussed in ISTC-5220.

8.4 Testing Intervals The test frequency for valves included in the Program will be as set forth in Reference 12.8, subsection ISTC-35 10 and Mandatory Appendix 1. An allowable extension, not to exceed +25 percent of the surveillance interval, may be applied to the test schedule as allowed by the Duane Arnold Energy Center Technical Specifications to provide operational flexibility, except for the relief valve sample testing schedules discussed in Mandatory Appendix I of Reference 12.8.

8.5 Valve Program Tables Section 10 lists those valves included in the IST Program along with references to ISI Class, required testing, respective test intervals, applicable requests for relief as well as other relevant information. A table legend at the end of Section 9 provides information on how to use the drawing coordinates to help locate valves on flow diagrams.

8.6 Deferred Testing Where quarterly testing of valves is impractical or otherwise undesirable, testing may be deferred and performed during cold shutdown or refueling periods as permitted by Reference 12.8, subsections ISTC-3521 and ISTC-3522. The valve program table identifies those valves to which deferred testing applies and the respective deferred test justification for each is provided in Section 12.

8.7 Relief Requests for Valve Testing Relief Request VR-0 I associated with valve testing is provided in Section 10.

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9.0 DAEC UNIT 1 INSERVICE TESTING PLAN - VALVE TABLES Drawinrg: 11)3 Slreet #: I

Description:

lAfain.Stenmt Trurhine.Stop ndm Co~ntrol Valves Valve Dwg Safety Vlv Act Norm Safety Valve Detscription Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV1064 451F4 2 n 2 GI, AO C/FO0 A O BTO CS DTJ-01 FST CS DTJ-01 PIT 2Y MAIN STEAMSI DRAIN ISOLATION TO CONDENSER i601043 86E0 2 B 3 GL MtO C A 0 BTO CS DTJ-01 PIT 2Y MAIN STEAM DRAIN LINE ISOLATION M101044 83A4 Y n 3 GL MO C A 0 BTO CS DTJ-01 3 PIT 2Y 3 DRYWELL STEAI LINE DRAINS CONDENSER ISOLATION 01054 -- 81F9 2 B 6 GA MIO 0 A C BTC CS DTJ-03 PIT 2Y MSR I E-1811 2ND STAGE REIIEAT STEAM SUPPLY M01055 83F7 2 B 6 CA MO 0 A C BTC CS DTJ-03 PIT 2Y MSR I E-18A 2ND STAGE REIIEAT STEAM SUPPLY M01362A 71E9 2 n 3 GA MIO 0 A C BTC CS DTJ-04 PIT 2Y

,%SIL"A" SUPPLY TO OFFGAS AND SJAE

-%013622 70E5 2 B 3 GA MIO 0 A C BTC CS DTJ-04 PIT 2Y MfSL"B" SUPPLY TO OFFGAS AND SJAE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page I of 87

Drawing: 104 Sheet #: I

Description:

Turhitte Steam Seals Valve Dwg Safety VIv Act Norm Satety Valve Delcription Coor Class Cat. Size Type Type Pos AP Position Test Freq RR DJT Remarks M01169 69C1 2 B 3 GA MO 0 A C BTC Cs DTJ-02 PIT 2Y TURBINE STEAM SEAL MAIN STEAMI SUPPLY ISOLATION M01170 72C2 2 B 3 GA MO C A C BTC CS DTJ-02 PIT 2Y TURBINE STEAMI SEAL PRESS REGULATOR BYPASS VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 2 of 87

Drawving: 1/79 Shteer #: I

Description:

Condtenvate and Dentiteralized1Vater.S7voemw Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Typie Pos AIP Position Test Freq RR DJT Remarks V09-OO65 33E9 2 A I GA ,%I LC P C AT-I AJ DEMIN WATER SUPPLY TO DRYWELL V09-01 11 27E9 2 A I CA %I LC P C AT-I AJ DRYWELL DEMIN WATER SUPPLY IIDR ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 3 of 87

i Drawing: 112 Sheet #: I

Description:

Reactor Bruildinty Cooling Water Smsien, Valve Dwg Safety Vlv Act Norm Safety l Valve Description Coor Class Cat. Si7e Type Type Pos A/P Position Test Freq RR DJT Remarks N104841A 38D6 2 A 4 GA MO 0 A C AT.I AJ BTC Cs DTJ-07 PIT 2Y DRYWELL RBCCW RETURN HEADER ISOLATION N104841 B 38D7 2 A 4 GA MO 0 A C AT-I AJ BTC CS DTJ-07 PIT 2Y DRYWELL RBCCW SUPPLY HEADER ISOLATION PSV4842 24E5 N C 0.75 RV SA C A O/C CT-SP IOY2 16,3 DN EQUIP DRAIN SUMP IIX IE-34 TUBE SIDE RELIEF IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 4 of 87

Draving: 113 Sheet #: I

Description:

RIIR Service Water & Eynerzencv Service Vater System Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV1956A 31E9 3 B 4 GA AO C/FO A 0 BTO Q 12 FST QI CB CHILLER IV-CII-IA DISCII TO ESWV ISOLATION CV1956iB 17E9 3 B 4 GA AO C/FO A 0 llTO Q 12 FST Q Cll CHILLER IV-CII-IB DISCII TO ESWV ISOLATION CV2080 57F3 3 r 6 GL AO C/FO A 0 BTO Q 12 FST Q SBDG G1(-31 COOLER IE-53A ESW SUPPLY ISOLATION CV2081 59E7 3 B 6 GL AO C/FO A 0 BTO Q 12 FST Q I SII)G IG-21 COOLER IE-53B ESWV SUPPLY ISOLATION M01942 85D9 2 n 12 GA MNO C P C PIT 2Y RIIR SERVICE WATER CROSS- TIE TO RIIR SYSTEM

%101943A 85E9 3 n 12 GA 10 C/KL P C PIT 2Y RIIRSW PUMPS IP-22A/C CROSS-TIE TO RIIR

,%101943B 79F1 3 B 12 GA MTO CIKL P C PIT 2Y RIIRSW PUNPS IP-22B/D CROSS-TIE TO RIIR M01947 69C0 3 B 16 GA MO0 C A 0 BTO Q PIT 2Y RIMR IIX IE-201B SERVICE WVATER OUTLET ISOLATION

-M01998A 71AS 3 B 16 BTF MO 0 P 0 PIT 2Y ESW/RIIRSW A LOOPS RETURN TO COOLING TOWERS

-M01998T- 71B4 3 B 16 lBTF_ MO1 0 P 0 PIT 2Y ESWIRIIRSW B LOOPS RETURN TO COOLING TOWERS 02039A - -- 42F6 3 B 4 GA M1O 0 A C BTC Q PIT 2Y Cn CHILLER IV-CII-IA WELL WATER SUPPLY ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 5 of 87

Drawing: 113 Sheet fi: I

Description:

RIMR Service Water & Emnerg'ency' Service Water Ststent Valve Dwg Satety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pas AIP Position Test Freq RR DJT Remarks M%02039B 271F6 3 B 4 GA MO 0 A C BTCQ PIT 2Y CB CMILLER IV-CII-I B WVELL WATER SUPPLY ISOLATION M102046 57C3 3 II 16 GA MIO C A 0 BTO Q PIT 2Y RiIR IIX I E-201A SERVICE WATER OUTLET ISOLATION M02077 331F6 3 GA MO 0 A C BTC PIT 2 CHILLER IV-CII-IA DISCII TO WELL WTR ISOLATION M02078 18176 3 GA GA4 MO 0 A C BTCQ PIT 2 CHILLER IV-CII-I B DISCII TO WELL WTR ISOlATION P5V1988 73C9 3 C 0.75 RV SA C A- OIC CT-SP I0Y2 16 RIMR IIX I E-201 B TUBE SIDE (RIlRSW) PRESSURE RELIE PSV2068 62D2 3 C 0.75 RV SA C A OIC CT-SP I 0Y2 16 R I IR I IX I E-2 0 1A T UBE SI DE (R I IRSW) PR ESS RE LIE F V'13-0036 29F1 3 C 4 CK SA SYS A 0 CT-CC Q CT-CO Q IV'-Ch-111 ESW SVPPLY HIEADER CIIECK V'ALVE V13-0051 44F'1 3 C 4 CK SA SYS A 0 CT-CC Q CT-CO0 IV-CII-IA ESW~ SUPPLY HEADER CHECK VALVE V1I3-0121 27F1 3 C I CK SA SYS A 0 DSBY RI DTJ-19 AIR CONIP IK-4/1K-3 'i' ESWV/WW INLET CHECK VALVE V13-0126 42F1 3 C I CK SA SYS A 0 DSBY RI DTJ-19 AIR COMP IK-3IIK-4'A' ESWIWVW INLET CHECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section Scin9Pg9 Page 6 off8 87

I Drawing: 1i1 Sheet #: I1

Description:

Nuclear BRiler Srsteti Valve Dwg Safety VIv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV4412 32E0 I A 20 GL AO O/FC A C AT-I AJ BTC Q FST QIR DT.1-05 PIT 2Y "A" MAIN STEAM LINE INBOARD ISOLATION CV4413 25E0 I A 20 GL AO O/FC A C AT-I AJ BTC Q FST QIR DTJ-05 PIT 2Y "A" MAIN STEAMI LINE OUTBOARD ISOLATION CV4415 74CI I A 20 CL AO O/FC A C AT-I AJ BTC Q FST QIR DTJ-05 PIT 2Y "B" MAIN STEAM LINE INBOARD ISOLATION CV4416 82CI I A 20 GI, AO O/FC A C AT-I AJ BTC Q FST Q/R DTJ-05 PIT 2Y "B" MIAIN STEAM LINE OUTBOARD ISOLATION CV4418 31C2 I A 20 CL AO O/FC A C AT-I AJ BTC Q FST Q/R DTJ-05 PIT 2Y "C" M\IAIN STEA.MI LINE INBOARD ISOLATION CV4419 24C2 I A 20 GL AO O/FC A C AT-I AJ BTC Q FST Q/R DTJ-05 PIT 2Y "C" MAIN STEAMN LINE OUTBOARD ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 7 of 87

Drawsing: 114~ Sheet #: I

Description:

Nuclear Boiler Svyteni Valve esrpinDwg Satety Viv Act Norm Safety VleDsrpinCoor Class Cat. Size Type Type Pos AlP Position Test Freq RR DJT Remarks CV4420 74D8 I A 20 CL AO OIFC A C AT-I AJ BTC Q FST QIR DTJ-05 PIT ZY "D"'%MAIN STEAM%LINE INBOARD ISOLATION CV4421 82D)8 I A 20 GIL AO O/FC A C AT-I AJ IBTC Q FST Q/R DTJ-05 PIT 2Y "D" MAIN STEAM LINE OUTBOARD ISOLATION CV4428 641F2 I B 0.5 GI, AO C P C PIT 2Y REACTOR VESSEL HEAD VENT ISOLATION CV4429 71 F2 I B 0.5 GCL AO C P C PIT 2Y REACTOR VESSEL HIEAD VENT ISOLATION M0(4423 37A8 I A 3 GA IMO 0 A C AT-I AJ BTC Q PIT 2Y MAIN STEAM LINE DRAIN INBOARD ISOLATION M04424 34A8 I A% 3 CA MO 0 A C AT-I A.J BTC Q PIT 2Y MAIN STEAM,% LINE DRAIN OUTBOARD ISOLATION M04441 34A5 I A/C 16 SCK MO O/KL A C AT-I AJ 6 BTC Cs DTJ-27 CT-CC R DTJ-27 CT-CO R* DTJ-27 4 PIT 2Y RX FEEDWATER LOOP A INLET STOP CIIECK 1ST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 8 of 87

Drawing: 114 Sheet #: I

Description:

Nuclear RollerSystem Valre Dwg Sarety Vlv Act Norm Safety Description Calve Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks M104442 72n1 1 AIC 16 SCK 'MO OIKL A C AT-i AJ 6 BTC CS DTJ-27 CT-CC R DTJ-27 CT-CO R* DTJ-27 4 PIT 2Y RX FEEDWATER LOOP n INLET STOP CHECK PSV4400 47El I m/C 6 RV SAP C/KL A o/C CT-SP 5Y 14 MAIN STEAM LINE A ADS RELIEF VALVE PSV4401 42EI I I/C 6 RV SAP C/KL A o/C CT-Sr 5Y 14 MAIN STEAM LINE A LLS RELIEF VALVE PSV4402 62C2 I B/C 6 RV SAP C/KL A o/C CT-SP sY 14 MAIN STEAM LINE r ADS RELIEF VALVE PSV4403 66C2 I C 6 SV SA C A o/C CT-SP 5Y MAIN STEAIM LINE BISAFETY RELIEF VALVE PSV4404 47C3 I C 6 SV SA C A o/C CT-Sr sY MAIN STEAM LINE C SAFETY RELIEF VALVE PsV4405 43C4 I I/C 6 RV SAP C/KL A o/C CT-SP sY 14 MAIN STEAM LINE C ADS RELIEF VALVE PSV4406 62E0 I I/C 6 RV SAP C/KL A o/C CT-Sr 5Y 14 MAIN STEAM LINE D ADS RELIEF VALVE PSv4407 67E0 I B/C 6 RV SAP C/KL A o/C CT-SP 5Y 14 MAIN STEAMI LINE D LLS RELIEF VALVE PSV4439A J471n 3 C 6 RV SA C A 0/C CT-VSP 1Y-SRV PSV-4400 RELIEF LINE VACUUM BREAKER PSV4439B 47A9 3 C 6 RV SA C A o/C CT-VSP MoY SRV PSV-440I RELIEF LINE VACUUM BREAKER PSV4439C 51A7 3 C 6 RV SA C A o/C CT-VSP IOY IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 9 of 87

Drwing: 114 Sh~eet #: I

Description:

Nuclear Roiler.Tr~sfte Valve Dwr Safety Vlv Act Norm Safety Valve Description Conr Class Cat. Size Type Typ~e Pox AIP Position Test Frtq RR DJT Remarks PSV4439D 47A7 3 C 6 RV SA C A O/C CT-VSP M0Y PSV4439E 50A7 3 C 6 RV SA C A O/C CT-VSP IMY SRV PSV-4407 RELIEF LINE VACUUMI BREAKER PSV4439F 49A7 3 C 6 RV SA C A O/C CT-VSP IOY SRV PSV.4406 RELIEF LINE VACUU.MI BREAKER V14-0001 67BI I A/C 16 CK SA SYS A O/C AT-I AJ CT-CC R DTJ-27 CT-CO R^ DTJ-27 4 FEEDWATER CIIECK VALVE V14-0003 41BI I A/C 16 CK SA SYS A O/C AT-I AJ CT-CC R DTJ-27 CT-CO R^ DTJ-27 4 FEEDWATER CHECK VALVE V14-0009 60E7 Y C 2 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-14 2,3 CT-CO R* DTJ-14 2,3,4 VALVE,CK,N2 SUPPLY TO SV4406 AND 7 V14-00l4 70C9 Y C 2 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-14 2,3 CT-CO R^ DTJ-14 2,3,4 VALVE,CK,N2 SUPPLY TO SV4402 V14-0015 48E9 Y C 2 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-14 2,3 CT-CO R^ DTJ-14 2,3,4 VALVE,CK,N2 SUPPLY TO SV4400 & 01 IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 10 of 87

Drawing: 114 Sheet #: I

Description:

Nuclear Roiler Sstemn Valve Dwg Satety Viv Act Norm Satety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V14-0016 39C7 Y C 2 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-14 2,3 CT-CO R* DTJ-14 2,3,4 VALVECK,N2 SUPPLY TO SV4405 V14-0032 43F8 N A/C 0.75 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DJT-13 2,3 CT-CO R* DJT-13 2,3,4 ChIECK VALVE FOR N2 SUPPLY TO ACCUMI IR0)2A V14-0lOt 29E9 N A/C 2 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DJT-13 2,3 CT-CO R* DJT-13 2,3,4 CIIECK VAI.VE FOR N2 SUPPLY TO ACCU:I IROOIB V1*4-0104 69F8 N A/C 2 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-13 2,3 CT-CO R* DTJ-13 2,3,4 VALVE,CIIK, NITROGEN TO ACCIJM IROQIA, MISIV CV441 V14-0108 43F8 N A/C 0.75 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-13 2,3 CT-CO R* DTJ-13 2,3,4 VAI,VE,CIIK, NITROGEN TO ACCUM IR002B,, MSISV CV441 VI4-0112 69F8 N A/C 2 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-13 2,3 CT-CO R* DTJ-13 2,3,4 VALVE,CIIK, NITROGEN TO ACCUM IROO1IC, NISIV CV441 V14-0116 43F8 N A/C 0.75 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-13 2,3 CT-CO R* DTJ-13 2,3,4 VALVE,CIIK, NITROGEN TO ACCUM IR002C, NISIV CV441 IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page I11 of 87

Drawing: 114 Sh~eet #: I

Description:

Mtelearl BoilerSiwtent Valve Dwg Safety Vlv Act Norm Safety Valve Detscription Coor Class Cat. Size Type Type Pos ,UP Position Test Freq RR DJT Remarks V14-0120 69F8 N A/C 2 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-13 2,3 CT-CO R^ DTJ-13 2,3,4 VALVE,CIIK, NITROGEN TO ACCUM IROOID, MISIV CV442 V14-0124 43F8 N A/C 0.75 CK SA SYS A C AT-6 2Y 2,3 CT-CC R DTJ-13 2,3 CT-CO R^ DTJ-13 2,3,4 VALVE,CIIK, NITROGEN TO ACCUM IRoO2D, MISIV CV442 XFV4453A 30D5 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IoYI VR-01 PIT 10VI VR-01 MN STMI LINE A INST LINE EXCESS FLOW CIIECK VALVE XFV4453B 30DI I C I XFC SA SYS A C AT-2 I0YI VR-01 CT-CC I0YI VR-01 CT-CO I0YI VR-01 PIT IOYI VR-01 MIN STMI LINE A INST LINE EXCESS FLOW CIIECK VALVE XFV4454A 31D4 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 PDIS-4432C/D LP LINE ISOLATION (,MISL A FLOWV)

XFV4454B 31D3 I C I XFC SA SYS A C AT-2 1OYI VR-01 CT-CC 10YI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 PDIS-4432C/D lIP LINE ISOLATION (NISL A FLOW)

IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 12 of 87

Drawivig: 114 Sheet #: I

Description:

Nuclear Boller St's tent Valve ecrponDwg Safety Vlv Act Norm Satety VleDsrpinCoor Class Cat. Size Type Type Pos AIP Position Test Freq RR DJT Remarks XFV4455A 31118 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC 10YI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 PDIS-4436CID LP LINE ISOLATION (MISL C FLOW)

XFV'44551 301B3 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 PDIS-4436C/D lip LINE ISOLATION (MSL C FLOW)

XFV4456A 321B7 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC 10YI VR-01 CT-CO 10YI VR-01 PIT IOYI VR-01I MIN STM'%LINE C INST LINE EXCESS FLOW CHECK VALVE XFV4456B1 31114 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO laY, VR-01 PIT IOYI VR-01 MN STM'% LINE C INIST LINE EXCESS FLOW CIhECK VALVE XFV4457A 76D3 1 C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO 10YI VR-01 PIT 10YI VR-01 MN STM'% LIINE D INST LINE EXCESS FLOW CHECK VALVE XFV4457B 77D0 I C I XFC SA SYS A C AT-2 IOYI VR-0I CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 MN STM LINE D INST LINE EXCESS FLOW CHIECK VALVE 1ST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 13 of 87

Drawing: 114 Sheet #: I

Description:

Nuclear Boiler Sjstent Valre Dwg Safety VIv Act Norm Safet Valve Description Coor Class Cat. Size Type Type Pos AlP Position Test Freq RR DJT Remarks XFV4458A 77D4 I C I XFC SA SYS A C AT-2 IYI VR-O1 CT-CC IOYI VR-O1 CT-CO IOYI VR-O1 PIT IOYI VR-OI PDIS-4438C/D LP LINE ISOLATION (NISL D FLOW)

XFV4458B 76DI I C I XFC SA SYS A C AT-2 IOYI VR-O1 CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT lOYI VR-OI PDIS-443sC1D lip LINE ISOLATION (MISI D FLOW)

XFV4459A 77B7 I C I XFC SA SYS A C AT-2 1oYI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-O1 PDIS-4434A/B LP LINE ISOLATION (,%ISL B FLOW)

XFV4459B 77B3 I C I XFC SA SYS A C AT-2 10YI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-O1 PIT IOYI VR-OI PDIS-4434A/B lip LINE ISOLATION (,NISL B FLOW)

XFV4460A 76B6 I C I XFC SA SYS A C AT-2 IOYI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-OI PDIS-4434CID LP LINE ISOLATION (,%ISL, B FLOW)

XFV4460B 76B4 I C I XFC SA SYS A C AT-2 IOYI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IYI VR-01 PDIS-4434C/D lIP LINE ISOLATION (MISI B FLOW) 1ST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 14 of 87

Drawihg: 115 Shleet #:1:

Description:

Reactor Vevvel hIstrntentation Valve Dwg Safety VIv Act Norm Safety Valve Description Coor Class Size Type Type Cat. Pos A/P Position Test Freq RR DJT Remarks SV4594A 39C4 I A I GL SO OIC/FC A C AT-I AJ BTC Q FST 1 PIT 2Y LOOP A .JET PUMP SAMPLE LINE INBOARD ISOLATION SV4594B 67C3 I A I GL SO O/C/FC A C AT-I AJ BTC Q FST Q I PIT LOOP B JET PUJM^lP SAMPLE LINE INBOARD ISOLATION SV4595A 36C4 I A I GL SO OIC/FC A C AT-I AJ BTC 0 FST I PIT 2Y LOOP A JET PUEMP SAIMPLE LINE OUTBOARD ISOLATION SV4595B 70C3 I A I CL SO OICIFC A C AT-I AJ BTC Q FST Q I PIT 2Y LOOP B JET PUMP SAMPLE LINE OUTBOARD ISOLATION XFV4501A 40D2 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-01 CT-CO WIYI VR-01 PIT 1OYI VR-01

