Text

ASME OM Code In-Service Testing Program Document
	ML16299A278
Person / Time
Site:	Catawba
Issue date:	08/31/2016
From:	; Duke Energy Carolinas
To:	; Office of Nuclear Reactor Regulation
References
	CNS-16-067
	Download: ML16299A278 (359)
	v • d • e

{{#Wiki_filter:CATAWBA NUCLEAR STATION ASMEOMCode

              'Jn-Service Testing Program Document August 2016 Revision 08 Fusion Revision 30 JV 10/5/16 Prepared by:                                 Date:  7-21-ZLJ/{o Reviewed by: ,                               Date: 1/).1/2010

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DOCUMENT REVISION DESCRIPTION REVISION PAGES or SECTION REVISED AND DESCRIPTION NO. 5 Revised per PIP C10-1060. Specific changes include:

Revised NC PORV Stroke Requirement Position Statement (Enclosure 9.6),.
Added new MSIV Stroke Requirement Position Statement (Enclosure 9.7),
Revised Enclosure 9.9, Priority for Cold Shutdown Valve Testing, (1) replacing 1(2)NI009A inadvertently removed via previous revision and (2) adding Special Note 3 for MSIV Cold Shutdown Valves, and
Other minor changes to support clarity and format.

6

Added new Enclosure 9.9, Containment Penetration Check Valve Position Statement. Other minor changes for structure and format.

7

Added new Step 4.2.9, Thermal Expansion Check Valves (PIP C-11-5991 CA#21). Corrected items identified during the 2012 CNS IST Program Assessment (PIP C-12-09204 CA#5). Other minor changes for structure and format.

8

Revised to Update Program to the 4th Interval.

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CNS ASME In-service Testing Program Rev. 08 Page 2 of 60 CNSSCOPE.DOC 7/21/2016

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TABLE OF CONTENTS 1.0 Program Document 1.1 Scope of Document 1.2 References 1.3 Definitions and Terms 1.4 Valve Program 1.4.1. In-Service Testing (IST) Program 1.4.2 Valve Testing Program Exemptions and Position Statements 1.4.3 Check Valve Testing 1.4.4 Relief Valve Testing 1.4.5 Leak Rate Testing 1.4.6 Testing from Remote Locations 1.4.7 Post Maintenance and Modification Testing (Retest) 1.4.8 Fail-Safe Testing of Valves 1.4.9 Skid-Mounted Valves 1.4.10 Valve Test Acceptance Criteria 1.5 Pump Program 1.5.1 In-Service Testing (IST) Program Pump testing Program Exemptions and Position Statements 1.5.2 1.5.3 Vibration Monitoring 1.5.4 Testing Required from Remote Locations 1.5.5 Post Maintenance and Modification Testing (Retest) 1.5.6 Skid-Mounted Pumps 1.5.7 Pump Test Acceptance Criteria 1.5.8 Pump Group Classification 1.5.9 Pump Design 1.5.10 Standby Make-up Pumps 1.6 Snubber Program 1.6.1 Purpose 1.6.2 Scope 1.7 Relief Request 1.7.1 Implementation of Relief Request

1. 7 .2 Code Cases 1.8 Justification for Deferrals 1.8.1 Testing Deferral Justifications 1.9 Appendices Appendix A: IST Program Responsibilities 10CFR50, Appendix B, Supplemental Program Guidance Document Appendix B:

Appendix C: Notification of Program Changes CNS ASME In-service Testing Program Rev. 08 Page 3 of 60 CNSSCOPE.DOC 7/21/2016

TABLE OF CONTENTS (continued) 1.10 Enclosures Enclosure 10.1: Enclosure 10.2: Enclosure 10.3: Revising the Program Document Relief Request Template Justification for Deferral Enclosure 10.4: System Piping Classification Correlation Enclosure 10.5: Valve Stroke Time Data Evaluation Flow Chart Enclosure 10.6: NC PORV Stroke Requirement Position Statement Enclosure 10. 7: MSIV Stroke Requirement Position Statement Enclosure 10.8: SA-1 & SA-4 Position Statement Enclosure 10.9: Containment Penetration Check Valve Position Statement Enclosure 10.10: Priority for Cold Shutdown Valve Testing Enclosure 10.11: Position Indication Tests of Manual Actuated Pneumatic Valve Position Statement Enclosure 10.12: SG PORV Stroke Requirement Position Statement 2.0 Table of Abbreviations for Pump and Valve Summary Tables 3.0 Pump lnservice Testing Program 4.0 Valve lnservice Testing Program 5.0 Relief Request

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6.0 Justification for Deferral 7.0 Supplemental Testing Program i.e. Augment Testing Program CNS ASME In-service Testing Program Rev. 08 Page 4 of 60 CNSSCOPE.DOC 7/21/2016