.JET PUMlP 9 FLOW LP CAL LINE ISOLATION XFV4501B 40DI I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT 10YI VR-01

.IET PUM,1P 13 FLOW LP CAI, ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page I S of 87

Drawing: 115 Sheet #: L

Description:

Reactor Vessel histrumentatinni Valve Dwg Safety VIv Act Norm Satety Valve Description Coor Class Cat. Size Type Type Pos ANP Position Test Freq RR DJT Remarks XFV4503 40D0 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-01 CT-CO IYI VR.01 PIT lnYl VR-0l JET PUMP 10 FLOW LP LINE ISOLATION (TO FT-4503)

XFV4504 66DO I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC 10YI VR-01 CT-CO IOYI VR-01 PIT 1oYI VR-O0 JET PUMP 2 FLOW LP LINE ISOLATION (TO FT-4504)

XFV4505 2418 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC I1YI VR-01 CT-CO IYI VR-01 PIT 10YI VR-01 VAIVE,CIIK,FLOW,EXCESS,RX RECIRC XFV4506 2438 I C I XFC SA SYS A C AT-2 1OYI VR-01 CT-CC IOYI VR-01 CT-CO 10YI VR-01 PIT 1OYI VR-01 JET PUNMP 3 FLOW LP LINE ISOLATION (TO FT-4506)

XFV4507 241B7 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 JET PUMPI 12 FLOW LP LINE ISOLATION (TO FT-4507)

XFV4508 24B7 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT lOYI VR-01 JET PUMIP 4 FLOW LP LINE ISOLATION (TO FT-4508)

IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 16 of 87

Drawivng: 115 Sheet #: j

Description:

Reactor Vevwel 1istr,,,mentation Valve Dwg Sarety Vlv Act Norm sarety Valve Description Coor Class Cat. Size Type Type Pos ,vP Position Test Freq RR DJT Remarks XFV4510A 66D2 I C I XFC SA SYS A C AT-2 1OYI VR-01 CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-OI JET PUMP 5 FLOV' CAL LP LINE ISOLATION XFV4510B 67DI I C I XFC SA SYS A C AT-2 10YI VR-OI CT-CC 10YI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-OI JET PUMP I FLOW CAL LP LINE ISOLATION XFV4511 24116 I C I XFC SA SYS A C AT-2 I0YI VR-01 CT-CC 1OYI VR-0I CT-CO IOYI VR-OI PIT IOYI VR-OI

.JET PUMP 14 FLOW LP LINE ISOLATION (TO FT-4511)

XFV4512 24115 I C I XFC SA SYS A C AT-2 laYI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-OI JET PUMP 6 FLOW LP LINE ISOLATION (TO FT-4512)

XFV4513 24115 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-OI

.JET PUMIP 15 FLOW LP LINE ISOLATION (TO FT-4513)

XFV4514 24114 I C I XFC SA SYS A C AT-2 laYI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-OI PIT IOYI VR-OI JET PUMIP 7 FLOW LP LINE ISOLATION (TO FT-4514)

__ST __Plan__-_ort_10_Yar__ne__a_-Rv___on___Sectio IST Plan - Fourth 10 Year Interval - Revision O Section 9 Page 17 of 87 I

Drawing: LL15 Sheet #: L1

Description:

Reactor Veaue hn tr,,,,e,,tation IValve DsrpinDwg Safety VIv Act Norm Safety Vav[ ecito Coor Class Cat. Size Type Type Pos A11P Position Test Freq RR MIT Remarks XFV 4515 24B5 I C I XFC SA SYS A C AT-2 IOY! VR-01t CT-CC tOY! VR-01!

CT-CO IOYI VR-01!

PIT 10YI VR-01 JET PUMP 16 FLOW 'LP LINE ISOLATION (TO FT-4515)

XFV4516 24133 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOlYI VR-01 CT-CO IOlYI YR-fl1 PIT MlY YR-fl1 JIET PUMPS8 FLOW LP LINE ISOLATION (TO FT-45 16)

XFV4518 67C5 I C I XFC SA SYS A C AT-2 IOYI YR-fl!

CT-CC IOYI YR-fl!

CT-CO IOYI YR-fl!

PIT IOY! YR-fl!

JET PUMP I FLOWY lip CAL LINE ISOLATION XFV4519 38C5 I C I XFC SA SY's A C AT-2 IOYI VR-O1 CT-CC IOYI VR-01 CT-CO IOYI YR-fl!

PIT IOlYI YR-fl1 JET PUMP 13 FLOW lIP CAL ISOLATION XFV'4i28 ------------ 66-C41 I C IF -XFCS-A 'SYS -A --- C AT-2 IOI YVR -fl! ---

CT-CC IOYI YR-fl1 CT-CO IOlYI YR-fl!

PIT IOYI VR-01I PRESS ABIOVE CORE PLATE SENSING LINE ISOLATION XFV4562 40D7 I C I XFC SA SYS A C AT-2 IOlYI VR-01l CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 RX WVTR LEVEL NR VAR LEG SENSING LINE ISOL 1ST Plan - Fourth 10 Year Interval - Revision 0Seto9Pae1of8 Section 9 Page 18 of 87

Drawing: 115 Sheet #: I

Description:

Reatcfor Vessel hi,,xryntentation Valve DsrpinDwg Safety Viv Act Norm Satety VleDsrpinCoor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks XFV457R 66E8 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IOY1 VR-01 PIT IOYI VR-01 RXNN'TR LEVEL WVII FLOODUP REF LEG SENSING LINE XFV4579 66E5 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-O1 CT-CO IOYI VR-O1 PIT IOYI VR-01 RX PRESS/LEVEL WR YARWAY REF LEG SENSING LINE XFV'4580 66E2 I C I XFC SA SYS A C AT-2 IOYI yR-Oh CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 RX WTR LEVEL WVRYARWAY V'AR LEG SENSING LINE XFV4581 66E0 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC JOYI VR-01 CT-CO IOYI VR-01 PIT IOY1 VR-01 RX WVTR LEVEL NR REF LEG SENSING LINE ISOL XFV4582 66D6 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01I PIT 10Y! VR-01 RX LEVEL NR VAR LEG & FLOODUP VAR LEG LINE XFV45813 66D3 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC hOYI VR-01 CT-CO IOYI VR-OI PIT IOYI VR-01 RX PRESSURE SENSING LINE ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0Seto9Pae1of8 Section 9 Page 19 of 87

Drawing: 115 Sheet #: I

Description:

Reactor Vessel Instrumentationi Valve DecitinDwg Safety Vilv Act Norm Safety VleDsrpinCoor Class Ca. Sz Type Type Pos A/P Position Test Freq RR DJT Remarks XFV4584 66C6 I C I XFC SA SYS A C AT-2 i1lYI VR-01 CT-CC 10YI VR-01 CT-CO 10Y! VR-01 PIT I0YI VR-O1 JET PUMPS5 FLOW lip CAL LINE ISOLATION XFV4585 66C3 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT 10YI VR-01 PRESS BELOW CORE PLATE SENSING LINE ISOLATION XFV4586 40E5 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT I0'Y' VR-01 RX NNTR LEVEL WRVRARWAY REF LEG SENSING LINE XFV4587 40E2 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOVI VR-01 CT-CO 10YI VR-01 PIT 10',' VR-01 RX WTR LEVEL WR YARWAY VAR LEG SENSING LINE XFV4588 40E0 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC 10YI VR-01 CT-CO 10YI VR-01 PIT 10Y! VR-01 PS-45G664588 SENSING LINE ISOL (RX PRESS)

XFV4S89 40D3 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC 10',' VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 RX WNTR LEVEL NR REF LEG SENSING LINE ISOL 1ST Plan - Fourth 10 Year Interval - Revision 0Seto9Pae2of8 Section 9 Page 20 of 87

Drawing: 115 Sheet #: I

Description:

Reactor Vessel Instrutmentation Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks XFV4590 4OC6 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC 10YI VR-01 CT-CO 10YI VR.01 PIT 10YI VR-01 JET PUMP 9 FLOW llP LINE ISOLATION XFV4591 40C4 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-01 CT-CO 10'YI VR-01 PIT 10YI VR-01 PRESS BELOW CORE PLATE SENSING LINE ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 21 of 87

Drawiing: 116 Sheet #: I

Description:

Reactor Reciregilation Sveten Valve DsrpinDwg Safety Vlv Act Norm Safety VleDsrpinCoor Class Cat. Size Type Type Pos AIP Position Test Freq RR DJT Remarks CV4639 68E1 I A 0.75 GL AO OIFC A C AT-I AJ BTC Q FST Q PIT 2Y RECIRC SAMPLE LINE INBOARD ISOLATION CV4640 7OE2 I A 0.75 GL AO OIFC A C AT-I AJ BTC Q FST Q PIT 2Y RX RECIRC SYSTEM's SAMPLE LINE OUTBOARD ISOLATION M64-627 27B8 I 11 22 GA MO 0 A C BTC Cs DTJ-09 PIT 2Y RX RECIRC PUMIP IP-201A DISCHIARGE ISOLATION M064628 86118 I 1 22 GA MO0 0 A C IITC Cs DTJ-09 PIT 2Y RX RECIRC PUMIP IP.201B DISCHIARGE ISOLATION XFV4607 56A4 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC lIP/I VR-01 CT-CO 1DYI VR-01 PIT 10YI VR-01 RECIRC PP A SEAL I PRESS (PT-46071PM4609 ISOL)

NXF146 0R8------ 57-A4- I --- C I NFC- S-A SY S- A --- C - AT--2 IO0YI1 -VR -0 1 CT-CC 10YI VR-01 CT-CO 10YI VR-01 PIT loyl VR-01 RECIRC PP II SEAL I PRESS (PT-4608/P1-4610 ISOL)

IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Patie 22 of 87

Drawing: 116 Sheet #: I

Description:

Reactor RecirculationSstemt Valve Dwg Safety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks NFV4611 56A3 I C I XFC SA SYS A C AT-2 1oYI VR-01 CT-CC IOYI VR-01 CT-CO 10YI VR-01 PIT 10YI VR-01 RECIRC PP A SEAL 2 PRESS (PT461 IP14613 ISOL)

XFV4612 57A4 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC 10YI VR-01 CT-CO I1YI VR-0l PIT IOYI VR-01 RECIRC PP 13SEAL 2 PRESS (PT-4612/PI4614 ISOL)

XFV4637 66D7 I C I XFC SA SYS A C AT-2 IOVI VR-01 CT-CC 10YI VR-01 CT-CO 10yl VR-01 PIT IOYI VR-01 RECIRC PP n SUCT PRESS (PS-4637 ISOLATION)

XFV4638 66D3 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC 10YI VR-01 CT-CO 10YI VR-01 PIT lOYI VR-01 RECIRC PP n SUCT PRESS (PS4638 ISOLATION)

XFV14641A 71F4 I C I XFC SA SYS A C AT-2 jOYI VR-01 CT-CC 10YI VR-01 CT-CO 10YI VR-01 PIT 10YI VR-01 PDIS-4641 SENSING LINE FROMIJET PUMIP 1/2 RISER XFV4641B 41F7 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC 1OYI VR-01 CT-CO IO1YI VR-01 PIT IOYI VR-01 PDIS-4641 SENSING LINE FROM JET PP 15/16 RISER IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 23 of 87

Draw'ing: 116 Sheet #: I

Description:

Reactor Recircuatio,, Systenr Valve Dwg Sarety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks XFV4642A 71FI I C I XFC SA SYS A C AT-2 IOYI VR-OI CT-CC 10YI VR-OI CT-CO IOYI VR-0I PIT IOYI VR-OI PDIS-4642 SENSING LINE FRONI ET PUMlP 3/4 RISER XFVf464213 41F3 I C I XFC SA SYS A C AT-2 IOYI VR-0I CT-CC IOYI VR-OI CT-CO IOYI VR-01 PIT IOYI VR-OI PIIIS-4642 SENSING LINE FRON JET PP 13114 RISER XFV4643A 71FO I C I XFC SA SYS A C AT-2 IOYI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-OI PDIS-4643 SENSING LINE FROM JET PUMP 5/6 RISER XFV46f431 41FO I C I XFC SA SYS A C AT-2 IOYI VR-0I CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-O1 PDIS-4643 SENSING LINE FROMI IET PP 11/12 RISER XFV4644A 71E8 I C I XFC SA SYS A C AT-2 IOYI VR-0I CT-CC IOYI VR-OI CT-CO IOYI VR-O1 PIT IOYI VR-0Ol PDIS-4644 SENSING LINE FRONI JET PUMIP 7/8 RISER XFV464411 41E8 I C I XFC SA SYS A C AT-2 IOYI VR-O0 CT-CC IOYI VR-OI CT-CO IOYI VR-O0 PIT IOYI VR-01l PDIS-4644 SENSING LINE FROM JET PUMP 9/1 0 RISER IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 24 of 87

Drawiig: 116 Sheet #: I

Description:

Reactor Recirculadti,,Sstemt Valve Dwg Safety Vlv Act Norm Satety Valve lDescription Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks XFV4663 44E2 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-01 CT-CO 10YI VR-01 PIT IOYI VR-OI FT-4631A Lr lINF ISOI (IP-201A DISCI! FLOWV)

XFV4664 45E2 I C I XFC SA SYS A C AT-2 10YI VR-OI CT-CC JOY] VR-OI CT-CO IOYI VR-OI PIT IOYI VR-OI FT4631A 1P LINE ISOI, (IP-201A DISCII FLOW)

XFV46T5 42D2 I C I XFC SA SYS A C AT-2 IOYI VR-OI CT-CC 0YoI VR-01 CT-CO IOYI VR-01 PIT 10YI VR-01 FT-4632C LP LINE ISOL (IP-201B DISCII FLOW)

XFV4666 47C9 I C I XFC SA SYS A C AT-2 10YI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-OI FT-4C32C HP lINE ISOL (IP-201B DISCII FLOW)

XFV4667 46E0 I C I XFC SA SYS A C AT-2 10YI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-01 PIT IOYI VR-01 FT-4631B1 L lINE ISOL(IP-201A DISCII FLOWV)

NXFV406S 4RE0 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-.O CT-CO IOYI VR-OI PIT IOYI VR-OI FT-1631 n lIP1LINE ISOL (I P-201A DISCII FLOW)

IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 25 of 87

Drawing:.116 Sheet #: I

Description:

Reactor RecirculatlonS1stem, Valve Dwg Safety Viv Act Norm sarety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks XFV4669 43D6 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT I1YI VR-01 FT-4632D lIP LINE ISOL(lP-201 DISCII FLOW)

XFV467(0 45D6 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-O0 CT-CO IOYI VR-01 PIT IOYI VR-01 FT-46321B LP LINE ISOL (I P-201 B DISCII FLOW)

XFV4671 43D4 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC 10YI VR-O0 CT-CO IOYI VR-01 PIT 1OYI VR-01 FT--631 C LP LINE ISOL (I P-201A DISCII FLOWV)

XFV4672 44D2 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC 1OYI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 FT-4631C IIP LINE ISOL(IP-201A DISCII FLOW)

XFV4673 44E0 I C I .FC SA SYS A C AT-2 IOYI VR-01

- CT-CC 1OYI VR-01 CT-CO 10YI VR-01 PIT IOYI VR-01 FT-4632A LP lINE ISOL(IP-201B DISCII FLOW)

XFV4674 45E0 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR.01 CT-CO IOYI VR-01 PIT lOYt VR-01 FF-4632A lip LINE ISOL(IPr201Bl DISCII FLOW)

IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 26 of 87

Drawing: 116 Sheet l: I

Description:

Reactor RecirculationSVsten, Valve Dwg Safety Viv Act Norm Safety ValeDcrip~tion Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks XFV4675 45S0 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC 1OYI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 FT-4631D LP LINE ISOL (IP-201A DISCII FLOW)

XFV4676 44CS I C I XFC SA SYS A C AT-2 1OYI VR-01 CT-CC 1OYI VR-01 CT-CO 10Y1 VR-01 PIT IOYI VR-01 FT-i63ID lip LINE ISOL(IP-201A DISCIT FLONV)

XFV4677 45C6 I C I XFC SA SYS A C AT-2 1OYI VR-01 CT-CC 10YI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 FT-4632D lIP LINE ISOI, (IP-201B DISCIT FLOW)

XFV'4678 43C7 I C I XFC SA SYS A C AT-2 1OYI VR-01 CT-CC 1OYI VR-01 CT-CO 1OYI VR-01 PIT IOYI VR-01 FT-4632D LP LINE ISOL (IP-21ln DISCII FLOW)

XFV4679 76A7 I C I XFC SA SYS A C AT-2 1OYI VR-01 CT-CC IOYI VR-01 CT-CO I0YI VR-01 PIT IOYI VR-01 PDIS-4626A-D & PDT4624 lIP SENSING LINE ISOL XFV4680 76A3 I C I XFC SA SYS A C AT-2 1OYI VR-01 CT-CC 1OYI VR-01 CT-CO 10YI VR-01 PIT 10YI VR-01 PDIS4626A-D & PDT-4624 LP SENSING LINE ISOL IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 27 of 87

Drawiing: 11(; Shtee #: I

Description:

Reactor Recircuilation S'lstein Valve Dwg Safety Vlv Act Norm Safety Valve Dlescription Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks XFY4681 37A8 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOVI VR-01 CT-CO 10YI VR-01 PIT I0YI VR-01 PDIS-462sA.D & PDT4623 lip SENSING LINE ISOL XFV4682 37A3 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT 1OYI VR-01 PDIS-4625A-D & PDT-4623 LP SENSING LINE ISOL IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 28 of 87

Drawing: 117 Sheet #: I

Description:

Control RodDrive IIrdraulicSrstem Valve Dwg Safety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CVI804A 62A4 I A 0.75 GL AO OtFC A C AT-1 AJ BTC Q FST Q PIT 2Y "A" RECIRC PUMP MNIINI- PURGE SUPPLY ISOLATION CV1804B 49A4 I A 0.75 GL AO O/FC A C AT-I AJ BTC Q FST Q PIT 2Y "B" RECIRC PUMIP MIINI- PURGE SUPPLY ISOLATION V17-0052 29D8 I A 3 CK SA SYS A C AT-I R CT-CC R DTJ-I 7 CT-CO R* DTJ-17 4 CRD-TO-VESSEI, RETURN IIDR UPSTREAMI CHECK VALVE V17-0053 25D8 I A 3 CK SA SYS A C AT-I R CT-CC R DTJ-17 CT-CO R* DTJ-17 4 CRD-TO-VESSEL RETURN IIDR DOWNSTREAM CHECK VALVE Vl 7-0083 44A2 I NC I CK SA SYS A C AT-I R CT-CC R DTJ-08 CT-CO R* DTJ-08 4 VALVE,CIIKRX RECIRC V17-0096 67A3 I A/C 1 CK SA SYS A C AT-I R CT-CC R DTJ-08 CT-CO R* DTJ-08 4 VAIVE,CIIK,RX RECIRC IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 29 of 87

[Draw'ing: .LL8 Sheet #: IL

Description:

Coittrol Rod Drive I1i'drantlic Syt~ei IvleDwg sarety V'iv Act No rm Safety I Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR D.JT Remarks CV1i849(MM-H R1CS 2 II 0.75 GL AO C A 0 NA NA S4, 5 SCRAM INLET VALVE CVI850(H#4H 66CS 2 B 0.75 GIL AO C A 0 NA NA S4,5 SCRA'M OUTLET VALVE CVISS9 41F5 N1 II I GL AO OI7C A C BTC 0 3 FST Cs DTJ.16 3 PIT 2Y 3 SCRAM DISCHARGE VOLUME VENT VALVE CVR8S9B_ - 40_F2_ 2- -B I C_

GL -AO O/F17C -A - C BT-C - Q-FST Cs DTJ-16 PIT 2Y SCRAM DISCHARGE VOLUME V'ENT VALVE CV1867A 55C9 N B 2 GI, AO O/FC A C BTC 0 3 FST Cs DTJ-16 3 PIT 2Y 3 SCRAM,% DISCHIARGE VOLUME DRAIN OUTBOARD ISOLATION CVI867B 55D0 2 B 2 GL AO O/FC A C BTC Q I

FST Cs DTJ-1 6 PIT 2Y SCRAM DISCHIARGE VOLUME DRAIN INBOARD ISOLATION v'l8.0IIS(##. 82B3 2 A/C 0.5 CK SA SYS A C NA NA Si, 5 CHIECK VLV, CHARGING WITR RISER

`VI8-_0 9 I9 (-# - - - - - - - - --- 80DO- -2 - -C 0.5 _CK S-A ' S -YS A- - -C -NA

- - - -NA

- - - - - - -S-2,5-CHECK VLV, COOLING NVTR IIDR V18.1453(f##. 64C6 2 C 0.75 CK SA SYS A 0 NA NA S3,5 CIIECII VLV, SCRAM DISCII RISER 1ST Plan - Fourth 10 Year Interval - Revision 0Seto9Pae3of8 Section 9 Page 30 of 87

Drawving: 119 Sheet #: I

Description:

Residual Heat Rentosal SIsten, Valve Dwg Safety VIv Act Norm Satety Valve lDscription Conr Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks M01902 81E9 2 A 10 GA MO C/KL A C AT-I AJ BTC Q PIT 2Y RIIR LOOP B INBOARD DRYWELL SPRAY ISOLATION M01903 h7E9 2 B 10 GL :MO C/KIL A C BTC Q PIT 2Y RIIR LOOP B DRYWELL SPRAY IIDR OUTBOARD ISOLATION M01904 62D7 2 B 20 ANG MO 0 A 0 BTO Q PIT 2Y RIIR LOOP B LPCI OUTBOARD INJECTION ISOLATION MI01905 67E0 I A 20 GA 'MO C A O/C AT-5 2Y BTC Q BTO Q PIT 2Y RIIR LOOP B LPCI INBOARD INJECTION ISOLATION M101908 85D8 I A 1S GA MO C P C AT-5 2Y PIT 2Y RIIR SHUTDOWN COOLING SUCTION ISOLATION M01909 85D5 I A 18 GA M1O C P C AT-5 2Y PIT 2Y RIIR SIIUTDOWN COOLING OUTBOARD SUCTION ISOL, tM01912 72n8 2 B 14 GA IMO C/KL P C PIT 2Y RIIR PP IP229B SID CLNG & FUEL POOL CLNG SUCTIO M01913 77118 2 B 14 GA 'MO OIKL P 0 PIT 2Y RIIR PUMlP I P-229B TORUS SUCTION ISOLATION M01920 84C9 2 B 14 GA MO C/KL P C PIT 2Y RIIR PP IP-229D SID CLNG & FUEL POOL CLNG SUCTIO N101921 79n8 2 B 14 GA IMO O/KL P 0 PIT 2Y RIIR PUMP IP-229D TORUS SUCTION ISOLATION 1ST ___Plan__-_o__t_10_Yar________-Revision_0_Sectio IST Plan - Fourth 10 Year Interval - Revision O Section 9 Page 31 of 87

7Dra wing: 119 She fI

Description:

Residual Hleat Removal St' tent IValve Seti:. Dwg Safety V~v Act Norm Satety Valve Description Coor Class Cat. Size Type Type Pos AlP Position Test Freq RR DJT Remarks M01932 57E6' 2 B 12 GA MfO C/KL A 0/C BTC Q BTO Q PIT 2Y RIIR LOOP B TORUS SPRAY & COOLING SUPPLY IIDR ISO M01933 56E4 2 A 4 GL, MO C A 0/C AT-I AJ BTC Q BTO Q PIT 2 RIIR LOOP II TORUS SPRAY MEADER ISOLATION M0193S 54E0 2 B 12 GI. MO C A 0/C RTC Q BTO 0 PIT 2Y RIIR1 LOOP B TORUS COOLING & TEST RETURN IIDR ISOL M'*01935 56113 2 B 3 GA MO1 C A 0/C BTC Q BTO Q PIT 2Y RIIR1PUMPS IP-2298/D, MINIM'%UM, FLOWV BYPASS M01936 6I1DO N B 4 GA 'MO C P C PIT 2Y 3 RIIR DRAIN TO WASTE SURGE TANK OUTBOARD ISOLATION M01937 64D0 2 B 4 GA MO C P C PIT 2Y RIIR1DRAIN TO WASTE SIIRGE TANK INBOARD ISOLATION M01939 45C8 2 B 12 GA 'MO 0 A 0/C BTC Q BTO Q PIT 2Y RIIR IIX I E-201B INLET ThROTTLE VALVE N101940 46D4 2 B 18 GL MO I 0 A 0/C BTC Q BTO 0 PIT 2Y RI IRIIX I E-201B BYPASS VALVE IST Plan - Fourth 10Year Interval - Revision 0Seto9Pae3of8 Section 9 Page 32 of 87

Drawing: 119 Sheet #: I

Description:

Residnal Heat Remnoval vsftern Valve Dwg Safety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks M0I941 29D4 2 n 12 CA NMO O/KL P 0 PIT 2Y RIIR IIX IE-2011 OUTLET ISOLATION M0194911 42C1 2 n I GL MO%0 C P C PIT 2Y RIIR IIX IE-201B SIIELL SIDE INBOARD VENT

.MIO1989 77C8 2 n 24 GA NIO O/KL P 0 PIT 2Y RIIR LOOP n TORUS SUCTION ISOLATION PSV1911 84D1 2 C I RV SA C A O/C CT-SP IOY2 16 RIIR SHUTDOWN CLG SUCTION HEADER PRESSURE RELIEF PSV 1919 69C2 2 C I RV SA C A O/C CT-SP IOY2 16 RIIR PUMtP IP-229B SUCTION PRESSURE RELIEF PSV1927 88C4 2 C I RV SA C A O/C CT-SP IOY2 16 RIIR PUMIP IP-229D SUCTION PRESSURE RELIEF PSV1953 32C1 2 C 0.75 RV SA C A O/C CT-SP IOY2 16 RIIR IIX IE-201BSIIELL SIDE PRESSURE RELIEF PSV1975 38F0 2 C I RV SA C A O/C CT-SP IOY2 16 RIIR IIX IE-201 B DISCIIARGE HEADER PRESSURE RELIEF SV'I972 22C5 2 1 I (G.1. SO CIK/L P C BTC Q FST Q 4 PIT 2Y RIIR IIX I E-201 n PASS SAMPI LINE INBOARD ISOLATION SV1973 17C5 N B I GL SO C/KL P C BTC Q FST Q 4 PIT 2Y RIIR IIX I E-201B PASS SAMP LINE OUTBOARD ISOLATIO V19-000I 78A7 2 C 12 CK SA SYS A O/C CT-CC Q CT-CO Q VALVE,CIIK,RIIR,PUNIP IP229D DISCII

__STPlan__-o--__ eviion_0 _ _Section_9_Page__ 33_of_87 IST Plan - Fourth 10 Year Interval - Revision O Section 9 Page 33 of 87

Drawing: 119 Sheet #: I

Description:

Residual Heat Removal Si~ten Valve Dwg Safety VIv Act Norm Safety Valve lescription Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V19-0003 53A7 2 C 12 CK SA SYS A O/C CT-CC Q CT-CO Q VALVE,CIIK,RIIR,PUMNIP IP229B DISCII V19-0014 82A9 2 C 3 CK SA SYS A O/C DSSBY RI DTJ-20 VALVE,CIIK,RiIR,IP229D DISCILBYP LINE V19-0016 56A9 2 C 3 CK SA SYS A O/C DS13Y RI DTJ-20 VALVE,CIIK,RIIR. P229B DISCIIBYP LINE V19-0020 64B2 2 C I SCK SA SYS/LO A C DSIIY RI DTJ-28 "B" RIIR LOOP KEEP FILL SUPPLY LINE STOP CHECK V19-0022 66B5 2 C I CK SA SYS A C DSBY RI DTJ-28 RIIR/CORE FILL PUMP IP-70 CORE SPRAY CHECK VALVE V19-0023 68115 2 C I SCK SA SYS/LO A C CT-CC Q CT-CO Q "I" CORE SPRAY KEEP FILL SUPPLY LINE STOP CHECK V19-0024 66B8 2 C I CK SA SYS A C DSBY RI lTJ-28 RIIR FILL PUMrP IP-70 TO PUMP A,C CHECK VALVE V19-0048 47E4 2 B 18 GA M 0 P 0 PIT 2Y RIIR LOOP CROSSTIE V19-0124 67137 2 C 0.75 CK SA SYS A C DSBY RI DTJ-28 "A" RIIR LOOP KEEP FILL SUPPLY LINE STOP CIIECK V19-0128 68B3 2 C I SCK SA SYS/LO A C CT-CC Q CT-CO Q "A" CORE SPRAY KEEP FILL SUPPLY LINE STOP CHECK V19-0147 78D9 I B 20 GA M 0 P 0 PIT 2Y "13" I.PCI SUPPLY LINE MANUAL ISOLATION V19-0149 77D8 I A 20 CK SA SYS A O/C AT-5 2Y CT-CC R DTJ-29 CT-CO R^ DTJ-29 16 VALVE, CHECK, RIIR, LPCI, INJECT LOOP B 1ST ___Plan__-_or__10_Yar__ne____-Revision_0_Sectio IST Plan - Fourth IO Year Interval - Revision O Section 9 Page 34 of 87

Drawing: 119 Sheet #: I

Description:

Revidlnal hleat Removal Svsten Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos AIP Position Test Freq RR DJT Remarks V19-0 195 87D8 I A 0.5 CK SA C A O/C AT-5 2Y CT-CC R DTJ-30 CT-CO Ri DTJ-30 16 M0-1 908 BYPASS ChIECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 35 of 87 1

LDrawing:

Valve 120 Valve Description Sheet fi: I

Description:

Resvidual Hfeat Remroval S1vstent Dwg Coor Safety Class Cat. Size Viv Type Act Type Norm Pos A/P Safety Position Test Freq RR DJT Remarks M02000 30E9 2 A 10 CA MO%1 C/KL A C AT-I AJ BTC Q PIT 2Y MRii LOOP A INBOARD DRYWELL SPRAY VALVE M02001 44E9 2 B It) GI. MO CIKL A C BTC Q PIT 2Y RIIR LOOP A DRYWELIL SPRAY IIDR OUTBAORD ISOLATION M02003 43D9 I A 20 GA MO C A 0/C AT-5 2Y BTC Q BTO Q PIT 2Y RIIR LOOP A LPCI INBIOARD INJECTION ISOLATION M02004 48D6 2 B 20 A NG MOI 00 A 0 BTO Q PIT 2Y R111R LOOP A LPCI OUTBOARD INJECTION ISOLATION N102005 51E6 2 B 12 CA MO C/KL A 0/C BTC Q BTO Q PIT 2 RI111 LOOP A TORUS SPRAY & COOLING SUPPLY IIDR ISO M00) 13 2 A 4 GIL MO C A /C AT-I 2Y BTC Q BTO Q PIT 2Y RiIR LOOP A TORUS SPRAY HEADER ISOLATION M02007 53EI 2 B 12 GI. MO% C A 0/C BTC Q BTO Q PIT 2 11i1R LOOP A TORUS COOLING & TEST RETURN IIDR ISOL IST Plan - Fourth 10 Year Interval - Revision 0Seto9Pae6of8 Section 9 Page 36 of 87

Drawinig: 120 Sheet #: I

Description:

Residutal Heat Rentovi'l Svtwe,,

Valve DsrpinDwg Safety Vlv Act Norm Safety VleDsrpinCoor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks M02009 50119 2 B 3 GA MO1 C A 0/C BTC Q BTO Q PIT 2Y RIIR PUM'%PS IP.229A/C MINIM'%UM' FLOW BYPASS M02010 54C7 2 B 18 GA M,10O 0KL P 0 PIT 2Y RIIR LOOPS A/B CROSS-TIE HIEADER ISOLATION MOZ2I1I 39C0 2 B 14 GA MO%1C/KL P C PIT 2Y IUI1iRPP lP-229A S/DlCLNG & FUEL POOL CLNG SUCTIO M02012 319 2 B 14 GA M O/L P 0 PIT 2 RIIR1 PtuMP IP-229A TORUS SUCTION ISOLATION MNO20I5 321B9 2 B1 14 GA IMO O/KL P 0 PIT 2Y IIR PUMP IP-229C TORUS SUCTION ISOLATION M102016 28C0 2 B 14 GA MO C/KL P C PIT 2Y I P-229C SiI1UTDOWVN COOLING & FUEL POOL COOLING SU M02029 6C B 12 GA 'MO O/KL A /C BTC Q BTO Q PIT 2 RIIM 11X I E-201A INLET THROTTLE VALVE M00060D4 2 B 8 G O 0 A 0/C BTC Q BTO Q PIT 2 RlIR IIX IE-201A BYPASS VALVE M02031 72D3 2 B 1 GA MIO O/KL P 0 PIT 2 RlIR IlX IE-20IA OUTLET ISOLATION M020441142 I GIL MO C P C PIT 2Y RIIR IIX IE-201A ShELL SIDE INBOARD VENT M00934C8 2 B 24 GA MIO O/KL P 0 PIT 2Y RIIR LOOP A TORUS SUCTION ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 37 of 87

Drawing: 120 Sheet #: I

Description:

Residuallfeat Rentoval.System ValDe Dwg Sarety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks PSV2019 42C8 2 C I RV SA C A O/C CT-SP 10Y2 16 RIIR PUM5lP IP-229A SUCTION PRESSURE RELIEF PSV2020 24C4 2 C I RV SA C A O/C CT-SP 10Y2 16 RIIR PUMIP IP-229C SUCTION PRESSURE RELIEF PSV2042 64C1 2 C 0.75 RV SA C A O/C CT-SP 10Y2 16 RIIR IIX I E-20IA SiIELL SIDE PRESSURE RELIEF PSV2057 70E6 2 C I RV SA C A O/C CT-SP I0Y2 16 RIIR IIX IE-201A DISCHARGE HEADER PRESSURE RELIEF SV2051 79C5 2 B I GL SO C/KL A C BTC Q FST Q I PIT 2Y RIIR IIX I E-201A PASS SANMP LINE INBOARD ISOLATION SV2052 83C5 N B I GL SO C/KL P C IBTC Q FST Q I PIT 2Y RIIR IIX I E-201A PASS SAMIP lINE OUTIBOARD ISOLATIO V20--000 33A7 2 C 12 CK SA SYS A O/C CT-CC Q CT-CO Q VALVE,CIIK,RIIR,PU.MlP IP229C DISCI_

V20-0003 55A8 2 C 12 CK SA SYS A O/C CT-CC Q CT-CO Q VALVE,CIIK,RIIR,PUtNP IP229A DISCII V20-0006 50A9 2 C 3 CK SA SYS A 0/C DSBY RI DTJ-20 IP-229A DISCIIARGE BYPASS LINE CIIECK VALVE V20-0008 27B1 2 C 3 CK SA SYS A O/C DSBY RI DTJ-20 VALVE,CIIK,RIIR,IP229C DISCII,BYP LINE V20-0081 29D9 I B 20 GA '% 0 P 0 PIT 2Y "A" LPCI SUPPLY LINE MANUAL ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 38 of 87

lDrawing: 120 Shleet #: I Descriptionr: Residuanl Heat Removlnl.vstent Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V20-0082 34E0 I A 20 CK SA SYS A O/C AT-5 2Y CT-CC R DTJ.25 CT-CO DTJ-25 VALVE, ClIK, RIIR, LPCI INJ LOOP A IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 39 of 87

Drawving: 121 Sheet #: I Descripfiow: Core SnravrSyvrem Valve Dwg Satety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos AlP Position Test Freq RR DJT Remarks N102100 52R1 2 B 12 GA MIO OIKL P 0 PIT 2Y CORE SPRAY PUMP IP-21 IA OUTBOARD TORUS SUCTION M02104 40C4 2 B 2 GA 1MO 0 A O/C BTC Q BTO Q PIT 2Y CORE SPRAY PUMlP I P-21 IA MIINIMUMI FLOW BYPASS 102112 52E0 2 B 8 GL MO C P C PIT 2Y CORE SPRAY LOOP A TEST BYPASS VALVE 10211S 57E7 2 B 8 GA M0 0 P 0 PIT 2Y CORE SPRAY LOOP A OUTBD INJECTION VALVE M02117 64E7 I A 8 GA 10 C A O/C AT-I 2Y AT-5 2Y BTC Q BTO Q PIT 2Y CORE SPRAY INBOARD INJECTION VALVE M102120 52B3 2 B 12 CA 10 O/1KL P 0 PIT 2Y CORE SPRAY PUMP I P-21 IB OUTBOARD TORUS SUCTION M02124 43C4 2 B 2 GA MIO 0 A O/C BTC Q BTO Q PIT 2Y CORE SPRAY PUP IIP-211B MIINIMIUMI FlOW BYPASS M02132 53D6 2 B 8 Gl, %10 C P C PIT 2Y CORE SPRAY LOOP B TEST BYPASS VALVE M02135 58D2 2 B 8 GA M10 0 P 0 PIT 2Y CORE SPRAY LOOP B OUTBD INJIECTION VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 40 of 87

Drawing: 121 Sheet #: L

Description:

Core Spraj'Svstent Valve Dwg Safety VIv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos AIP Position Test Freq RR DJT Remarks N102137 65D2 I A S GA MO C A O/C AT-I 2Y AT-5 2Y BTC Q BTO Q PIT 2Y CORE SP'RAY LOOP B INBD INJECTION VALVE M02146 57B5 2 B 12 GA M10 O/KI P 0 PIT 2Y CORE SPRAY PUMNlP I P-211 B INBOARD TORUS SUCTION M02147 57B2 2 B 12 GA 'MO OIKL P 0 PIT 2Y CORE SPRAY PUMIP I P-211 AINBOARD TORUS SUCTION PSV2102 33C7 2 C 0.75 RV SA SYS A O/C CT-SP 10Y2 16 CORE SPRAY PUMfiP IP-21 IA SUCTION PRESSURE RELIEF PSV2109 46E6 2 C 2 RV SA SYS A O/C CT-SP 10Y2 16 CORE SPRAY PUMlP IP-21 IA DISCII IIDR PRESS RELIEF PSV2122 50B7 2 C 0.75 RV SA SYS A O/C CT-SP 10Y2 16 CORE SPRAY PUMIP IP-211B SUCTION PRESSURE RELIEF I'SV2129 46D3 2 C 2 RV SA SYS A O/C CT-SP 10Y2 16 CORE SPRAY PUMP IPI-211B DISCIIHDR PRESS RELIEF V21-0007 36C3 2 C 10 CK SA SYS A 0 CT-CC Q CT-CO Q IP-211A DISCIIARGE IIEADER CIIECK VALVE V21-0009 38C3 2 C 2 CK SA SYS A 0 DSBY RI DTJ-20 I P-21 IA MIINIMlUMI FLOW LINE CHECK VALVE V21-0010 47C4 2 C 10 CK SA SYS A O/C CT-CC Q CT-CO Q IP-21 IB DISCHARGE IIEADER CHECK VALVE V'21-0t12 44C3 2 C 2 CK SA SYS A 0 DSBY RI DTJ-20 IP-21IB MINIUM FLOW LINE CHECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 41 of 87

Drawing: 121 Sheet #: I

Description:

Core Snras' Sristem Valve Dwg Safety VIv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V21-l0042 77EI I B 8 GA 'M 0 P 0 PIT 2Y CS LOOP "A" INJECTION HEADER MANUAL BLOCK V21-0043 77D8 I n x GA %I 0 P 0 PIT 2Y CS LOOP "B" INJECTION HEADER MANUAL BLOCK V21-0072 71E0 I A/C 8 CK SA SYS A O/C AT-5 2Y CT-CC R DTJ-21 CT-CO R* DTJ-21 VALVE, CIIKLPCS, A v21-i073 72D7 I A/C 8 CK SA SYS A O/C AT-5 2Y CT-CC R DTJ-21 CT-CO R* DTJ-21 VALVE, CIIK, LPCS B XFV2119 74FI I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IOYI VR-01 PIT IOYI VR-01 PDIS-2119 SENSING LINE (CORE SPRAY SPARGER DP)

XFV2139 74F4 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO IYI!. VR.01 PIT IOYI VR-01 PDIS-2139 SENSING LINE (CORE SPRAY SPARGER DP)

IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 42 of 87

1Drawing: 122 Sheet #: I

Description:

Hi-il Presunre Coolant Injection Steam Side Valve Dwg Sarety Vlv Act Norm Sarety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR D.JT Remarks CV2211 23C3 2 A I GA AO O/FC A C AT-I AJ RTC Q FST Q PIT 2Y IIPCI STM SUP DRAIN LINE UPSTREAM AUTO ISOLATION

_ _ _ 12_ ,

CV22 11 9_ -

9C3 2 - A I GA AO O/FC A C AT-I AJ BTC Q FST Q PIT 2Y IIPCI STM SUP DRAIN LINE DOWNSTREAM AUTO ISOL CV2234 60117 2 B I GA AO O/FC A C BTC Q FST Q PIT 2Y IIPCI COND PUMP IP.219 DISCII TO CRW INBD ISOL CV2235 64117 N B I GA AO O/FC A C BTC Q 3 FST Q 3 PIT 2Y 3 rIPCI COND PUMP IP-219 DISCII TO CRW OUTBD ISOL 1IV2201 33E0 2 B to PLC 110 C A O/C BTC Q 2 BTO Q 2 PIT 2Y 2 IIPCI TURBINE STOP VALVE M02202 31D8 2 B 10 GA MN1O C A 0 BTO Q PIT 2Y IIPCI TURBINE STEAM1 SUPPLY ISOLATION M02238 69E8 I A 10 GA MO 0 A C AT-I AJ BTC Q PIT 2Y IlPCI STEAM SUPPLY INBOARD ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 43 of 87

Drawing: 122 Sheet #: I

Description:

High Presunre Coolant hijection SteamiSide Valve ecrtinDwg Safety Vii' Act No rm Sft VleDsrpinCoor ClassCa. Sz Type Type Pos AVP Position Test Freq RR DJT Remarks N102239 601F2 I A It) GA MO 0 A C AT-1 AJ BTC Q PIT 2Y IiPCI STEAM SUPPLY OUTBOARD ISOLATION M02247 52C2 2 B 2 GL MO C A 0 BTO Q PIT 2Y IIPCI CONDENSER/LUBE OIL COOLER CLNC WVTR SUPPLY MO290A 861B6 2 A 2 GA 'MO 0 At C AT-I A.J BITC Q PIT 2Y IIPCIIRCIC TURD STM EXIIST VACUU'M BREAKER LINE IS M0(2_29-0 B- 86113- -2 - A 2- -GA M'-O- -0 A- C A-I - AJF---------

BTC Q PIT 2Y IIPCI/RCIC TURB STM'% EXIIST VACUUM'% BREAKER LINE IS PSE2213 61C6 2 C 16 RPD SA C A 0/C CT.RDR 5Y IIPCI TURBINE STEAM EXIIST RUPTURE DISC PSE2214 61 C8 N C 16 RPD SA C A 0/C CT-RDR MOY 3,15 IIPCI TURBINE STEAM EXIIST RUPTURE DISC PSV2223 32C0 N C 1.25 RV SA C P C CT-SP lOY 3 IIPCI CONDENSER I E-202 PRESSURE RELIEF PSV2228 52B15 2 C I RV SA C A 0/C CT-SP 10Y2 16 IIPCI LO0 COOLER COOLING WTR INLET PRESS RELIEF V'22-0016 74B18 2 C 16 CK SA SYS A 0/C CT-CC R DTJ-15 CT-CO R* DTJ-15 4 VAI.VE,CIIK,IIPCI,lS201 EXII LINE V'22.0017 78B7 2 C 16 SCK MSA SYS!LO A 0/C CT-CC R DT.J-15 CT-CO R* DTJ-15 4 IIPCI TURBINE STEAM EXHAUST LINE ISOLATION 1ST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 44 of 87

Drawing: 122 Sheet #: L

Description:

High PrevssreCnolauti Iluiection Steanim Side Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V22.0021 70B0 2 C 2 CK SA SYS A C DSBY RI DTJ-18 IlPCI EXIIAllST DRAIN POT DRAIN LINE CIIECK VALVE Vi22-0022 751B0 2 C 2 SCK 'MSA SYStLO A C DSIIY RI DTJ-18 IIPCI TURD STM EXIIST COND DRN POT RETURN TO TORUS V22-0026 38Bl 2 C 1.25 CK SA SYS A 0 DsBY RI DTJ-25 IIPCI CONDST PUMP IP-219 DISCII LINE CHECK VALVE V22.0028 44112 2 C 2 CK SA SYS A 0 DSBY RI DTJ-25 IIPCI TURD LUlBE OIL CLR IE-203 CLG VTR EXII LINE V'22-i0029 53B1 2 C 2 CK SA SYS A 0 DSBY RI DTJ-25 VAL.VECIIK,IIPCI,IP219 EXII LINE V22-00f63 82B7 2 A/C 3 CK SA SYS A o/C AT-I AJ DSBY RI DTJ-25 VAl.VE,CIIKIIPCIVAC BREAKER LINE V22-0064 84117 2 A/C 3 CK SA SYS A O/C AT-I AJ DSBY RI DTJ-25 VALVE,CIIKIIPCI,VAC BREAKER LINE NFV2246A 63E2 I C I XFC SA SYS A C AT-2 10YI VR-01 CT-CC IOYI VR-01 CT-CO I1YI VR-01 PIT 10YI VR-01 PS-2246A SENSING LINE (IlPCI STEAMSI PRESSURE)

XFV2246B 63E3 I C I XFC SA SYS A C AT-2 IOYI VR-01 CT-CC IOYI VR-01 CT-CO 10YI VR.01 PIT 10YI VR-01 PS-2246B SENSING LINE (lIPCI STEAM PRESSURE)

IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 45 of 87

Drawing: 122 Sheet #: 1

Description:

Higl, Pressure Coolant hniection Steant Side Valve Dwg Sarety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks I

XFV2246C 63D8 I C I XFC SA SYS A C AT-2 1oYI VR-OI CT-CC I1YI VR-OI CT-CO IOYI VR-OI PIT 10YI VR-OI PS-2246C SENSING LINE (IIPCI STEANI PRESSURE)

XFV2246D 63D6 I C I XFC SA SYS A C AT-2 IOYI VR-O1 CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-O1 PS-2246D SENSING LINE (IIPCI STEAM PRESSURE)

IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 46 of 87

Drawing: 123 Sheet #: 1

Description:

JHigh PressureCoolant Iniection J'atlerSide Valve l)wg Satety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P' Position Test Freq RR DJT Remarks CV2315 60n5 2 B 8 GL AO C/FC P C PIT 2Y IIPCI CST TEST RETURN LINE ISOLATION M02300 34E8 2 B 14 GA IMO 0 A C BTC Q PIT 2Y IIPCI PUIMP CST SUCTION ISOLATION M102311 58C7 2 B 12 GA MNIO 0 P 0 PIT 2Y IIPCI PUMP I)ISCIHARGE ISOLATION

M02312 65C7 I A 12 GA 1MO C A O/C AT-I AJ 6 BTC Q BTO Q PIT 2Y IIPCI FEEDWVATER INJECTION ISOLATION M102316 60E1 N B 8 GA 1MO C P C PIT 2Y 3 IIPCI/RCIC TEST RETURN REDUNDANT SIIUTOFF VALVE M102318 50C2 2 B 4 Gl, MO C A O/C BTC Q BTO Q PIT 2Y 5PCI PUMP MINIMUM FLOW BYPASS VALVE

1102321 69A6 2 B 14 GA IMO C A O/C BTC Q BTO Q PIT 2Y IIPCI PUM1P TORUS SUCTION INBOARD ISOLATION M02322 39E6 2 B 14 GA MO C A O/C BTC Q BTO Q PIT 2Y IIPCI PUIMP TORUS SUCTION ISOLATION PSV2301 29E8 2 C 1.5 RV SA SYS A O/C CT-SP 10Y TIPCI BOOSTER PP SUCTION PRESSURE RELIEF IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 47 of 87

Drawing: 123 Sheet #: I

Description:

ligh PressureCoolant Inlection IVater Side Valve Dwg Safety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V23-0001 62A5 2 C 14 CK SA SYS A 0 DSBY RI DTJ-32 IIPCI TORUS SUPPLY LINE CHECK VALVE V23-0004 37E5 2 C 14 CK SA SYS A 0 CT-CC Q CT-CO Q VALVE,CIIK.IIPCICONDST TK SUP LINE V23-0014 44C1 2 C 4 CK SA SYS A O/C DSBY RI DTJ-20 VALVECIIK.IIPCI,,MIIN FLOW LINE V23-0049 65C6 I C 12 CK SA SYS A O/C DSBY RI DTJ-31 VALVE,CIIECKIIIPCI WATERI P216 EXH LINE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 48 of 87

EDrawing: 124 Valvc escit Sheet #: I

Description:

Reactor Core Iholation Cooiing~Steam Side Dwg Safety Viv Act Norm Safety CV 2410 30C6 N A I CA AO OIFC A C AT-1 AJI 3 BTC Q 3 FST Q 1,3 PIT 2Y' 3 RCIC STM SUP DRAIN LINE UPSTREAM%AUTO ISOLATION CV2411I 30C3 N A 0 CA AO OIFC A C AT-I AJ3 BTC Q 3 FST Q 2, 3 PIT 2Y 3 RCIC STM%SUP DRAIN LINE DOWNSTREAM AUTO ISOL CEV2435 - ------ 55130- N--- B 1F CGA AO 0/CIF-C -A --- C- BT-C - 0 3-FST Q 1,3 PIT 2Y 3 CONDENSATE PUM'%P I P-228 DISCIIARGE DRAIN TO CRW~

M02400 69F0 I A 4 GA MO 0 A 0/C AT-I AJ BTC Q PIT 2Y RCIC STEAM SUPPLY INBOARD ISOLATION T1 E401 - - - - - - - - - - - E9- I -1 A 4- -GA MO' 1- 0 A- -0/ C -AT-I- - -AJF - - - - - - - --

RTC Q PIT 2 RCIC STEAM SUPPLY OUTBOARD ISOLATION MO2404 35E1 N B 4 GL MIO C A 0/C RTC Q

[ITO Q 3 PIT 2Y 3 RCIC TU3RBINE STEAM SUPPLY ISOLATION M04538E0 N B 3 GA MO 0 P 0 PIT 2Y3 RCIC TURBINE STEAM SUPPLY STOP VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 49 of 87

Draivintg: 124 Shteet #: I Descriptiorr: Reactor Core 1sola(tiont CooJlinL,Steanm Sid/e

'alve Dwg sarety Viv Act Norm sairety Valve lDescrip~tion Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks M102426 57Cn N B 2 GL MIO C A 0 BTO Q 3 PIT 2Y 3 RCIC CONDENSER/LUBE OIL COOLER CLNG VTR SUPPLY PSE2418 66D0 N C 10 RPD SA SYS A O/C CT-RDR MOY 3, 15 RCIC TURBINE STEAM EXIIST RUPTURE DISC PSE2419 66DI N C 10 RPD SA SYS A O/C CT-RDR IMY 3, 15 RCIC TURBINE STEAM EXIIST RUPTURE DISC PSV2430 62C2 N C 2 RV SA C A O/C CT-SP 10Y2 3, 16 RCIC CONDENSER CLNG WTIt SUPPLY PRESSURE RELIEF PSV2474 3sCI N C 1.25 RV SA C A O/C CT-SP laY 3 RCIC CONDENSER IE-205 PRESSURE RELIEF V24-0008 oSC7 2 A/C 10 SCK MISA SYS/LO A O/C AT-I AJ CT-CC R DTJ-24 CT-CO R*

RCIC TURBINE STEAMI EXII TO TORUS STOP-CIIECK V24-0010 43116 N C 1.25 CK SA SYS A 0 DSBY RI 3 VALVE.CIIK,RCIC,GLAND SEAL CNIST PP IP228 V24-0012 58n6 N C 2 CK SA SYS A 0 DSBY RI 3 AIA'%EsCIIKRCICIP228 EXII LINE V24-0023 80C9 2 C 10 CK SA SYS A O/C CT-CC R DTJ-24 CT-CO R* DTJ-24 VALVE,CIIK,RCIC,IS203 EXII LINE V24-0046 74C7 2 A/C 3 CK SA SYS A O/C AT-I AJ DSBY RI DT.1-27 RCIC TURB LUBE OLJ CLR IS-203 EXII VAC BRKR VALVE V24-0047 74C7 2 A/C 3 CK SA SYS A O/C AT-I AJ DSBY RI DTJ-27 VAI.VE,CIIK,RCICIS203 EXII VAC BREAKER IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 50 of 87

Drawving: 12-4 Shleet #: I1

Description:

Reamyo Core [volation Coolinc SDteant Sidle Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cnt. Size Type Type Pos A/P Position Test Freq RR DJT Remarks XFV2443A 59E3 I C I XFC SA SYS A C AT-2 IOYI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-I PIT IOYI VR-OI PS-2443A SENSING LINE (RCIC STEAM PRESSURE)

XFV2443B 59E4 I C I XFC SA SYS A C AT-2 IOYI VR-OI CT-CC IOYI VR-OI CT-CO 1oYI VR-OI PIT IOYI VR-OI PS-2443B1 SENSING LINE (RCIC STEAM PRESSURE)

XFV2443C 59EI I C I XFC SA SYS A C AT-2 IOYI VR-OI CT-CC IOYI VR-0I CT-CO IOYI VR-I PIT IOYI VR-OI PS-2443C SENSING LINE (RCIC STEAM PRESSURE)

XFV2443D 59EO I C I XFC SA SYS A C AT-2 IOYI VR-OI CT-CC IOYI VR-OI CT-CO IOYI VR-OI PIT IOYI VR-OI PS-2443D SENSING LINE (RCIC STEAMI PRESSURE)

IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 51 of 87 I

Drawing: 12- Sheet #: .L

Description:

Reactor Core Isolation Coolingr Water Side IValve DsrpinDwg Safety Vlv Act Norm Safety Valv DecripionCoor Class Cat. Size Type Type Pos A/P Position Test Frcq RR DJT Remarks M02500 44E7 V B 6 GA MO1 0 A C BTC Q 3 PIT 2Y 3 RCIC PUM.%P CST SUCTION ISOLATION M02510 50B19 2 B 2 GL MO C A 0/C BTC Q BTO Q PIT 2Y RCIC PUMP, MINIMUM'% FLOW BYPASS VALVE M02511 546 N B 4 GA IMO 0 P 0 PIT 2Y 3 RCIC PUMIP DISCHARGE ISOLATION M2I6C6 I A 4 GA MO C A 0/C AT-I AJ6 BTC Q BTO Q PIT 2Y RCIC INJECTION HIEADER ISOLATION M0I2515 56D6 N B 4 GL, MO C P C PIT 2Y 3 RCIC PU.MP DISCHARGE TEST LINE ISOLATION M102516 57B0 2 B 6 GA MO C A 0 BTO Q PIT 2Y RCIC PUEMP TORUS SUCTION INBOARD ISOLATION M02517 48E4 2 B 6 GA MIO C A 0 BTO Q PIT 2Y RCIC PUMP TORUS SUCTION OUTBOARD ISOLATION PSV2501 45D9 N C I RV SA C A 0/C CT-SP 10Y2 3, 16 RCIC PUMP I P-226 SUCTION PRESSURE RELIEF V'25.Of0O1 53A8 2 C 6 CIK SA SYS A 0 MSY RI DTJ-32 VALVE,CIIK.RCIC,TORUS WTR SUCT LINE V25-0003 46E6 N C 6 CK SA SYS A 0 CT-CC RI' 3 CT-CO 03 VALVE,CIIK,RCIC,CND.ST STRG TK LINE 1ST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 52 of 87

Side Drawing: 125 Sheet #: I

Description:

Reactor Core Isolation Coolin' WVater Vlv Act Norm Satety Valve Dwg Satety Test Freq RR DJT Remarks Size Type Type Pos AlP Position Valve Description Coor Class Cat.

0 DSBY RI DTJ-20 3 C 2 CK SA SYS A 45117 N V25-0006 RCIC IIN FLOW LINE CIIECK VALVE 0 CTC. 1E R DTJ-28 C 4 CK SA SYS A 62C5 I DTJ-28 V 2 -0036- CTONME R VALVE, CIIK, FDWVTR, 1P226,EXII LINE Section 9 Page 53 of 87 IST Plan - Fourth 10 Year Interval - Revision 0

Drawing: 126 Sheet #: I

Description:

Standhi' Liquid Control Systemo Valve D)wg Safety VIv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks PSV2607 53D2 2 C I RV SA SYS A 0/C CT-SP 1oY SBlC ACCUMULATOR IT-219A OVER PRESSURE RELIEF PSV2609 531B3 2 C I RV SA SYS A O/C CT-SP 10Y SBLC ACCUMULATOR IT-219B OVER PRESSURE RELIEF V26-on04 57C3 2 C 1.5 CK SA SYS A O/C DSBY RI DTJ-22 VAl'VECIIKSBLCPUMlP IP230A OUTLET V26-0006 56116 2 C 1.5 CK SA SYS A O/C DSBY RI DTJ-22 SBLC INJECTION PUMIP IP-230B1 OUTLET CHECK VALVE v26-noo8 77E3 I A/C 1.5 CK SA SYS A O/C AT-I R CT-CC R DTJ-23 CT-CO R DTJ-23 VALVE,CIIK,SBLC OUTBOARD V26-0009 85C7 I A/C 1.5 CK SA SYS A O/C AT-I R CT-CC R DTJ-23 CT-CO R DTJ-23 VALVECIIK.SBLC INBOARD V26-0032 87C3 I R 1.5 GA MI 0 P 0 PIT 2Y SBLC IN.IECTION LINE MANUAL ISOLATION XS26i8A 67E6 2 D 1.5 GA EXP C/KL A 0 DT-E .2/2Y DT-REC 2Y SBLC SQUID VALVE XS261811 67E6 2 D 1.5 GA EXP C/KL . A 0 DT-E .2/2Y DT-REC 2Y SBLC SQUIB VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 54 of 87

Drawinlg: 127 Sheet #: I

Description:

Reactor Water Cleanui Svvtem,,

Valve Dwg Saftety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos AIP Position Test Freq RR DJT Remarks M02700 84E3 I A 4 CA MO 0 A C AT-I AJ BTC Q PIT 2Y RNNCU INLET INBOARD ISOLATION M02701 7SE3 I A 4 GA 10 0 A C AT-I AJ BTC Q PIT RNVCU SUCTION OUTBOARD ISOLATION

_ _ _ _ _ _ _ _ _ _ _ _ _ _I__ _ _ _ _ _ _ _ _O_0_ _ _ _C_ _T- I-__

M102740 46FO I A 4 GL 'I0 0 A C AT-I AJ 6 BTC Q PIT 2Y RWCU RETURN HEADER OUTBOARD ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 55 of 87

I Drawting: 129 Sheet #: I Dcscription: River Water Sphnnli'S;'stemn Intake Strawtnre Valve lVale Dro Safety Vlv Act Norm Safety Valve Description Coor Class Cat Size Type Type Pos A/P Position Test Freq RR DJT Remarks AV2909A 62C5 3 C 3 AV SA SYS A C CT-CC Q CT-CO Q IP-l 17A DISCIIARGE AUTO VENT AV290913 49C6 3 C 3 AV SA SYS A C CT-CC Q CT-CO Q Ir-I 117R DISCIIARGE AUTO VENT AV2909C 62C5 3 C 3 AV SA SYS A C CT-CC Q CT-CO Q IP-1 17C DISCIIAR(;E AUTO VENT AV29/9D 29C5 3 C 3 AV SA SYS A C CT-CC Q CT-CO Q IP-117D DISCHARGE AUTO VENT AV2909E 5915 N C 3 AV SA SYS A C CT-CC Q 3 CT-CO Q 3 IP-1 17A/C DISCIIARGE AUTO VENT AV2909F 50E9 N C 3 AV SA SYS A C CT-CC Q 3 CT-CO Q 3 IP-l 17B/D DISCHARGE AUTO VENT V29-0001 71C6 3 C 18 CK SA SYS A O/C CT-CC Q CT-CO Q RIVER WATER PUMP r-I 117A DISCHARGE CIIECK VALVE V29-)003 60C6 3 C 18 CK SA SYS A O/C CT-CC Q CT-CO Q RIVER WATER PUMP I P-1 17C DISCIIARGE CIIECK VALVE V29-0005 51C6 3 C 18 CK SA SYS A 0/C CT-CC Q CT-CO Q RIVER WATER PUMP IP-1 17B DISCHARGE CHECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 56 of 87

Drawi'ing: 129 Sheet #: L

Description:

River Water Stinnli' Svvtent hntake Structure Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V29-0007 40C6 3 C 18 CK SA SYS A O/C CT-CC Q CT-CO Q RIVER WATER PUMP IP-117D DISCIIARGE CIIECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 57 of 87

Drawing: 130 Sheet #: 9

Description:

Sen'ke Air Sistem Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V30-0287 67C4 2 A I GA NM LC P C AT-I AJ DRYWELL BREATHING AIR SUPPLY OUTBOARD ISOL IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 58 of 87

Drawing: 132 Sheet #: I

Description:

Diesel GeneratorSvstents Valve c Dwg Sarety VIv Act Norm Satefy Valve Description Coor Class Cat. Size Type Type Pos AIP Position Test Freq RR DJT Remarks PSV3221A 87F4 Y C 0.5 RV SA SYS A O/C CT-SP IOY 3 AIR RECEIVER IT-I IsA PRESSURE RELIEF VALVE PSv322111 87117 Y C 0.5 RV SA SYS A O/C CT-SP IoY 3 AIR RECEIVER IT-I 15BiPRESSURE RELIEF VALVE PSV3222A 78F2 Y C 0.5 RV SA SYS A O/C CT-SP toY 3 AIR RECEIVER IT-Il 6fA PRESSURE RELIEF VALVE PSV3222n 78117 Y C 0.5 RV SA SYS A O/C CT-SP toY 3 AIR RECEIVER IT-I 1611 PRESSURE RELIEF VALVE PSV3223A 72F2 Y C 0.5 RV SA SYS A 0/C CT-SP toY 3 AIR RECEIVER IT-I 17A PRESSURE RELIEF VALVE PSV3223B 72B7 Y C 0.5 RV SA SYS A O/C CT-SP IoY 3 AIR RECEIVER IT-I 171 PRESSURE RELIEF VALVE v32-00n5 361B2 Y C 1.5 CK SA SYS A 0 CT-CC Q 3 CT-CO Q 3 VAIVECIIK,I)IESEI, FUEL OILIP044B DISCHARGE V32-0010 25113 Y C 1.5 CK SA SYS A 0 CT-CC Q 3 CT-CO Q -3 VALVE.CIIKDIESEL FUEL OIL. P044A DISCIIARGE v'32-00i9 49CI N C 1.5 CK SA SYS A O/C CT-CC Q 3 CT-CO Q 3 VALVE,CIIK,DIESEL OILIT037B FOOT VALVE V32-0021 4914 N C 1.5 CK SA SYS A O/C CT-CC Q 3 CT-CO Q 3 VALVE,CIIK,DIESEL OIL,IT037A FOOT VALVE v32-0032 81112 Y A/C 0.75 CK SA SYS A C AT-6 2Y 3 CT-CC Q 3 CT-CO Q 3 IK-1OC DISCHARGE CHECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 59 of 87

Drawing: 132 Sheet #: I

Description:

Diesel Generator Systents Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V32-0034 82D2 Y A/C 0.75 CK SA SYS A C AT-6 2Y 3 CT-CC Q 3 CT-CO Q 3 IK-l0l) DISCHARGE CHECK VALVE V32-0036 86E9 Y A/C 0.75 CK SA SYS A C AT-6 2Y 3 CT-CC Q 3 CT-CO Q 3 I K-IA DISCHARGE CIIECK VALVE TO IT-I 15A V32-0039 79E9 Y A/C 0.75 CK SA SYS A C AT-6 2Y 3 CT-CC Q 3 CT-CO Q . 3 IK-IOA DISCHARGE CIIECK VALVE TO IT-I 16A V32-0043 85F3 N C 2 CK SA SYS A C CT-CC Q 3 CT-CO Q 3 AIR RECEIVER IT-I 15A OUTLET CHECK VALVE V32-0t145 80F3 N C 2 CK SA SYS A C CT-CC Q 3 CT-CO Q 3 AIR RECEIVER IT-I 16A OUTLET CHECK VALVE V32-0047 86114 V A/C 0.75 CK SA SYS A C AT-6 2Y' 3 CT-CC Q 3 CT-CO Q 3 IK-lO1 DISCHARGE CHECK VALVE TO IT-I 151 V32-0048 791B4 Y A/C 0.75 CK SA SYS A C AT-6 2Y- - 3 CT-CC Q 3 CT-CO Q 3 I K-lIlB DISCIIARGE CIIECK VALVE TO IT-I 1611 v32-0052 85118 N C 2 CK SA SYS A O/C CT-CC Q 3 CT-CO Q 3 AIR RECEIVER IT-I 15B OUTLET CHECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 60 of 87

Drawing: 132 She et #: I

Description:

Diesvel GeneratorSvstent.