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1.1 SCOPE OF DOCUMENT

The purpose of the Catawba Nuclear Station (or hereafter referred to as "licensee" or "CNS")

In-Service Testing (IST) Program, as related to this document, is to assess the operational readiness of safety related pumps, valves, and dynamic restraints (snubbers) in accordance with ASME and NRC guidelines. This documented discusses the intent of the licensee's testing positions and philosophies with regards to the ASME Operations and Maintenance (OM) Code. It is not the purpose if this document to reiterate the ASME or NRC guidance in their entirety. Additionally, this document outlines the process for additional, changes, and deletions of pumps and valves from, and to, the IST Program. Technical Specifications require performance testing of pumps, valves, and dynamic restraints in accordance with ASME OM Code. This program document defines how CNS complies with the ASME OM Code and Technical Specification. Failure to meet the requirements of this program is a violation of Technical Specifications and 10CFR 50.55a. At CNS, the safe shutdown condition is defined as Mode 3, Hot Shutdown (Tech Spec B 3.3.4). 1.1.1 Program Period: Fourth Ten-Year Interval (120-month period beginning August 19, 2016); Unit(s) 1 and 2 concurrently; and ends on August 19, 2025. The start of this fourth ten-year interval was delayed by one-year as allowed by ASME

OM Code Subsection ISTA-3120(d). This paragraph provides allowance for each inservice test interval to be extended or decreased by as much as one year. Adjustment shall not cause subsequent intervals to be altered by more than one year from the original pattern of intervals. This delay was necessary to complete a review performed by contract services and to implement the recommended changes to the station inservice testing practices. With this delay, the fourth ten-year interval will be shortend 1

by one year, ending on Auguat 19, 2025. 1.1.2 Applicable ASME Code(s) and Addenda: ASME OM-2004 Edition; including OMb Code-2006 Addenda; and subject to the OM conditions, limitations, and modification in 10CFR50.55 a(b)(3). When approved by the NRC (ref: Regulatory Guide 1.192, Operating And Maintenance Code Case Acceptability, ASME OM Code), Catawba Nuclear Station will adopt the frequency requirements for extending periods (grace) for inservice testing of pumps and valves specified in ASME OM Code Case OMN-20, lnservice Test Frequency. Currently, the ASME OM Code does not provide for any frequency reductions or extensions of the surveillance periods* for pump and valve inservice testing. Code Case OMN-20 identifies a delay period for the inservice test frequencies for pumps and valves which a licensee may voluntarily apply. The NRC has reviewed Code Case OMN-20 and has found it acceptable for use. Catawba has not submitted a relief request for NRC approval to apply Code Case OMN-20. Therefore, Catawba will apply this "grace" period after this allowance is published in Regulatory Guide 1.192. CNS ASME In-service Testing Program Rev. 08 Page 5 of 60 CNSSCOPE.DOC 7/21/2016

1.1.3 Program Changes: The NRC shall be notified of IST Program changes; however, component additions and 1 deletions will be submitted and testing implemented or deleted without prior NRC

approval. In the instance where a component has been added to the IST Program, testing and the appropriate procedure changes will take place in a timely manner, but not exceeding one test period, after revising the program source documents unless determined to be impractical. If a hardship is identified, notification will be submitted to the NRC and an interim extension from testing implementation obtained.

The content of this program document is based on recommendations stated in NUREG-1482 (Rev. 2) and is intended for the purpose of maintaining program continuity and documenting additional discussions and positions relative to Code interpretations. Therefore, changes to this program document will not require prior NRC review and/or approval unless the licensee determines a need to do so.

1.2 REFERENCES

The following documents were used as references in the development of this document: ASME OM Code 2004 (plus addenda)"' Generic Letter 89 Safety-Related Motor-Operated Valve Testing and Surveillance Generic Letter 96 Periodic Verification of Design-Basis Capability of Safety-Related Power-Operated Valves Generic Letter 96 Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions 10 CFR 50, Appendix B 10 CFR 50.55a Technical Specifications Updated Final Safety Analysis Report (UFSAR) Nuclear System Directive: 408 Testing Reg. Guide 1.26 NRC Inspection Procedure 73756 NUREG/CP-0123, Proceedings of the NRC/ASME Symposiums on Pump and Valve Testing NUREG-1482 (Rev. 2), Guidelines for In-service Testing at Nuclear Power Plants, October 2013 NRC Information Notice 97-90 NRC Information Notice 97-16 CNS ASME In-service Testing Program Rev. 08 Page 6 of 60 CNSSCOPE.DOC 7/21/2016

1.3 DEFINITIONS and TERMS

AD-EG-CNS-1618, CNS Snubber Program Plan Generic Letter 89 Generic Letter 96 the NRC letter providing additional requirements in testing MOVs to design basis conditions.

the NRC letter requiring periodic verification of the capability of safety-related MOVs to perform their safety functions consistent with the current licensing bases. Generic Letter 96 the NRC letter notifying addressees about safety-significant issues that could affect containment integrity and equipment operability during accident conditions. NUREG-1482 - the NRC document that gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves. ASME OM Code - the section of ASME Codes and Standards Manual that determines how to perform in-service testing of light water reactor nuclear plant components. ASME ISTC Code - the part of ASME OM Codes dealing with the in-service testing of valves .

ASME ISTB Code -

ASME OMN-20 the part of ASME OM Codes dealing with the in-service testing of pumps. the OM Code Case that established the method for extending the test frequencies (i.e. "grace") for inservice testing of pumps and valves. Frequencies - the interval of time between in-service testing of the components. These intervals are defined in CNS Technical Specifications:

1) Quarterly (3 months) - once every 92

2) Cold Shutdown (CSD) - Average Coolant Temperature (Tavg) <

200°F

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

IST Component- components (valves and pumps) that are required to be tested per ASME OM Code. Sections 4.1 and 5.1 of this document define the criteria to be included in the IST Program .

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1.3 DEFINITIONS and TERMS (continued) "App. B Component" - components (valves and pumps) tested under of 10CFR50, Appendix

B. Used interchangeable with the term "Augmented Test Program".

NOTE: CNS historically included "App. B Component" within the station's "Supplemental Testing Program". For CNS 4th 1Oyr Interval, this reference was changed to the "Augmented Testing Program". "App. J Component" - components leak tested for containment integrity under 10CFR50, Appendix J (including Option B). Active Component - a component that must perform a mechanical motion during the course of accomplishing a system safety function. Passive Component- - a component that does not perform a mechanical motion during the course of accomplishing a system safety function. Operational Readiness - the ability of a component to perform its intended function when required. Seat Tightness Test - a qualitative test performed to assess a valve's ability to shut off between its disc and seat in accordance with the Owner established seat tightness criteria typically performed on PORVs as required by System Resistance - Trending - ISTC-5112. the hydraulic resistance to flow in a system. a comparison of current data to previous data obtained under similar conditions for the same equipment. Set Point- the value for which relief valves are set to relieve pressure. Leak Test- testing of valves to verify seat leakage is limited to a specified maximum. Stroke-Time - the time interva'1 from valve actuation to the limit switch indication light at the end of the actuating cycle. Limiting Stroke Time - the maximum time allowed for a valve to stroke before becoming immediately inoperable. Relief Requests - A request submitted to the NRC requesting relief from the requirements of the Code for testing a particular component or a generic group of components. Justif. For Deferrals - A documented explanation of why a valve can only be tested at a cold shutdown or refueling outage frequency as opposed to quarterly . CNS ASME In-service Testing Program Rev. 08 Page 8 of 60 CNSSCOPE.DOC 7/21/2016

1.3 DEFINITIONS and TERMS (continued)

Group A Pump-Group B Pump -

pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations. pumps in standby systems that are not operated routinely except for testing. Category A Valves -

valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required function(s).

Category B Valves - valves for which seat leakage in the closed position is inconsequential for fulfillment of the required function( s). Category C Valves - valves that are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) for fulfillment of the required function(s) .

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 9 of 60 7/21/2016

1.4 VALVE PROGRAM 1.4.1 In-Service Testing (IST) Program As required by 10CFR50.55a, valves that are classified in accordance of NRC Regulatory Guide 1.26 as Safety Class A, B, or C, which corresponds to ASME Class 1, 2, or 3 respectively, under the scope of ISTA, are included in the CNS IST Program. The following defines the criteria for inclusion of equipment in the IST Program: a) All Category A valves that fall within the Duke ISi Class A, B, or C boundaries. b) All Category Band C valves that fall within the Duke ISi Class A, B, or C boundaries and are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of the Design basis Accidents (Design Basis Accidents are defined as those described in Chapter 15 of the UFSAR). c) Valves in systems specifically required by Technical Specifications to be tested per ASME OM Code. CNS has some valves that are active in certain non-Design Basis Events, are cold shutdown valves not associated with an UFSAR Chapter 15 event, are significant to plant safety, or are of economic importance that are beyond the scope of 10CFR50.55a. Such valves will be tested in the Augmented (10CFR50 Appendix B) Program. See Appendix B of this document for a discussion of this program. The scope of the OM Standards and Code has not been expanded to include all safety-related pumps and valves in the IST Program. Until the scope of 10CFR50.55a is changed, the scope of the IST Program will continue to be limited to only those components within the applicable ASME Code Class 1, 2, or 3 systems unless otherwise determined by the licensee (reference NUREG-1482, rev. 2). 1.4.2 Valve Testing Program Exemptions and Position Statements Valves tested under jurisdiction of this program will be tested per requirements of OM ISTC at the specified frequencies unless it has been determined to be impractical. This section of the program document provides CNS positions on interpretations, guidance, and other options regarding testing alternatives. 1.4.2.1 Category A and AJC valves (containment, pressure isolation, and other applicable valves) will be leak tested in accordance with ISTC-3600. 1.4.2.2 Valves that stroke in less than 2 seconds may be exempted from reference ranges and the maximum limiting stroke time shall be 2 seconds as specified by OM ISTC-5152 .. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 1O of 60 7/21/2016