Valve Dwg Safety VIv Act Norm Safely Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V32-0054 80B8 N C 2 CK SA SYS A O/C CT-CC Q 3 CT-CO Q 3 AIR RECEIVER IT-I 1611 OUTLET CHECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 61 of 87 4

Drawing: 132 Sleet #: 2

Description:

Dievel Generator Sstents Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos AIP Position Test Freq RR DJT Remarks SV3261A 19C8 N B 1.5 2WY SO C A 0 NA NA 2, S5 SBDG IG-31 EMERG START AIR SUPPLY ISOLATION SV3261 n 19C4 N B 1.5 2W\Y SO C A 0 NA NA 2, S5 SBDG 1G-31 NORMAL START AIR SUPPLY ISOLATION SV3261C 15C5 N, n 1.5 2WY SO C A 0 NA NA 2, S5 SBDG I G-31 STARTING AIR SUPPLY LINE VENT SV3262A 19C8 N B 1.5 2WY SO C A 0 NA NA 2,S5 SI)DG I1-21 ENMERC START AIR SUPPLY ISOLATION sV3262B 19C4 N n 1.5 2WY SO C A 0 NA NA 2,S5 S1DG IG-21 NORMAL START AIR SUPPLY ISOLATION SV3262C 15C5 N B 1.5 2NVY SO C A 0 NA NA 2, S5 SBDn IG-21 STARTING AIR SUPPLY LINE VENT IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 62 of 87

Drawing: 137 Sheet #: IL

Description:

Radwvaste StyinnSystent Valve Dwg Satety Viiv Act Norm Safety Valve Description Coor Class Ca t. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV3704 751F8 2 A 3 GA AO OIFC A C AT-I AJ BTC Q FST Q I PIT 2 DRYWELL, FLOOR DRAIN SUMP INBOARD ISOLATION CV3705 71IF8 2 A 3 GA AA 0OFC A C AT-I AJ BTC Q FST Q I PIT 2Y DRYWELL, FLOOR DRAIN SUM,%P OUTBOARD ISOLATION CV3728 7t)DI 2 A 3 CA AO O/FC A~ C AT-I AJ BTC Q FST Q I PIT 2Y DRYWELL, EQUIP DRAIN SUMP INBOARD ISOLATION CV3729 67D1 N A 3 GA AO O/FC A C AT-I A.J 3 BTC Q 3 FST Q 2,3 PIT 2Y 3 DRYWELI, EQUIP DRAIN SUMP OUTBOARD ISOLATION 1ST Plan - Fourth 10 Year Interval - Revision 0Seto9Pae6of8 Section 9 Page 63 of 87

Drawing: 143 Sheet#f: I

Description:

ContainrnettAtiniospliere Control Sivtentt Valve esrpinDwg Safety Sie Viv Act Norm Safety VleDsrpinCoor Class Ca. Sz Type Type Pos AJP Position Test Freq RR DJT Remarks IS260A-BAI, 68C5 2 A 0.375 BAL SO C A C AT-1 AJ BTC Q 2 FST Q PIT 2Y TIP DRIVE IS-218A BALL VALVE IS260A-SIIE 68C4 2 D 0.375 SIT EXP O/IL A C DT-E .2/2Y BT-REC 2Y TIP DRIVE IS-218A~SHEAR VALVE 1S260H-BAL, 75C5 2 A 0.375 BAL SO C A C AT-1 AJ1 BTC Q FST Q I PIT 2Y TIP DRIVE IS-218BH HALL VALVE lS260B-SIIE 75C4 2 D 0.375 SII EXP O1IKL A C DT-E .2I2Y DT-REC ZY TIP DRIVE IS-218H SIIEAR V'ALVE 1S26OC-BAI, 72C5 2 A 0.375 HAL, SO C A C AT-I AJ HTC Q FST Q I PIT 2Y TIP DRIVE IS-218C HALL VALVE 1S260C-SIIE 72C4 2 D 0.375 SHI EXP OIKL A C DT-E .2/2Y DT-REC 2Y TIP DRIVE IS-218C SHIEAR VALVE CV4300 77C1 2 A IS HTF AO C/FC A C AT-1 AJ 6 AT.7 Q HTC Q 8 FST Q I PIT 2Y TORUS V'ENT LINE INBOARD ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0Seto9Pae6of8 Section 9 Page 64 of 87

Drawing: 14.3 Sheet #: I Descriptionl: Co7ntainnint Atntolmyvnere Co7ntrol.Sy-vent Valve Dwg! Safety Vlv Act No rm Safety Valve lDescription Coor Class Cat. Size Type Type Pos .ur Position Test Freq RR DJT Remarks CV4301 83C1 2 A 18 BTF AO C/FC A C AT-I AJ 6 AT-7 Q BTC Q 8 FST Q PIT 2Y TORUS VENT LINE OUTBOARD ISOLATION

_ _ _ _ _ _ _ _ _ _ _ _2__ _ _ _ _ _ _ _ _A__ _ _ _ _ _ _ _ _ _ _ - _-_ _ _ _ _ _ _ _ _ _ 6 _

CV4302 73DO 2 A Is BTF AO C/FC A C AT-I AJ 6 AT-7 Q BTC Q 8 FST Q PIT 2Y DRYWELL VENT LINE INBOARD VENT CV4303 80DO 2 A 18 BTF AO C/FC A C AT-I AJ 6 AT-7 Q BTC Q 8 FST Q I PIT 2Y DRYWELL VENT LINE OUTBOARD ISOLATION CV4304 77A8 2 A 20 BTF AO CIFO A 0 AT-I AJ 6 BTC Q BTO Q BT-VOP R FST Q I PIT TORUS VACUUM.I BREAKER V-43-169 ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 65 of 87

Drawing: 143 Sheet #: I

Description:

Co,:tainnent A tmo.vnlhere Coiitrol ,Svstens Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV430i5 78A8 2 A 20 BTF AO C/FO A O AT-I AJ 6 BTC Q BTO Q BT-VOP R FST Q I PIT 2Y TORUS VACUUlMlI BREAKER V-43-168 ISOLATION CV4306 21C4 2 A 18 BTF AO C/FC A C AT-I AJ 6 AT-7 Q BTC Q 8 FST Q PIT 2Y CONTAINMENT PURGE SUPPLY ISOLATION VALVE

_ _ _ _ _ _ _ _ _ _ _ _2__ _ _ _ _B _A T_ _O___ _ _ A_ _ _ _ T-I__ _ _ _ _ _ _ _ _ 6 _

CV4307 29C4 2 A 18 BTF AO C/FC A C AT-I AJ 6 AT-7 Q BTC Q 8 FST Q PIT 2Y DRYWELL PURGE INLET ISOLATION VALVE

_ _ _ _ _ _ _2 _8_2__ 9_ _1 _T_ 8_

_A__ _ _ _ _ _ _ _ C _ _ -_ _ _ _ _ _ _ _ _ _ _ 6 _

CV4308 29B8 2 It 18 BTF AO C/FC A C AT-I A.l 6 AT-7 Q BTC Q 8 FST Q PIT 2Y TORUS PURGE INLET ISOLATION VALVE CV4309 78Cn 2 A 2 BTF AO C/FC i C AT-I AJ BTC Q FST Q I PIT 2Y INRID TORUS VENT BYPASS LINE ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 66 of 87

Draswing: 143 Sheet #: I

Description:

Contani,,,,eirtAt,,oVnphereCoitlrolSVStem Valve Dwg Safety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV4310 72C9 2 A 2 GA AO C/FC A C AT-I AJ BTC Q FST Q I PIT 2Y INBOARD DW VENT CV-4302 BYPASS

_CV4311

_ _ _ _ _ _ _ _ _ _ _ _2__ 33D1 _ _6__

2 A _ _ 6_ _ GA

_C/_ AO C_

C/FC A_

A C_

C A-AT-I-I - -AJ - - - - - - - -

BTC Q FST Q I PIT 2Y CONTAINMENT N2 MAKEUP SUPPLY ISOLATION CV4312 _ _ _ _ _ _ _ _ _ _2_A_6__

37C7 2 _A _ _ 6_ _C_

GA _CACAT-AO C/FC A C __AT.1I -- _ _ AJ _ _ _ _ _ _ _

BTC 2 FST I PIT 2Y DRYWELL NITROGEN IAKEUP INLET ISOLATION

_ _ _ _ _ _ _ _ _ _ _ _ _2_A__ _ _A__ _ _ _ _ _ _ _A_ _ _AT- __ I -- _ _ _ _ _ _ _ _ _

CV4313 33C8 2 A 6 GA AO C/FC A C AT-1 AJ BTC 2 FST I PIT 2Y TORUS NITROGEN MAKEUP INLET ISOLATION CV4327A 72BS 2 A/C 18 CK SAP SYS A 0 AT-4 R CT-CC Q CT-CO R CT-VSP R PIT 2Y VAI.VE,CIIK,VAC IBRKTORUS/DRYWELL VAC BREAKER IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 67 of 87

Draw'ing: 143 Sheet #: I

Description:

ConfantinrentAtltniosphere Control Srstem, Valve Dwg sartety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV4327B 72118 2 A/C 18 CK SAP SYS A O AT4 R CT-CC Q CT-CO Q CT-VSP R PIT 2Y VAI,VE,CIIKVAC BRKTORUS/DRYNVELL VAC BREAKER CV4327C 72B8 2 A/C 18 CK SAP SYS A 0 AT-4 R CT-CC Q CT-CO Q CT-VSP R PIT 2Y VAI,VE,CIIK,VAC BRKTORUS/DRYWELL VAC BREAKER CV4327D 72BS 2 A/C 18 CK SAP SYS A 0 AT-4 R CT-CC Q CT-CO Q CT-VSP R PIT 2Y VALVE,CIIKVAC BRKTORUS/DRYWELL VAC BREAKER CV4327F 72B8 2 A/C 18 CK SAP SYS A 0 AT4 R CT-CC Q CT-CO Q CT-VSP R PIT 2Y VAIVE,CIIK,VAC BRKTORUS/DRYWVELL VAC BREAKER CV4327C 72B8 2 A/C 18 CK SAP SYS A 0 AT-4 R CT-CC R CT-CO CT-VSP R PIT 2Y VALVE,CIIKVAC BRKTORUS/DRYWELL VAC BREAKER 1ST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 68 of 87

Drawnei1g: 143 Sheet #: I

Description:

Cnut niti,,,e1tt A ftwo.nere Control S;'ste,,,

Valve Dwg Satety Vlv Act Norm Satety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV432711 72138 2 A/C 18 CK SAP SYS A 0 AT.4 R CT-CC Q CT-CO Q CT-VSP R PIT 2Y VALVE,CIIKVAC BRKTORUS/DRYWELL VAC BREAKER CV4357 851B8 2 A 8 BTF AO CIKL A C AT-I AJ 6 AT-7 R BTC R DTJ-10 FST R DTJ-10 PIT 2Y TORUS HARD PIPE VENT LINE ISOLATION

_ _ _ _ _ _ _ _ _ _ _ _ _2__ _2_GA__ _ _ _ _ _ _ _ACAT- __ I -- _ _ _ _ __J_ _

CV4371A 51E1 2 A 2 GA AO O/FC A C AT-I AJ BTC Q FST Q I PIT 2Y DW VALVES N2 SUPPLY ISOLATION (FROM IT-128)

CV4371C 69E2 2 A 2 GA AO O/FC A C AT-I AJ BTC Q FST Q I PIT 2Y TORUS/DW VACUUM BKR N2 SUPPLY ISOLATION

_ _ _ _ _ _ _ _ _ _ _ _ _2_A_2_GAAO__ _ _ _ _ ACAT- __ - -- _ _ _ _ __J_ _

CV4378A 56D0 2 A 2 GA AO O/FC A C AT-I AJ BTC Q FST Q I PIT 2Y N2 COMPRESSOR IK-14 DW SUCTION ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 69 of 87

Drawinsg: 143I Sheet #: I fAtmnt~xlere ControlSystent Descriptinit: Corntfainnenft Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV4378B 54Dn 2 A 2 GA AO O/FC A C AT-I AJ BTC Q FST Q I PIT N2 CO'MPRESSOR I K-14 DWSl1CTION ISOLATION PSEJ357 87B8 N A 8 RPD SA C A C AT-7 2Y 3 TORUS HARD PIPE VENT LINE RUPTURE DISC V43-0032 32B10 N C 0.5 CK SA SYS A 0 NA NA 2 VAIVE,CIIK,VAC BRK,CV4305,AIRSUPPIX V43.0035 59B0 N C 0.5 CK SA SYS A 0 NA NA 2 VALVE,CIIKVAC BRK,CV4305,AIRSUPPLY V43-016O8 78A2 2 A/C 20 CK SA SYS A O/C AT-I AJ 6 CTC'ME Q CTONIE 2 CT-VSP R PIT 2y VAI.VE,CIIK,VAC BRKTORUS/RB VACUUM BREAKER V43-0169 77A2 2 A/C 20 CK SA SYS A O/C AT-I AJ 6 CTCM1E Q CTONIE 2 CT-VSP R PIT 2Y VAI.VE,CIIK,VAC BRKTORUS/RB VACUUM BREAKER

_- _ _ _ _ _ _ _ _ _ _ _ _N__ _ _C_0.5_ _ _ _ _ _A_ _CA_0_ _C_ _ _ _ _ _ _ _ _ _

V43-0441 8 5C6 N A/C 0.5 CK SA C A O/C AT-6 2Y 3 CT-CC R 3 CT-CO R* 3,4 VALVE,CIIK,TORUS WXII,CV4300 AND CV4357,AIS IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 70 of 87

Drawing: 143 Sheet #: 1

Description:

CotnairintentAtmtosrphere ControlSstemii Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V43-0503 59E0 2 A 0.375 CK SA SYS A C AT-I R CT-CC R DTJ-12 CT-CO R* DTJ-12 4 TIP INDEXER N2 PURGE SUPPLY CHECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 71 of 87

Draiving: 143 Sheet #: 3

Description:

ContainmnentAtmnosph1ere Control .Ssient Valve Dwg Safety Vlv Act Norm Satety Valve Description Coor Class Ca t. Size Type Type Pos A/P Position Test Freq RR DJT Remarks M04320A 37D6 N B 2 CA MO C A O/C BTC Q BTO Q PIT 2Y CAD N2 SUPPLY REGULATOR PCV.4320A OUTLET ISOL

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _2 _ _ _ _ _ __OC_ C_ _A_0/ _ _ _ __C_ _

5142n37E6 IN n 2 (;A NIO C A O/C IITCQ BTO 0 PIT 2Y CAD N2 SUPPLY REGULATOR PCV-4320B OUTLET ISOL M04323A 47D6 N n 2 Cl 10 C A O/C BTC Q BTO Q PIT 2Y VAILVEISOLCADIT007A-IICAD N2 FLOW M0432313 47E2 N B 2 GL MO C A O/C BTC Q BTO Q PIT 2Y VAI.'EISOl,.CADIT007A-IICAD N2 FLOW PSV4336 54D8 N C 2 RV SA C A 0 CT-SP 10Y 3 SV4331A 411B3 2 A 2 GA SO C/FC A O/C AT-I AJ BTC 0 BTO 0 FST Q 1 PIT 2Y LOWER DRYWELL SPRAY CAD N2 INBOARD ISOLATION SV4331 n 38112 N A 2 GA SO C/FC A O/C AT-I AJ BTC Q BTO Q FST Q I PIT 2Y LOWER DRYWELL SPRAY CAD N2 OUTBOARD ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 72 of 87

Drawing: 143 Sheet #: 3

Description:

Contain,,nent A finosphiere Control Sivsttni Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks SV'4332A 41119 2 A 2 GA SO C/FC A 0/C AT-I AJ BTC Q BTO Q FST Q I PIT 2Y UPPER DRYWELL SPRAY CAD N2 INBOARD ISOLATION SV4332B 3R1B9 N A 2 GA SO C/FC A 0/C AT-I AJ BTC Q BTO Q FST Q I PIT 2Y UPPER DRYWELL SPRAY CAD N2 OUTBOARD ISOLATION SV4333A 31C5 2 A 2 GA SO CIFC A 0/C AT-I AJ BITC Q BTO Q FST Q I PIT 2Y WEST TORUS SPRAYlIIDR CAD N2 SUPPLY INBOARD ISOL SV4333B1 38C5 N A 2 GA SO C/FC A 0/C AT-I AJ BTC Q BTO Q FST Q I PIT 2 WEST TORUS SPRAY IlDR CAD N2 SUPPLY OUTBOARD ISO SV4334A 41Dt) 2 A 2 GA SO C/FC A C AT-I A.1 BTC Q BTO Q FST Q I PIT 2Y NORT11 TORUS SPRAY MEADER CAD N2 SUPPLY INBD ISO IST Plan - Fourth 10 Year Interval - Revision 0Seto9Pae7of8 Section 9 Page 73 of 87

Drawing: 143 Sheet #: 3

Description:

ContainimentAtlmosphereConltrolSi'stenm Valve Dwg Satety Viv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks SV4334B 38D10 N A 2 GA SO C/FC A C AT-I AJ BTC Q BTO Q FST Q I PIT 2Y NORTH TORUS SPRAY HEADER CAD N2 SUPPLY OUTBD IS V43-0082 36B4 N C 2 CK SA SYS A 0 CT-CC Q CT-CO Q VAlVE,CIIK,CAD,SV433 I B,CNTMlT SPRAY IIDR V43-0084 35C0 N C 2 CK SA SYS A 0 CT-CC Q CT-CO Q VAlVE,CIIK,CAD,SV43321B,CNTMNIT SPRAY IIDR V43-0086 35C6 N C 2 CK SA SYS A 0 CT-CC Q CT-CO Q VALVECIIK,CAD,SV4333B,TORUS SPRAY IIDR V43-0n88 35DI N C 2 CK SA SYS A 0 CT-CC Q CT-CO Q VALVE,CIIK,CAD,SV4334B,TORUS SPRAY IIDR IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 74 of 87

Drawing: 143 Sheet #: 4

Description:

Containnment Atmosphere Control Swstem Valve Dwg Safety Vfv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V43-0214 59E4 2 A 2 SCK MSA C/LO A C AT-I R CT-CC R CT-CO R DRN'WELL NITROGEN SUPPLY HEADER ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 75 of 87

Drawing: 14L6 Sheet i:L

Description:

Service Wafer Systen Pnmntyhotiie Valve esrpinDwg Safety Vlv Act Norm Safety VleDsrpinCoor Class Cat. Size Type Type Pos AlP Position Test Freq RR D.JT Remarks CV4909 631F5 3 B 24 BTF AO C1/OfFC A C BTC Q FST Q PIT 2Y RIVER WATER RADWVASTE DILUTION LINE ISOLATION CV'49I0A 721F4 3 II 24 BTF AO OIFC A C BTC Q IFST Q PIT 2Y RADWASTE DILUTION LINE ISOLATION FROM RVSYS A CV491011 721F5 3 11 24 BTF AO O/FC A C BTC Q FST QI PIT 2Y RADWASTE DILUTION LINE ISOLATION FROM RWV SYS II CV4914 67EI 3 II 20 BTF AO OIFO0 A 0 BTO Q FST QI PIT ZY IP-11711/D1INLETTO STILIIN'GBASIN CVN4-915

- - - - - - - - - - - - E0 - 3- I 20- IBTF A-O 0/F0 -A - - BT-O - - -Q- - - - - - - - - -

FST QI PIT 2 1P-Il17A/C INLET TO STILLING BASIN V46-06Oi - - - - - - - - - - - -5311I 3 C -1 2 -CK -SA 'Sys- A- -0/C- -Cr-C C - Q- - - - - - - - --

CT-CO Q RIIRSNN PUM'%P I P-22D DISCHIARGE CHECK VALVE V46-0013 591B1 3 C 12 CK SA SYS A 0/C CT-CC Q CT-CO Q RllRSNN PUMP IP.2211 DISCIIARGF CHIECK VALV'E V'46-0018 65112 3 C S CK SA SYS A 0/C CT-CC Q CT-CO Q I P-99B1 DISCHIARGE CHECK VALVE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 76 of 87

Drawing: 1476 S3eetC#: DescriptioS: Servi/e PCmpose SA CaterSCTtC Valve Dwg Safety VIV Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks V46-0021 711B2 3 C 8 CK SA SYS A O/C CT-CC Q CT-CO Q IP-99A DISCIIARGE CHECK VALVE V46-0026 77B1 3 C 12 CK SA SYS A O/C CT-CC Q CT-CO Q RHIRSW PUMP IP-22C DISCHARGE CIIECK VALVE V46-0030 831B1 3 C 12 CK SA SYS A 0/C CT-CC Q CT-CO Q RIIRS11PUNMP IP-22A DISCHARGE CHECK VALVE

[ST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 77 of 87

Drawing: 157 Sheet #: I

Description:

DrywsellCoolln' WlaterSVstenm Valve Dwg Safety Vlv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks CV5704A 64F4 2 A 4 CL AO O/FO A C AT-I AJ 6 BTC Cs DTJ-06 PIT 2Y DRYWEL.l COOLING LOOP A WELL WATER RETURN ISOL CV5704B 61F4 2 A 4 GL AO O/FO A C AT-1 AJ 6 BTC CS DTJ-06 PIT 2Y DRYWELL COOLING LOOP B WELL WATER RETURN ISOL CV571SA 84B1 2 A 4 GL AO O/FO A C AT-I AJ 6 BTC CS DTJ-06 PIT 2Y DRYWELL COOLING LOOP A WELL WATER SUPPLY ISOL CV5718B 82B2 2 A 41 GL AO O/FO A C AT-I AJ 6 BTC CS DTJ-06 PIT 2Y DRYWEIL COOLING LOOP B WELL WATER SUPPLY ISOI, V57-0075 69F1 2 A 3 GA INI C/LC P C AT-I AJ 6 DW CLNG LOOP A BACKWASII SUPPLY DOWNSTREAM ISOL V57-0076 70E6 2 A 3 GA MI C/LC P C AT-I A.l 6 D%% Cl,NG LOOP n BACKWAShI SUPPLY DOWNSTREAM ISOL V57-0077 81A9 2 A 3 GA NI C/LC P C AT-I AJ 6 DW CLNG LOOP A BACKWASH RETURN TO EQUIP DRN SUMP v57-0078 8IA5 2 A 3 GA NI C/LC P C AT-I AJ 6 DW CLING LOOP B BACKWASH RETURN TO EQUIP DRN SUMP IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 78 of 87

Drassing: 173 Sh/eet #: L

Description:

Standby Filter Unit Control Ruiildnh Valve Dwg Safety Vlv Act Norm Sarety Valve Description Coor Class Cat Size Type Type Pos A/P Position Test Freq RR DJT Remarks PSV7333A 58AS N C I RV SA C A O/C CT-Sr IoY 3 AIR RECEIVER IV-S-12 OVER PRESSURE RELIEF PSV7333B 74A8 N C I RV SA C A O/C CT-SP toY 3 AIR RECEIVER IV-S-13 OVER PRESSURE RELIEF V73-0006 63BI N A/C I CK SA SYS A C CT-CC Q 3 CT-CO Q 3 VALVE,CIIK,CB II&V,IVS012 PLT INSTRU AIR SUP V73-0007 63B1 N C I CK SA SYS A C CT-CC Q 3 CT-CO Q 3 VALvECIIKCB Il&VIVS012 PLT INSTRU AIR SUP V73-0016 81BI N C I CK SA SYS A C CT-CC Q 3 CT-CO Q 3 VALVE,CIIK,CB II&V,IVS013 PLT INSTRU AIR SUP V73-0017 81110 N C I CK SA SYS A C CT-CC Q 3 CT-CO Q 3 VALVECIIK,CB II&V,IVS013 PLT INSTRU AIR SUP V73-0032 81A7 N C I CK SA SYS A 0 CT-CC Q 3 CT-CO Q 3 VALV'E,CIIK,CB II&V,IK004 AIR EXII LINE V73 0n33 81A7 N C I CK SA SYS A 0 CT-CC Q 3 CT-CO Q 3 VALVE,CIIK,CB II&V,IK004 AIR EXII LINE V73.0034 63A7 N C I CK SA SYS A 0 CT-CC Q 3 CT-CO Q 3 VALVE,CIIK,CB Il&V,lK003 AIR EXII LINE V73-0035 63A7 N C I CK SA SYS A 0 CT-CC Q 3 CT-CO Q 3 VALVE,CIIK,CB II&VIK003 AIR EXII LINE IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 79 of 87

Drawinig: i8i Sheet #: L

Description:

Coont anintmet A tinovnlpere Afonitorinty Sctein Valve Dwg Safety VIv Act Norm Safety Valve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks SV8IOIA 54D9 2 A I GI, SO O/FC A C AT-I AJ BTC Q 12 FST Q DRYWELL #1 SAMPLE LINE ISOLATION

_ _ _ _ _ _ _ _ _47_ _9_2_ _I__ _ _SO__ _ _ _ _ _ _ C__ - _-_ _ _ _ _ _ _ _ _ _ _ _

SV81 01B 47D9 2 A I CL SO O/FC A C AT-I AJ BTC Q 12 FST Q DRYWELL tI SAMPLE LINE ISOLATION SV8102A 57D9 2 A I GL SO O/FC A C AT-I AJ BTC Q 12 FST Q DRYWELL #I SAMPLE LINE ISOLATION SV810213 _ _ _ _ _ _44119_2_A 44D9 2 A _ _ II__

_0__ GL _ _ O/FC SO _ _ A_

A C_

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AT-I _ _ AJ_ _ _ _ _ _ _ _

BTC Q 12 FST Q I DRYWELL HI SAMPLE LINE ISOLATION

_ _ _ _ _ _ _ _ _ _ _ _ _2_A__ _ _LSO__ _ _ _ _ ACAT- __ I -- _ _ _ _ _ _ _ _ _

SV8103A 54D3 2 A I GL SO OIFC A C AT-I AJ BTC Q 12 FST Q DRYWELL #2 SAMPLE LINE ISOLATION SV810t3B 46D3 2 A I GL SO O/FC A C AT-I AJ BTC Q 12 FST Q DRYWELL t2 SAMPLE LINE ISOLATION

_ _ _ _ _ _ _ _ _6_ _3_2_AICLSO__ _ _ _ _ A_ C_ A- I-___ _ _ _ _ _ _ _ _ _

SV81tl4A 5fiD3 2 A I GL SO O/FC A C AT-I AJ BTC Q 12 FST Q DRYWELL H2 SAMPLE LINE ISOLATION 1ST a_n_ __Pl __-o-_ R e v i s i o n_0_S e c t i on_9_P a ge_8 0_ o f 7

_8 IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 80 of 87

Drawting: .L8L Sheet #: I

Description:

Co,,tai,,,,,e,,t Atmyosphere Afonritori,,t, Srvtent VSlv esrtinDwg Safety Ct Sie VIV Act Norm Sft VleDsrpinCoor Class Ca. Sz Type Type Pos A/P Position Test Freq RR DJT Remarks SVSIO4II 44D)3 2 A I GL SO 0/FC A C AT-1 AJ BTC Q 12 FST Q DRYWELL 02 SAMPLE LINE ISOLATION SV8105A 531)0 2 It 1 GL SO 0/PC A C AT-I AJ BTC Q 12 FST Q DRYWELL SAMPLE RETURN LINE ISOLATION SYBIOSII 461)0 2 A I GL SO O/FC A C AT-I AJ BTC Q 12 FST Q DRY'WELL SAMPLE RETURN LINE ISOLATION SV8106A 56D0 2 A I CL SO O/FC A C AT-I AJ BTC Q 12 FST Q DRYW~ELL SAMPLE RETURN LINE ISOLATION

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`SV 8106f 441)0- 2- -A I GL C -SO 0-/FC -A - C- -AT AJ----------

BTC Q 12 FST Q DRYWELL SAMPLE RETURN LINE ISOLATION SV8107A 45C5 2 A I GL SO OIFC A C AT-1 AJ BTC Q 12 FST Q CAM SYSTEM%A TORUS RETURN LINE INBOARD ISOLATION SVSI07II 45C5 2 A I GL SO 0/FC A C AT-I AJ BTC Q 12 FST Q CAMI SYSTEM B TORUS RETURN LINE INBOARD ISOLATION IST Plan - Fourth 10Year Interval - Revision 0Seto9Pae8of7 Section 9 Page 81 of 87

IDrawing: 18) S/ieel #: I Des cription: Co,,tai,,,,,ent Atnstosnhere ,¶foniitori,,i' Sw'ent IVaive Dwgc Safety Vii' Act Norm Safety IValve Description Coor Class Cat. Size Type Type Pos A/P Position Test Freq RR DJT Remarks SV~iOSA 56C5 2 A I GIL SO OIFC A C AT-i A.J RTC Q 12 FST 0 CAM.% SYSTEM A TORUS RETURN LINE OUTBOARD ISOL SV8iO08I 43C5 2 A I GIL SO OIFC A C AT-i AJ BTC Q 12 FST QI CAM'% SYSTEM B TORUS RETURN LINE OUTBOARD ISOL 5V8109A 53C1 2 A I GI, SO OIFC A C AT-I AJ BTC Q 12 FST Q CAM,% SYSTEM A TORUS SAMIPLE LINE INBOARD ISOLATION SVRIO9iI 47C1 2 A I GI, SO O/FC A C AT-I AJ BTC Q 12 FST Q CA'M SYS B TORUS SAM,%PLE LINE INBOARD ISOLATION SV811OA 57C1 2 A I GIL SO O/FC A C AT-I AJ BTC Q 12 FST Q CAM SYSTEM A TORUS SAMPLE LINE OUTBOARD ISOL SVRIIOB 43C1 2 A I GIL SO O!FC A C AT-1 AJ BTC Q 12 FST Q 1 CAM,% SYSTEM B TORUS SAMPLE LINE OUTBOARD ISOL IST Plan - Fourth 10Year Interval - Revision 0Seto Section 99 Page Pae882 of of 877

Drawintg: 18 Sheet #: L

Description:

Port Accidleit Sanmnlinc' S;'.¶tenl Valve Dwg Safety Viv Act Norm Safety Valve Description Coor Class Cat. Si7e Type Type Pos AlP Position Test Freq RR DJT Remarks SV8772A 841B7 2 A I CL SO C/FC P C AT-I AJ FST Q I PIT 2Y PASS LIQ SAMPLE RETURN TO TORUS INBD ISOLATION SV87721i 85117 N A I CL SO C/FC P C AT-I AJ FST Q I PIT 2Y PASS lIlQ SAMPLE RETURN TO TORUS OUTRlI) ISOLATION IST Plan - Fourth 10 Year Interval - Revision 0 Section 9 Page 83 of 87

DAEC Station 4 T1I Interval Inservice Testing Program LEGEND FOR VALVE TABLES Valve No. Valve name indicated on the respective flow diagram.

Dwg Coor Flow Diagram drawing coordinates for the valve. See Section 5.4 for further information on how to interpret the 4 alphanumeric characters.

Safety Class ISI Classification of the valve. The classification will be 1, 2, 3, Y, or N. Y orN designates non-class components, where Y is augmented ISI.

Cat. Valve category per ISTC-1300 Size Valve's nominal size in inches.

A/lP Indicates whether valve is Active (A) or Passive (P).

V'lv Type Valve Types as follows:

ANG Angle AV Auto-Vent BAL Ball BTF Butterfly CK Check GA Gate GL Globe PLG Plug RPD Rupture RV Relief SCK Stop Check SH Explosive Diaphragm shear SV Safety XFC Excess Flow 2NNY Two-way 3NYrY Three-way Check 4NWrY Four-way Act Type Valve actuator type as follows:

AO Air operated a AP Air pilot operated EXP Explosively actuated HO Hydraulic Al Manual MISA Self and Manual Actuated MO Electric motor operated SA Self actuated SAP Self actuated, Pilot Operated SO Solenoid operated Norm Pos Normal position of the valve during plant operation at power. Abbreviations are as follows:

C Closed FC Closed, fails closed FO Fails open KL Key locked, main panel LC Locked closed LO Locked open or at the valve.

NE Normally Energized ND Normally De-energized 0 Open SYS Position dependent Revision 0 (Section 9 Page 84 of 87)

DAEC Station 4 Tmi Interval Inservice Testing Program Exam Type Identifies the test requirements for a valve as follows:

AT-1 Appendix J Test AT-2 Excess Flow Check Valve Test AT4 Torus/Drywell Vacuum Breaker Leaktest AT-5 Pressure Isolation Valve Leak Test AT-6 Accumulator Check Valve Leak Test AT-7 Purge/Vent Pressure Decay Test BTD Full-stroke exercise test to DE-ENERGIZED BTE Full-stroke exercise test to ENERGIZED BTO Full-stroke exercise time test to OPEN Position BTC Full-stroke exercise time test to CLOSE Position BT-VOP Vacuum breaker operational test (Part 1, 1.3.4.3)

CTCNIE Check valve mechanical exercise-CLOSED CTONIE Check valve mechanical exercise-OPEN CT-CC Check valve exercise test to the CLOSED Position CT-CO Check valve exercise test to the OPEN Position CT-RDI Rupture diaphragm inspection CT-RDR Rupture diaphragm replacement CT-SP Safety/Relief Valve Setpoint Verification Test CT-VSP Check Valve/Vacuum Breaker Setpoint Test DSBY Check valve disassembly/inspection DT-E Explosive Valve Test DT-REC Record verification for explosive valves FST Fail-safe Test NA Components is skid mounted and no IST testing requirements are applicable.

PIT Remote Position Indication Verification Test Freq The required test interval as defined below:

AJ Test frequencty is determined by the Appendix J program, as allowed by ISTC-3620.

CS Cold shutdown, as clarified by NUREG 1482 section 2.4.5. Note: Cold shutdown is a frequency, not a plant condition.

Q Quarterly - every 92 days (during plant operation).

R Each reactor refueling outage (cycle). For valves for which disassemblies are governed by relief requests, only one in each group may be affected each outage. To determine the actual frequency, review valve relief requests, if one is referenced.

R* Check valve exercise open test or exercise close test that is not refueling outage dependent and may be performed more frequently than once a refueling interval.

RI Valve will be grouped with other valves in-accordance with ISTC-5221 (c) , with at least one valve dissassembled each refueling outage in-accordance with ISTC-5221 (c) .

R2 50% of Main Steam and Safety Valves are tested during successive refueling outages.

2Y Every 2 years

.2/2Y Explosive valves require at least 20 % replacement every two years per ISTC-5260.

5Y 5 Year replacement of non-reclosing pressure relief devices per Appendix I of ASME OM Code 2001 Edition through 2003 addendum.

6M Semi-annually (every 6 months).

10Y Safety/relief valves are tested on a sampling basis in accordance with Appendix I of ASME OM Code 2001 Edition through 2003 addendum.

10Y1 Excess Flow Check Valve Test scheduled per Relief Request VR-01.

10Y2 Thermal relief valves are tested once every 10 years in accordance with ASME OM Code 2001 Appendix 1.

Relief Req No Refers to the specific relief request associated with the indicated test requirement.

Defer Test Refers to the specific justification for deferred testing (cold shutdown or refueling)

Revision 0 (Section 9 Page 85 of 87)

DAEC Station 4T1rInterval Inservice Testing Program associated with the indicated test requirement.

Notes Important items not covered under other documentation as to valve construction and testing.

TABLE NOTES Notes preceded with an "S" indicate that the component is considered skid mounted.

1. Normal stroke to safety position satisfies fail safe testing requirement.

2. Component is considered skid mounted. Pumps and valves integral to or that support operation of major components, even though these pumps and valves may not be located directly on the skid.

3. Valve is not within the ISI-code boundaries. Testing of this valve will be performed in accordance with the Code to the extent practical. Relief requests will not be submitted for this valve if the Code requirements cannot be met. Also cold shutdown or refueling justifications will not be provided for this valve, in this document.

4. Check valve exercise open test or exercise close test that is not refueling outage dependent and may be performed more frequently than once a refueling interval.

5. There are 89 individual CRD hydraulic control units (HCU's) with each unit provided with one of these valves. The valve number listed is typical of all 89 like valves. All 89 valves will be tested as specified for the typical valve.

6. Due to a restrictive plant configuration, the type C leaktest procedures for these valves yield test results related to the combined leakage of several valves tested as a group and not a valve-specific seat leakage. The leakrate acceptance criteria assigned to these valves is the limit for the entire group of valves being tested.

7. Reserved

8. The "full" stroke of this 1/4-turn Butterfly valve is restricted by physical modifications to a range from fully closed to 30 degrees open.

9. These valves are exercised (tested) during normal control rod exercising routines.

10. Reserved

11. This solenoid valve operates under accident or emergency conditions. During exercise of this valve the stroke time of the associated main valve is measured and evaluated.

12. Valve has no remote position indication.

13. There are 89 individual CRD hydraulic control units (HCU's) with each unit provided with one of these solenoids. The two scram pilot solenoids are contained in the same valve for each HCU.

The solenoid number listed is typical of all 89 like solenoids. All 89 solenoids will be tested as specified for the typical solenoid.

14. Category 'B' Safety Relief valves are exempt from stroke timing and position indication testing.per ISTC-1200.

15. Rupture disc does not see pressure during operation,and therefore does not experience wear. Valve is outside of Code boundary. Disc will be replaced per vendor recommendation every 10 years.

16. Relief valve is classified as a thermal relief according to design documentation.

S1 These valves are supplied with the HCU. The safety function of these check valves to close is verified by depressurizing the supply water charging header and verifying that the scram accumulator Revision 0 (Section 9 Page 86 of 87)

DAEC Station 4 THI Interval Inservice Testing Program maintains pressure. Scram accumulator pressure is also verified once every seven days per Tech Spec. surveillance requirement SR 3.1.5.1.

S2 These valves are supplied with the HCU. Per NUREG 1472, industry experience has shown that normal control rod motion may verify the cooling water header check valve moving to its safety function position, which can be demonstrated because the control rod motion may not occur if the valve were to fail in the open position. Motion of each fully withdrawn control rod is verified every seven days by TS SR 3.1.3.2 and each partially withdrawn control rod every 31 days by TS SR 3.1.3.3.

S3 These valves are supplied with the HCU. The safety function to open of these valves is verified during TS required scram insertion time testing per SRs 3.1 A.1 and 3.1 A.2. Failure of these check valves to open will result in failure to meet the required insertion time for associated control rod.

S4 These valves are supplied with the HCU and are considered to be skid mounted. CVI 849(##-##)

opens to provide a flow path for CRD drive water to the CRD housing. CV1850(##-##) opens to provide a flow path from the CRD housing to the scram discharge volume. The safety function of these valves is adequately tested during TS required scram time testing. Failure of either of the these valves for a given control rod will result in a failure to meet the required scram insertion time.

S5 These valves are integral to the operation of the EDG air start system and are adequately tested during testing EDG.

Revision 0 (Section 9 Page 87 of 87)

DAEC Station 4n' Interval Inservice Testing Program 10.0 VALVE RELIEF REQUESTS Revision 0 (Section 10 Page 1 of 4)

DAEC Station 4Tn1 Interval Inservice Testing Program Valve Relief Request - VR-O1 Proposed Alternative Test for Excess Flow Check Valves In Accordance with 10 CFR 50.55a(a)(3)(i)

Systems: Feedwater Control (45.02)

Residual Heat Removal (49.00)

Core Spray (51.00)

Nuclear Steam Supply Shutoff (58.02)

Reactor Vessel Recirculation (64.01)

Neutron Monitoring (78.01)

Reactor Non-Nuclear Instrumentation (80.00)

Valves:

XFV2119 XFV4457B XFV4513 XFV4590 XFV4668 XFV2139 XFV4458A XFV4514 XFV4591 XFV4669 XFV2246A XFV4458B XFV4515 XFV4607 XFV4670 XFV2246B XFV4459A XFV4516 XFV4608 XFV4671 XFV2246C XFV4459B XFV4518 XFV4611 XFV4672 XFV2246D XFV4460A XFV4519 XFV4612 XFV4673 XFV2443A XFV4460B XFV4528 XFV4637 XFV4674 XFV2443B XFV4501 A XFV4562 XFV4638 XFV4675 XFV2443C XFV4501 B XFV4578 XFV4641 A XFV4676 XFV2443 D XFV4503 XFV4579 XFV464I B XFV4677 XFV4453A XFV4504 XFV4580 XFV4642A XFV4678 XFV4453B XFV4505 XFV4581 XFV4642B XFV4679 XFV4454A XFV4506 XFV4582 XFV4643A XFV4680 XFV4454B XFV4507 XFV4583 XFV4643B XFV4681 XFV4455A XFV4508 XFV4584 XFV4644A XFV4682 XFV4455B XFV45 IOA XFV4585 XFV4644B XFV4666 XFV4456A XFV451 OB XFV4586 XFV4663 XFV4667 XFV4456B XFV4511 XFV4587 XFV4664 XFV4589 XFV4457A XFV4512 XFV4588 XFV4665 Categoa: C Class: I Function:

Excess flow check valves (EFCVS) specifically designed, by Marotta Scientific Controls Inc., for the DAEC are provided in each instrument process line that penetrates the drywell and is part of the reactor coolant pressure boundary. The excess flow check valve is designed so that it will not close accidentally during normal operation, will close if a Revision O (Section 10 Page 2 of 4)

DAEC Station 4ri' Interval Inservice Testing Program rupture of the instrument line is indicated downstream of the valve, can be reopened wvhen appropriate, and has its status indicated in the control room.

An orifice is installed just inside the drywell on each of these instrument lines. The orifice limits leakage to a level where the integrity and functional performance of secondary containment and associated safety systems are maintained, the coolant loss is within the capability of the reactor coolant makeup system, and the potential offsite exposure is substantially below the guidelines of 10 CFR 100. Regulatory Guide 1.11 requested that an additional isolation valve capable of automatic operation be located outside containment on these instrument process lines. At the DAEC, these are the excess flow check valves.

Test Requiremcnt:

2001 Edition and the 2002 and 2003 Addenda of the ASME OM Code.

ISTC-35 10 Exercising Test Frequency. Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC-3560, ISTC-5221 and ISTC-5222. Power-operated relief valves shall be exercise tested once per fuel cycle.

Basis for Relief:

The excess flow check valve is a simple device: the major components are a poppet and spring.

The spring holds the poppet open under static conditions. The valve will close upon sufficient differential pressure across the poppet. Functional testing of the valve is accomplished by venting the instrument side of the tube. The resultant increase in flow imposes a differential pressure across the poppet, which compresses the spring and decreases flow through the valve.

Excess flow check valves have been extremely reliable throughout the industry. In the first 30 years of operation at the DAEC, no excess flow check valve has failed to close due to actual valve failure (i.e., not related to test methodology). The DAEC Technical Specifications (TS) detail what frequency is required to maintain a high degree of reliability and availability, and provide an acceptable level of quality and safety. In the NRC's Safety Evaluation, which approved the associated TS amendment, the Staff concluded, "Based on the acceptability of the methods applied to estimate the release frequency, a relatively low release frequency estimate in conjunction with unlikely impact on core damage and negligible consequence of a release in the reactor building, we conclude that the increase in risk associated with the licensee's request for relaxation of EFCV surveillance testing to be sufficiently low and acceptable." DAEC requested this relief pursuant to IOCFR50.55a(aX3)(i) to exercise excess flow check valves at the frequency specified in amended DAEC TS Surveillance Requirement (SR) 3.6.1.3.7.

Proposed Alternative Test:

Excess flow check valves will be exercised at the frequency specified in the amended DAEC TS Surveillance Requirement (SR) 3.6.1.3.7. The surveillance requirement is to test a representative Revision 0 (Section 10 Page 3 of 4)

DAEC Station 4el Interval Inservice Testing Program sample of Excess Flow Check Valves so that each Excess Flow Check Valve is tested at least once every 10 years.

The Excess Flow Check Valves have position indication in the control room. Check valve remote position indication is excluded from Regulatory Guide 1.97 as a required parameter for evaluating containment isolation. The remote position indication will be verified in the closed direction at the same frequency as the exercise test, which will be performed at the frequency prescribed in the amended DAEC TS Surveillance Requirement (SR) 3.6.1.3.7. Afier the close position test, the valves will be reset, and the remote open position indication will be verified. Although inadvertent actuation of an EFCV during operation is highly unlikely due to the spring-poppet design, the DAEC will verify the EFCVs indicate open in the control room at a frequency greater than once every 2 years.

Reference:

DAEC Technical Specification Amendment 230 approved by the NRC on December 29, 1999

Safety Evaluation by the Office of Nuclear Reactor Regulation of the third I 0-year interval inservice inspection plan request for relief regarding excess flow check valve surveillance requirements, Duane Arnold Energy Center, Docket No. 50-331, dated March 28,2000.

Revision 0 (Section 10 Page 4 of 4)

DAEC Station 4Tn1 Interval Inservice Testing Program 11.0 DEFERRED TEST JUSTIFICATIONS - VALVES Revision 0 (Section 11 Page 1 of 34)

DAEC Station 4n' Interval Inservice Testing Program Deferred Test Justification DTJ-O1 SYSTEM: MAIN STEAM TURBINE STOP AND CONTROL VALVES VALVES: CV1064 Main Steam Drain Isolation to Condenser M01043 Main Steam Drain Isolation M01044 Drywell Steam Line Drains Condenser Isolation FUNCTION: These normally closed valves open to provide a flow path for Main Steam Isolation Valve (MSIV) leakage to the main condenser following an accident.

TEST REQUIREMENTS: ISTC-3521(c) if exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns.

BASIS: These valves open to direct MSIV leakage to the main steam drain lines and to the main condenser to reduce offsite dose to the public, after the MSIVs have isolated. The system was installed in 1994 to replace the MSIV leakage control system, and to permit greater leakage through the MSIVs.

These valves are remote manually opened following isolation of the MSIVs as part of MSIV leakage treatment system. Since the function of these valves is to operate after the MSIVs close, the valves do not cycle with main steam line pressure in the line during accident conditions. These valves were not designed to be routinely operated during full power operation with full main steam line pressure. Quarterly full or partial cycling would result in increased wear, resulting in increased packing leakage, etc. while subject to pressures far greater than the valves will experience during accident conditions for the MSIV leakage treatment system.

Alternate Testing: Exercise valves during cold shutdown.

Revision 0 (Section 11 Page 2 of 34)

DAEC Station 4"H Interval Inservice Testing Program Deferred Test Justification DTJ-02 SYSTEM: MAIN STEAM TURBINE STOP AND CONTROL VALVES VALVES: M01169 Turbine Steam Seal Main Steam Supply Isolation M01170 Turbine Steam Seal Press Regulator Bypass FUNCTION: The normally open valve MOI 169 and the normally closed valve MOI 170 close to divert Main Steam Isolation Valve (MSIV) leakage to the main condenser following an accident.

TEST REQUIREMENTS: ISTC-3521(c) if exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns.

BASIS: These valves close to direct MSIV leakage to the main steam drain lines and to the main condenser to reduce offsite dose to the public, after the MSIVs have isolated. The system was installed in 1994 to replace the MSIV leakage control system, and to permit greater leakage through the MSIVs.

The turbine steam seal system provides steam to the turbine glands to control air leakage into the turbine. The system is essential for turbine operation, and was not designed for full or partial valve cycling while the turbine is online. Operating Instruction 01 692 Precaution and limitation #3 states: "If MOl 170 regulator bypass is opened further than necessary, it is possible to lift PSVI 173 A/B/C due to high pressure/flow even though seal pressure at PI1 167A at IC07 indicates <6 Psig (lift setpoint) (a). Adjustments to steam seal pressure should normally be made using PCI 175. (b). MOI 170 regulator bypass and MOI 171 manual unloader should not be used to adjust seal pressure, except in the case of a regulator failure." It would be very difficult to transition to the bypass without lifting the reliefs or getting a low steam seal pressure alarm. The turbine steam seal system provides steam to the turbine glands to control air leakage into the turbine. The system is essential for turbine operation, and was not designed for full or partial valve cycling while the turbine is online. Full or partial valve cycling should not be performed during plant operation to avoid unnecessary pressure transients on the steam seal system.

These valves are remote manually opened following isolation of the MSIVs as part of MSIV leakage treatment system. Since the function of these valves is to operate after the MSIVs close, the valves do not cycle with main steam line pressure in the line during accident conditions. These valves were not designed to be routinely operated during full power operation with full main steam line pressure. Quarterly full or partial cycling would result in increased wear, such as increased packing leakage, etc.

while subject to pressures far greater than the valves will Revision 0 (Section 11 Page 3 of 34)

DAEC Station 4n' Interval Inservice Testing Program experience during accident conditions for the MSIV leakage treatment system Alternate Testing: Exercise valves during cold shutdown.

Revision 0 (Section 11 Page 4 of 34)

DAEC Station 4n"Interval Inservice Testing Program Deferred Test Justification DTJ-03 SYSTEM: MAIN STEAM TURBINE STOP AND CONTROL VALVES VALVES: MO1054 MSR 1E-18B 2nd Stage Reheat Steam Supply M01055 MSR 1E-18A 2nd Stage Reheat Steam Supply FUNCTION: These normally open valves close to divert Main Steam Isolation Valve (MSIV) leakage to the main condenser following an accident.

TEST REQUIREMENTS: ISTC-3521(c) if exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns.

BASIS: These valves open to direct MSIV leakage to the main steam drain lines and to the main condenser to reduce offsite dose to the public, after the MSIVs have isolated. The system was installed in 1994 to replace the MSIV leakage control system, and to permit greater leakage through the MSIVs.

The safety function of these valves is to be remote manually closed following isolation of the MSIVs. These valves are normally open to allow 2nd Stage Reheat Steam to be supplied to feedwater heaters. These valves do not have a mechanism to equalize pressure across the valve after they are isolated, and should not be fully or partially stroked with main steam pressure in the line to avoid requiring the plant to enter cold shutdown in-order to re-open the valves.

Alternate Testing: Exercise valves during cold shutdown.

Revision 0 (Section 11 Page 5 of 34)

DAEC Station 4T'n Interval Inservice Testing Program

. Deferred Test Justification DTJ-04 SYSTEM: MAIN STEAM TURBINE STOP AND CONTROL VALVES VALVES: M01362A MSL"A" Supply to Offgas and SJAE M01362B MSL"B" Supply to Offgas and SJAE FUNCTION: These normally open valves close to divert Main Steam Isolation Valve (MSIV) leakage to the main condenser following an accident.

TEST REQUIREMENTS: ISTC-3521(c) if exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns.

BASIS: These valves close to direct MSIV leakage to the main steam drain lines and to the main condenser to reduce offsite dose to the public, after the MSIVs have isolated. The system was installed in 1994 to replace the MSIV leakage control system, and to permit greater leakage through the MSIVs.

These motor-operated valves provide steam to the Steam Jet Air Ejectors. These valves are remote manually closed following isolation of the MSIVs as part of the MSIV leakage treatment system. Since the function of these valves is to operate after the MSIVs close, the valves do not cycle with main steam line pressure in the line during accident conditions. These valves were not designed to be routinely operated during full power operation with full main steam line pressure. Quarterly cycling would result in increased wear, such as increased packing leakage, etc. at pressures far greater than the valves will experience during the accident conditions for the MSIV leakage treatment system.

Alternate Testing: Exercise valves during cold shutdown.

Revision 0 (Section 11 Page 6 of 34)

DAEC Station 4 n' Interval Inservice Testing Program Deferred Test Justification DTJ-05 SYSTEM: MAIN STEAM VALVES: CV4412 "A" Main Steam Line Inboard Isolation CV4413 "A" Main Steam Line Outboard Isolation CV4415 "B" Main Steam Line Inboard Isolation CV4417 "B" Main Steam Line Outboard Isolation CV4418 "C" Main Steam Line Inboard Isolation CV4419 "C" Main Steam Line Outboard Isolation CV4420 "D" Main Steam Line Inboard Isolation CV4421 "D" Main Steam Line Outboard Isolation FUNCTION: These normally open valves close for reactor vessel and containment isolation.

TEST REQUIREMENTS: ISTC-352 1(c) if exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns.

BASIS: These valves have two fail-safe modes. One is loss of electric power. This mode is tested on-line (quarterly) by normal closure of each valve where the closure signal de-energizes the solenoid valves which control the actuator pilot valves.

The second mode is loss of nitrogen gas pressure to the actuator.

In this case the nitrogen pressure on the underside of the actuator piston, which keeps the valve open, is exhausted to atmosphere upon the failure of the supply system. The closure time is 3 to 5 seconds, after the nitrogen pressure has decayed to the point at which the air-valves reposition (internal spring force overcomes the pneumatic force). Exercising the MSIV's by closing utilizing spring force only complies with the recommendations of General Electric Service Information Letter 477. During refueling shutdowns, the MSIV's are also cycled utilizing the accumulators only (non-safety grade nitrogen makeup is isolated) in accordance with NRC Information Notice 85-84, Inadequate Inservice Testing of Main Steam Isolation Valves. Both of these tests require access to the drywell and a considerable expenditure of plant staff resources. Thus, the scope of these tests precludes testing during cold shutdown periods.

Alternate Testing: Exercise fail-safe capability of the valves during Refueling Outages.

Revision 0 (Section 11 Page 7 of 34)

DAEC Station 4n' Interval Inservice Testing Program Deferred Test Justification DTJ-06 SYSTEM: DRYWELL COOLING VALVES: CV5704A DRYWELL COOLING LOOP A RETURN ISOL CV5704B DRYWELL COOLING LOOP B RETURN ISO CV5718A DRYWELL COOLING LOOP A SUPPLY ISO CV5718B DRYWELL COOLING LOOP B SUPPLY ISO FUNCTION: These normally open valves close to provide containment isolation.

TEST REQUIREMENTS: ISTC-3521(c) if exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns.

BASIS: These valves isolate drywell cooling when closed. Partially or fully cycling the drywell cooling isolation valves quarterly may cause pressure spikes in the system that could potentially cause drywell coolers to leak, damaging the drywell coolers.

Significant drywell cooler leakage can cause the plant to shutdown to repair this unidentified leakage source in the drywell. Potential equipment damage is adequate reason for cold shutdown testing according to NUREG 1482 Rev.l.

Alternate Testing: Exercise valves during cold shutdown.

Revision 0 (Section 11 Page 8 of 34)

DAEC Station 4 n' Interval Inservice Testing Program Deferred Test Justification DTJ-07 SYSTEM: REACTOR BUILDING CLOSED COOLING WATER VALVES: M04841A Drywell RBCCW Return Header Isolation M04841B Drywell RBCCW Supply Header Isolation FUNCTION: These normally open valves close to provide primary containment isolation.

TEST REQUIREMENTS: ISTC-3521(c) if exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns.

BASIS: During plant operation, these valves are open to supply and return cooling water to and from reactor recirculation pump components inside the drywell. These include the pump motor windings, seal water coolers and lube oil coolers. Closing or partially closing either of these valves interrupts cooling water flow and could result in damage to pump and motor components.

Alternate Testing: Exercise valves during cold shutdown.

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DAEC Station 4Tn Interval Inservice Testing Program Deferred Test Justification DTJ-08 SYSTEM: Control Rod Drive VALVES: V17-0083 Reactor Recirculation Mini Purge Check Valve V17-0096 Reactor Recirculation Mini Purge Check Valve FUNCTION: These check valves close to provide primary containment isolation.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refueling outages.

BASIS: These are simple check valves with no positive means of determining valve disk position, thus the only means of determining closure of these valves is by performing leak tests.

Such testing requires drywvell entry plus extensive system preparations. Performance of these leak tests is impossible during plant operation due to the inaccessibility of the drywell and impractical at cold shutdown due to the testing requires de-inerting the drywell.

Alternate Testing: Exercise valves during refueling outages.

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DAEC Station 4u'TInterval Inservice Testing Program Deferred Test Justification DTJ-09 SYSTEM: DRYWELL COOLING VALVES: M04627 RX Recirc Pump IP-201A Discharge Isolation M04628 RX Recirc Pump IP-201B Discharge Isolation FUNCTION: These normally open valves close to divert MSIV leakage to the main condenser following an accident.

TEST REQUIREMENTS: ISTC-3521(c) if exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns.

BASIS: Closing either of these valves during plant operation places the recirculation system in a "single loop" configuration. Although single-loop operation is possible, routinely entering into this configuration is undesirable and contrary to the prudent and safe operation of the reactor plant. In addition, operation in a single loop configuration requires a severe power reduction.

Alternate Testing: Exercise valves during cold shutdown.

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DAEC Station 4T'I Interval Inservice Testing Program Deferred Test Justification DTJ-10 SYSTEM: CONTAINMENT ATMOSPHERE CONTROL VALVES: CV4357 - Containment Hard Vent Valve FUNCTION: The containment hard vent system was installed as requested in Generic Letter 89-16 to provide a means of venting primary containment irrespective of the release of radioactivity to the environment. This system will be utilized only when plant conditions have degraded beyond design conditions considered in the DAEC Final Safety Analysis Report.

TEST REQUIREMENTS: ISTC-3521(d) if exercising is not practicable during operation at power or cold shutdown, it may be limited to full stroke during refueling outages.

BASIS: Because the hard vent system is not intended to be used to mitigate events considered in the Final Safety Analysis Report, components other than those provided for primary containment isolation are not within the scope of the Inservice Test (IST)

Program, as discussed in ISTA-I 100. These components have been added to the 1ST Program for testing on an augmented basis. The intent of including these components in the Program is to provide a reasonable level of operational readiness for the hard vent system and testing at a refueling frequency satisfies this.

Alternate Testing: Exercise valve during refueling outages.

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DAEC Station 4 TH1 Interval Inservice Testing Program Deferred Test Justification DTJ-11 SYSTEM: CONTAINMENT ATMOSPHERE CONTROL COMPONENT: V43-0214 - Drywell Instrument Nitrogen Header Supply Stop check valve FUNCTION: This check valve closes for containment isolation.

TEST REQUIREMENTS: ISTC-3522(C) if exercising is not practicable during operation at power or cold shutdown, it shall be performed during refueling outages.

BASIS: This is a simple check valve with no positive means of determining valve disk position, thus the only practical means of determining closure is by performing a leak test.

Performing a leak test of this valve requires containment access, isolation of nitrogen to the containment, and an extensive valve re-alignment. The resources and time required to complete such a test places an undue burden on the plant staff and is not justified by the little gain in plant safety afforded by the test.

Alternate Testing: Exercise valve during refueling outages.

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DAEC Station 4'1" Interval Inservice Testing Program Deferred Test Justification DTJ-12 SYSTEM: NEUTRON MONITORING COMPONENT: V43-0503 - Tip System Purge Check Valve FUNCTION: This valve provides containment isolation for the TIP system nitrogen purge line.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power or cold shutdown, it may be limited to full stroke during refueling outages.

BASIS: This is a simple check valve with no disk position indication and the only practical method of verifying closure is by performing a leak test. The method of leak testing for this valve requires separation of the containment penetration flange which constitutes a breach of primary containment integrity and thus not practical during plant operation. Furthermore, the testing requires approximately 20 man-hours to complete. Taking into account the typical general area radiation dose rate of 200 mR/hour in the vicinity of this valve at cold shutdown, the estimated total exposure per test is approximately 4 man-Rem.

Based on the foregoing discussion, the costs and burden on the plant staff associated with cold shutdown testing of this valve is not justified by the little potential gain in plant safety afforded by the test. The use of a seat leakage test to confirm obturator closure when no other means are practical is endorsed in NUREG-1482 rev. 1, Part 4.1.6.

Alternate Testing: Exercise valve during refueling outages.

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DAEC Station 4el Interval Inservice Testing Program Deferred Test Justification DTJ-13 SYSTEM: NUCLEAR BOILER COMPONENT: V14-0032 - Check Valve For N2 Supply To Accum 1RO02A V14-0100 - Check Valve For N2 Supply To Accum 1RO01B V14-0104 - Check Valve For N2 Supply To Accum iROOlA V14-0108 - Check Valve For N2 Supply To Accum 1RO02B V14-0112 - Check Valve For N2 Supply To Accum IRO1C V14-0116 - Check Valve For N2 Supply To Accum IR002C V14-0120 - Check Valve For N2 Supply To Accum IRO0D V14-0124 - Check Valve For N2 Supply To Accum IR002D FUNCTION: These valves provide isolation for the safety related MSIV nitrogen accumulators. These check valves close to maintain pressure in the accumulator on a loss of nitrogen supply.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refueling outages.

BASIS: These are simple check valves with no disk position indication and the only practical method of verifying closure is by performing a leak test. The method of leak testing for these valves requires entering the drywell and thus not practical during plant operation. This would require de-inerting the drywell.

Based on the foregoing discussion, the cost and burden on the plant staff associated with cold shutdown testing of these valves is not justified by the little potential gain in plant safety afforded by the test.

Alternate Testing: Exercise valves during refueling outages.

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DAEC Station 4 T11 Interval Inservice Testing Program Deferred Test Justification DTJ-14 SYSTEM: Main Steam COMPONENT: V14-0009 - Check Valve For N2 Supply To PSV4406 and PSV4407 V14-0014 - Check Valve For N2 Supply To PSV4402 V14-0015 - Check Valve For N2 Supply To PSV4400 and PSV4401 V14-0016 - Check Valve For N2 Supply To PSV4405 FUNCTION: These valves provide isolation for the safety related Main Steam Relief Valve actuator nitrogen supply. These check valves close to maintain pressure in the accumulator on a loss of nitrogen supply.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refueling outages.

BASIS: These are simple check valve with no disk position indication.

The only practical method of verifying closure is by performing a leak test. The method of leak testing for these valves requires entering the drywell and thus not practical during plant operation. This would require de-inerting the drywell. Based on the foregoing discussion, the cost and burden on the plant staff associated with cola shutdown testing of these valves is not justified by the little potential gain in plant safety afforded by the test.

Alternate Testing: Exercise valves during refueling outages.

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DAEC Station 4 T11 Interval Inservice Testing Program Deferred Test Justification DTJ-15 SYSTEM: Main Steam COMPONENT: V22-0016 - Valve Check HPCI 1S201 Exhaust Line V22-0017 - HPCI Turbine Steam Exhaust Line Isolation FUNCTION: These check valves open to provide a flow path for exhaust steam from the HPCI turbine to the Torus. They close for containment isolation.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power or cold shutdown, it shall be performed during refueling outages.

BASIS: During plant operation these valves must be capable of opening to allow turbine exhaust steam to exit into the suppression chamber. Testing of these valves to the closed position requires downstream valves to be closed when air is used to verify valve closure. While the tests are in progress, the respective pump is inoperable since there is no path for turbine exhaust steam.

There are no local or remote indicators of obturator position, nor are system parameters indicative of closure. The closure test method is analogous to a leak test (without quantifying leakage).

The NRC has determined, in NUREG 1482 rev. I section 4.1.6, that the need to set up test equipment is adequate justification to defer reverse flow testing of a check valve until a refueling outage.

Alternate Testing: Exercise valves during refueling outages.

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DAEC Station 4n' Interval Inservice Testing Program Deferred Test Justification DTJ-16 SYSTEM: CONTROL ROD DRIVE COMPONENTS: CV1859B - CRD Scram Discharge Header Vent Valves CV1867B - CRD Scram Discharge Header Drain Valves V1859A and CV1867B*

FUNCTION: In the event of a scram these valves close when solenoids SV1868A, SV1868B, SV1869A, and SV1869B de-energize.

Closure isolates the scram discharge headers and reactor coolant from the reactor building.

TEST REQUIREMENT: ISTC-3521 (d) if exercising is not practicable during operation at power or cold shutdown, it may be limited to full stroke during refueling outages.

BASIS: Actuating the CRD scram discharge header vent and drain valves utilizing SV1868A, SV1868B, SV1869A, and SV1869B requires initiation of a full SCRAM signal. These solenoids are tied to the RPS system and de-energize to vent air from the valve actuator.

The vent and drain valves are equipped with test solenoids that allow for quarterly exercising; the vent and drain valves are verified to close on a loss of air. The appropriate method of fail-safe testing these valves is to use the safety-related logic and solenoids. This is not practical quarterly: such testing could result in a plant trip.

Alternate Testing: Exercise valves using the fail-safe solenoids during cold shutdowns.

These valves are not Class 1, 2 or 3 and are listed in this justification for completeness reasons only.

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DAEC Station 4n' Interval Inservice Testing Program Deferred Test Justification DTJ-17 SYSTEM: CONTROL ROD DRIVE COMPONENTS: V17-0052 - CRD Return To Reactor Vessel Check Valves V1 7-0053 - CRD Return To Reactor Vessel Check Valves FUNCTION: These valves close for containment isolation.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power or cold shutdown, it shall be performed during refueling outages.

BASIS: These are simple check valves with no positive indication of disk position thus the only means of determining closure of these valves is by performing leak tests. Such testing requires drywell entry plus extensive system preparations. Performance of these leak tests is impossible during plant operation and impractical at cold shutdown due to the unreasonable burden on the plant staff.

The NRC has determined, in NUREG 1482 rev. I section 4.1.6, that the need to set up test equipment is adequate justification to defer reverse flow testing of a check valve until a refueling outage. Note that this line is normally isolated and valve degradation during operation is unlikely.

Alternate Testing: Exercise valves during refueling outages.

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DAEC Station 4 n' Interval Inservice Testing Program Deferred Test Justification DTJ-18 SYSTEM: HIGH PRESSURE COOLANT INJECTION (HPCI)

COMPONENTS: V22-0021 - HPCI Condensate Drain Valve V22-0022 - HPCI Condensate Drain Valve FUNCTION: During HPCI operation these valves open to provide a flowpath for discharging condensate from the HPCI turbine exhaust drain pot to the torus. They close for containment isolation.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refuel outages.

ISTC-5221(c) If the test methods in ISTC-5221(a) and ISTC-5221 (b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement.

ISTC-5221(c)(3) At least one valve from each group shall be disassembled and examined at each refuel outage; all valves in each group shall be disassembled and examined at least once every 8 years.

BASIS: V22-0021 and V22-0022 are in series and the only practical method of verifying full stroke (open) is by measuring full accident flow through the line. However, there is no installed flow measurement instrumentation.

Alternate Testing: These valves will be grouped and examined in-accordance with ISTC-5221(c). At least one valve wvil be disassembled and examined each refueling outage.

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DAEC Station 4u' Interval Inservice Testing Program Deferred Test Justification DTJ-19 SYSTEM: Emergency Service Water (ESW)

COMPONENTS: V13-0121 - 1K003/4 Cooling Water Inlet Check Valve V13-0126 - 1K003/4 Cooling Water Inlet Check Valve FUNCTION: These check valves open to provide a flow path for emergency service water to the HVAC instrument air compressors IK003 and IK004.

TEST REQUIREMENTS: ISTC-522I(c) If the test methods in ISTC-5221(a) and ISTC-5221 (b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement.

ISTC-5221(c)(3) At least one valve from each group shall be disassembled and examined at each refuel outage; all valves in each group shall be disassembled and examined at least once every 8 years.

BASIS: These are simple check valves with no means of mechanical exercising or positive indication of disc position, the only practical method of verifying full stroke (open) is by measuring full accident flow through the line. There is no installed flow instrumentation on the associated branch lines thus flow measurements are not practical.

Since these valves are identical seeing essentially identical service, they qualify for sample disassembly as set forth in ISTC-5221(c).

Alternate Testing: These valves will be grouped and examined in-accordance with ISTC-5221(c). At least one valve will be disassembled and examined each refueling outage.

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DAEC Station 4 nTInterval Inservice Testing Program Deferred Test Justification DTJ-20 SYSTEM: Core Spray Residual Heat Removal High Pressure Coolant Injection Reactor Core Isolation Cooling COMPONENTS: V21-0009 - 1P-211A Minimum Flow Line Check Valve V21-0012 - 1P-211B Minimum Flow Line Check Valve V19-0014 - 1P229D Minimum Flow Line Check Valve V19-0016 - 1P229B Minimum Flow Line Check Valve V20-0006 - 1P229A Minimum Flow Line Check Valve V20-0008 - 1P229C Minimum Flow Line Check Valve V23-0014 - 1P216 Minimum Flow Line Check Valve V25-0006 - 1P226 Minimum Flow Line Check Valve FUNCTION: These swing check valves open during pump operation to provide recirculation flowpaths to the torus in order to prevent pump damage due to heatup as a result of operation under shutoff or minimal flow conditions.

TEST REQUIREMENTS: ISTC-5221(c) If the test methods in ISTC-5221(a) and ISTC-5221 (b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement.

ISTC-5221(c)(3) At least one valve from each group shall be disassembled and examined at each refuel outage; all valves in each group shall be disassembled and examined at least once every 8 years.

BASIS: These are simple check valves with no means of mechanical exercising or positive indication of disc position, thus the only practical method of exercising them is with system flow. Due to the lack of appropriate flow instrumentation in the associated lines, verification of accident flow is not practical.

Alternate Testing: These valves will be grouped and examined in-accordance with ISTC-5221(c). At least one valve in each group will be disassembled and examined each refueling outage.

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DAEC Station 4 nTInterval Inservice Testing Program Deferred Test Justification DTJ-21 SYSTEM: CORE SPRAY COMPONENTS: V21-0072 - Core Spray Injection Check Valve V21-0073 - Core Spray Injection Check Valve FUNCTION: These check valves provide a flow path for low pressure core spray to the reactor vessel and prevent backflow from the reactor vessel to the low pressure core spray system.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power or cold shutdown, it shall be performed during refueling outages.

BASIS: The only means of determining closure of these valves is by performing a leak test. Such a test requires drywell entry plus extensive preparations. Performance of these leaktests is impossible during plant operation and impractical at cold shutdown due to the unreasonable burden on the plant staff. In order to gain personnel access to the drywell, the nitrogen used to inert the drywell must be de-inerted. De-inerting the drywell solely for the purpose of valve testing is excessively burdensome and a sound basis for test deferral to refueling as described in NUREG-1482 rev. l, Section 4.1.6.

Alternate Testing: Exercise valves during refueling outages.

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DAEC Station 4n' Interval Inservice Testing Program Deferred Test Justification DTJ-22 SYSTEM: Standby Liquid Control (SBLC)

COMPONENTS: V26-0004 - SBLC Pump Discharge Check Valve V26-0006 - SBLC Pump Discharge Check Valve FUNCTION: These check valves open during standby liquid control pump operation to provide flowpaths to the SBLC header and thence to the reactor vessel. They close to prevent backleakage through an idle pump or failed safety valve.

TEST REQUIREMENTS: ISTC-5221(c) If the test methods in ISTC-5221(a) and ISTC-5221(b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement.

ISTC-5221(c)(3) At least one valve from each group shall be disassembled and examined at each refuel outage; all valves in each group shall be disassembled and examined at least once every 8 years.

BASIS: These are simple check valves with no means of mechanical exercising or positive indication of disc position, thus the only practical method of verifying closure is by performing a backleakage test. Performance of such a backleakage test is not practical due to the lack of appropriate test connections.

Alternate Testing: These valves will be grouped and examined in-accordance with ISTC-5221(c). At least one valve will be disassembled and examined each refueling outage.

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DAEC Station 4T01 Interval Inservice Testing Program Deferred Test Justification DTJ-23 SYSTEM: STANDBY LIQUID CONTROL (SBLC)

COMPONENTS: V26-0008 - Standby Liquid Control Injection Check Valve V26-0009 - Standby Liquid Control Injection Check Valve FUNCTION: These check valves provide a flowpath for borated water from the standby liquid control injection header to the reactor vessel.

They close for containment isolation.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refuel outages.

BASIS: Full-stroke or partial open exercising of the SBLC injection check valves quarterly during operation or cold-shutdowns is impractical due to the extensive test set-up and system restoration. The performance of a partial open exercise requires drywell entry to isolate the test volume from the reactor by closing normally locked open manual valve V26-0032. This is required to develop conclusive flow rates through the check valves using a highly pure water source to pressurize the piping.

The drywell is inerted during reactor operation and is inaccessible.

The only practical means of exercising these valves to the open position is during a refueling outage by operation of the SBLC pumps and discharging into the reactor vessel. This cannot be done during normal operation or cold shutdown since the SBLC system must be drained and flushed to prevent contamination of the reactor coolant with sodium pentaborate. In addition, extensive testing and maintenance is required to replace the explosive charges in the isolation valves.

Alternate Testing: Exercise valves during refueling outages.

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DAEC Station 4 TH Interval Inservice Testing Program Deferred Test Justification DTJ-24 SYSTEM: REACTOR CORE ISOLATION COOLING (RCIC)

COMPONENTS: V24-0008 - RCIC Turbine Steam Exhaust Check Valve V24-0023 - RCIC Turbine Exhaust Check Valve FUNCTION: These check valves provide a flowpath for exhaust steam from the RCIC turbine to the torus. They close for containment isolation.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refuel outages.

BASIS: During plant operation these valves must be capable of opening to allow turbine exhaust steam to exit into the suppression chamber. Testing of these valves to the closed position requires downstream valves to be closed when air is used to verify valve closure. While the tests are in progress, the respective pump is inoperable since there is no path for turbine exhaust steam.

There are no local or remote indicators of obturator position, nor are system parameters indicative of closure. The closure test method is analogous to a leak test (without quantifying leakage).

The NRC has determined, in NUREG 1482 rev. I section 4.1.6, that the need to set up test equipment is adequate justification to defer reverse flow testing of a check valve until a refueling outage.

Alternate Testing: Exercise valves during refueling outages.

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DAEC Station 4 n' Interval Inservice Testing Program Deferred Test Justification DTJ-25 SYSTEM: Reactor Core Isolation Cooling (RCIC)

High Pressure Coolant Injection (IIPCI)

COMPONENTS: V24-0046 and V24-0047 - RCIC Turbine Exhaust Vacuum Breakers V22-0063 and V22-0064 - HPCI Turbine Exhaust Vacuum Breakers V22-0026 and V22-0029 - ILPCI Condensate Pump Discharge Line Check Valves V22-0028 - HIPCI Turbine Lube Oil Cooler Cooling Water Exhaust line.

FUNCTIONS: Following RCIC or HPCI operation the turbine exhaust vacuum breaker valves open to prevent a vacuum buildup in the exhaust lines and subsequent filling of the turbine exhaust piping from the torus. They close for containment isolation.

V22-0026 Barometric condenser condensate pump discharge check valve, supports operation of HPCI in the open and closed positions.

V22-0028 and V22-0029 open to provide a flow path for HPCI lube oil cooling and/or Gland Seal condensate pump discharge.

With the pumps in standby, these check valves prevent barometric condenser in-leakage.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refuel outages.

ISTC-5221(c) If the test methods in ISTC-5221(a) and ISTC-5221 (b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement.

ISTC-5221(c)(3) At least one valve from each group shall be disassembled and examined at each refuel outage; all valves in each group shall be disassembled and examined at least once every 8 years.

BASIS: These are simple check valves with no means of mechanical exercising or positive indication of disc position; thus the only practical method of exercising them is with system flow. Due to the lack of appropriate flow instrumentation in the associated lines, verification of accident flow is not practical.

Alternate Testing: These valves will be grouped and examined in-accordance with ISTC-5221(c). At least one valve in a group will be disassembled and examined each refueling outage.

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DAEC Station 4n' Interval Inservice Testing Program Deferred Test Justification DTJ-26 SYSTEM: REACTOR CORE ISOLATION (RCIC)

COMPONENTS: V25-0036 - RCIC Pump Discharge Check Valve FUNCTION: This valve opens to provide a flowpath for RCIC to the reactor vessel via the reactor feedwater piping.

a TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refuel outages.

ISTC-522 I(b) If a mechanical exerciser is used to exercise the valve, the force(s) or torque(s) required to move the obturator and fulfill its safety function shall meet the acceptance criteria specified by the Owner.

BASIS: Opening this valve quarterly with RCIC system flow is not practical during plant operation due to the potential for severe reactor vessel water level and temperature transients as well as possible contamination of reactor feedwater. This valve is provided with the capability to be mechanically exercised and opening torque measured; however, the location of the valve in the steam tunnel makes it inaccessible during power operation.

To ensure repeatable data for comparison to reference value torque, the piping is drained to equalize pressure across the obturator. This evolution requires reactor drywell entry to manually isolate V25-0036 from the reactor.

Alternate Testing: Exercise valve during refueling outages.

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DAEC Station 4 T11 Interval Inservice Testing Program Deferred Test Justification DTJ-27 SYSTEM: FEEDWATER COMPONENTS: V14-0001 and V14-0002 - Feedwater Inboard Isolation M04441, and M04442 - Feedwater Outboard Isolation FUNCTION: These valves close for reactor vessel and containment isolation.

V14-0001 and V14-0002 open to allow HPCI or RCIC inject, while M04441 and M04442 prevent diversion of HPCI and RCIC flow to the main feedwater system.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refuel outages for check valves V14-0001, V14-0002, M04441 and M04442.

ISTC-3521(c) if exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns for power-operated function of M04441 and M04442.

BASIS: During plant operation at power, reactor feedwater must be supplied through these valves to maintain reactor coolant inventory and reactor vessel water level. Closing either feedwater loop will isolate two of the four supplies of feedwater into the reactor vessel. This could result in thermal shock to the reactor vessel feedwater nozzles and spargers upon resumption of flow and a plant trip due to the potential for severe reactor vessel water level and power transients For testing M04441 and M04442 stop check valve capability, a leak test is required. V14-0001 and V14-0003 are simple swing check valves with no positive indication of disk position with the only means of determining closure of these valves are by performing leak tests. Such a test requires drywell and steam tunnel entry plus extensive preparations of the feedwater system including draining approximately 2000 gallons of water.

Furthermore, testing of Vl4-000l requires shutdown of the cleanup system that is undesirable during power operation or cold shutdown.

Performance of these leaktests is impossible during plant operation and impractical at cold shutdown due to the unreasonable burden on the plant staff.

Alternate Testing: Exercise check valves during refueling outages, exercise motor operator valves at a cold shutdown frequency.

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DAEC Station 4 nTInterval Inservice Testing Program Deferred Test Justification DTJ-28 SYSTEM: Residual Heat Removal/ Core Spray (RHR/CS)

COMPONENTS: V19-0022 and V19-0024 - RHR/CS KEEP FILL CHECK VALVES V19-0020 and V19-0124 -RILR/CS KEEP FILL CHECK VALVES FUNCTIONS: These valves close to isolate residual heat removal system or core spray from the torus. They open during standby mode to maintain pressure in those systems.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refuel outages.

ISTC-5221(c) If the test methods in ISTC-5221(a) and ISTC-5221 (b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement.

ISTC-5221(c)(3) At least one valve from each group shall be disassembled and examined at each refuel outage; all valves in each group shall be disassembled and examined at least once every 8 years.

BASIS: V 19-022 and V19-024 are simple check valves with no means of mechanical exercising or positive indication of disc position; and there is no practical method of exercising them is with a leak test.

V19-020 and V19-124 are stop check valves that have no remote manual isolation capability. There is no method to verify closure without using the installed manual hand-wheel to verify closure.

Alternate Testing: These valves will be grouped and examined in-accordance with ISTC-5221(c). At least one valve in a group will be disassembled and examined each refueling outage.

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DAEC Station 4n' Interval Inservice Testing Program Deferred Test Justification DTJ-29 SYSTEM: Residual Heat Removal COMPONENTS: V19-0149 - B RiHR INJECT CHECK VALVE V20-0082 - A RHR INJECT CHECK VALVE FUNCTIONS: These check valves close to isolate the reactor vessel from the residual heat removal system. They open to supply low pressure coolant injection to the vessel during an accident..

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power or cold shutdown, it shall be performed during refueling outages.

BASIS: The only means of determining closure of these valves is by performing a leak test. Such a test requires drywell entry plus extensive preparations. Performance of these leaktests is impossible during plant operation and impractical at cold shutdown due to the unreasonable burden on the plant staff. In order to gain personnel access to the drywvell, the nitrogen used to inert the drywell must be de-inerted. De-inerting the drywell solely for the purpose of valve testing is excessively burdensome and a sound basis for test deferral to refueling as described in NUREG-1482 rev. 1, Section 4.1.6.

Alternate Testing: Exercise valves during refueling outages.

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DAEC Station 4 nH Interval Inservice Testing Program Deferred Test Justification DTJ-30 SYSTEM: Residual Heat Removal COMPONENTS: V19-0195 -M01908 BYPASS CHECK VALVE FUNCTIONS: This check valve closes to isolate the reactor vessel from the residual heat removal system. The valve opens to reduce/relieve pressure between MO 1908 and MO 1909 to avoid pressure locking and thermal binding issues.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power or cold shutdown, it shall be performed during refueling outages.

BASIS: The only means of determining closure of this valve is by performing a leak test. Such a test requires dryvell entry plus extensive preparations. Performance of these leaktests is impossible during plant operation and impractical at cold shutdown due to the unreasonable burden on the plant staff. In order to gain personnel access to the drywvell, the nitrogen used to inert the drywell must be removed. De-inerting the drywell solely for the purpose of valve testing is excessively burdensome and a sound basis for test deferral to refueling as described in NUREG-1482 rev. 1, Section 4.1.6.

Alternate Testing: Exercise valve during a refueling outage.

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DAEC Station 4 Tfl Interval Inservice Testing Program Deferred Test Justification DTJ-31 SYSTEM: High Pressure Coolant Injection COMPONENTS: V23-0049 - HIPCI Pump Discharge Check Valve FUNCTION: V23-0049 opens to allow ECCS injection into the vessel.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refuel outages.

ISTC-5221(c) If the test methods in ISTC-5221(a) and ISTC-5221 (b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement.

ISTC-5221(c)(3) At least one valve from each group shall be disassembled and examined at each refuel outage; all valves in each group shall be disassembled and examined at least once every 8 years.

BASIS: This check valve has no positive means of determining valve disk position, thus, the only practical method of verifying full stroke (open) is by measuring full accident flow through the line.

However, opening this valve quarterly with HPCI system flow is not practical during plant operation due to the potential for severe reactor vessel water level and temperature transients as well as possible contamination of reactor feedwater. At cold shutdown steam is not available for pump operation.

Alternate Testing: This valve will be grouped and examined in-accordance with ISTC-5221(c). At least one valve in a group will be disassembled and examined each refueling outage.

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DAEC Station 4 nTInterval Inservice Testing Program Deferred Test Justification DTJ-32 SYSTEM: High Pressure Coolant Injection Reactor Core Isolation Cooling COMPONENTS: V23-0001 - IIPCI Pump Torus Supply Check Valve V25-0001 - RCIC Pump Torus Supply Check Valve FUNCTION: These check valves open to provide a flowpath from the torus to the HPCI and RCIC pumps.

TEST REQUIREMENTS: ISTC-3522(c) if exercising is not practicable during operation at power and cold shutdown, it shall be performed during refuel outages.

ISTC-5221(c) If the test methods in ISTC-5221(a) and ISTC-5221(b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement.

ISTC-5221(c)(3) At least one valve from each group shall be disassembled and examined at each refuel outage; all valves in each group shall be disassembled and examined at least once every 8 years.

BASIS: Both the HPCI and RCIC systems inject into the feedwater lines.

Operation of the RCIC or HPCI pumps from the torus is not practical due to reactor water chemistry concerns.

Alternate Testing: These valves will be grouped and examined in-accordance with ISTC-5221(c). At least one valve in a group will be disassembled and examined each refueling outage.

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DAEC Station 4T11 Interval Inservice Testing Program 12.0REFERENCE DOCUMENTS This Program Plan was developed per the requirements and guidance provided by the following documents:

12.1 Title 10, Code of Federal Regulations, Part 50.55a (10-1-04 Ed.).

12.2 NRC Regulatory Guides - Division 1 12.3 Standard Review Plan 3.9.6, "Inservice Testing of Pumps and Valves" 12.4 Updated Final Safety Analysis Report, Duane Arnold Energy Center 12.5 Duane Arnold Energy Center Technical Specifications 12.6 ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition, No Addenda 12.7 NRC Generic Letter 89-04, "Guidance on Developing Acceptable Inservice Testing Programs" 12.8 ASME OM Code-2001 through 2003 addendum "Code for Operation and Maintenance of Nuclear Power Plants".

12.9 NUREG-1482 rev. 1, Guidelines for Inservice Testing at Nuclear Power Plants 12.10 01-692 "Turbine Steam Seal System" Operating Instructions 12.11 General Electric Service Information Letter 477 12.12 NRC Information Notice 85-84 "Inadequate Inservice Testing of Main Steam Isolation Valves" 12.13 NRC Generic Letter 89-16 "Installation of a Hardened Wetwell Vent" 12.14 10CFR50 Appendix J Revision 0 (Section 12 Page 1 of 1)

NG-05-0427, Inservice Testing Program, Fourth Ten-Year Interval Update

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