1.4.2 Valve Testing Program Exemptions and Pos. Statements (continued)

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

1.4.2.4 OM ISTA-9230 identifies the minimum documentation requirements for a completed test or examination; which includes the signature of the person or persons responsible for conducting and analyzing the test. The dated initials of the person or persons responsible for conducting and analyzing the test may be used, provided the signature and initials are properly documented together within record of the tests. 1.4.2.5 It is the licensee's position that valve testing will be deferred if the normal Code required test frequency or plant conditions would result in increased personnel risk or damage to plant equipment. Practicality of such deferral shall be determined by the licensee and documented in the "Justification for Deferral" section of the IST Program manual. In such cases, the licensee will not perform any type of destructive testing to determine the period of time at which damage to the

equipment or risk to personnel would occur. Exercising valves on a cold shutdown or refueling outage frequency is not a deviation from the Code (reference NUREG-1482, Section 2.4.5).

NOTE: For cold shutdowns less than 48 hours, valve testing does not have to be performed. However, for cold shutdowns expected to exceed 48 hours, valve testing will commence as soon as possible, but no later than 48 hours after

reaching cold shutdown. Valve testing will proceed in a normal manner until all testing is complete or the plant is ready to return to power. It is expected that Operations and Outage Scheduling will expend a 'good faith' effort to perform cold shutdown testing during a short outage. A completion of all valve testing is not a prerequisite to return to power. Any testing not completed by the end of one cold shutdown will be performed during subsequent cold shutdowns, starting from the last test performed at the previous cold shutdown.

1.4.2.6 Manual valves that meet the scope requirements of OM ISTC-3500 or are credited in the safety analysis as capable of being repositioned to shut down the plant, to maintain the plant in a safe shutdown condition, or to mitigate the consequences of an accident will be included in the IST Program. Active manual valves will be exercised at a frequency not to exceed 2 years .

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 11 of 60 7/21/2016

1.4.2 Valve Testing Program Exemptions and Position Statements (continued) 1.4.2.7 Valves that are not categorized as ISi Class A, B, or C need not be included in the

IST Program. However, according to NUREG-1482, Section 2.2, "The intent of 10 CFR 50 Appendix A, GDC-1, and Appendix B, Criterion XI, is that all components, such as pumps and valves, that are necessary for safe operation must be tested to demonstrate that they will perform satisfactorily in service." The licensee may opt to include valves which do* not meet these criteria in the IST Program or in the Augmented Test Program. CNS will not submit Relief Requests or Justification for Deferrals for "Non-Code"- Class valves.

1.4.2.8 Thermal Relief Valves that meet the scope requirements of ISTA or are credited in the safety analysis for being capable of relieving pressure in Code Class 1, 2 and 3 piping systems by maintaining the plant in a safe shutdown condition, or in mitigating the consequences of an accident will be included in the IST Program. However, testing of such valves will be based on exercising frequencies established by the guidance given in OM Code, Appendix I, section 1-1300. 1.4.2.9 Thermal Expansion Check Valves: Several containment penetrations have been fitted with normally closed check valves designed to open to pass flow created by thermal expansion of fluid within the penetration (NRC GL 96-06). The quantity of flui(:J thermal expansion is so small that any opening of the check valve will allow it to pass the required flow to prevent over pressurization of the containment penetration. Open testing will be performed by verifying the ability to pass any amount of flow. Flow will not be quantified. NOTE: Thermal Expansion Check Valves are tested in accordance with the station Check Valve Condition Monitoring Program and Enclosure 9.9, Containment Penetration Check Valve Position Statement. 1.4.2.10 Containment Purge Valves (VPs), which are passive in the closed direction, will be leak tested per 10 CFR 50, Appendix J but not stroke-timed for IST purposes. Containment Purge valves are "passive" in Modes 1-4. During a postulated fuel handling accident inside the containment, no credit for containment isolation or mixing in the containment is taken. System design assures a safe release path from the containment with the VP system in operation. The radiological consequences of a postulated fuel handling accident are within the exposure guideline values of 10CFR 100. 1.4.2.11 Containment Hydrogen Purge Valves (VY), which are passive in the closed direction, will be leak tested per 10 CFR 50, Appendix J but not stroke-timed for IST purposes. These valves are "passive" in Modes 1-4. CNS Technical Specifications requires exercising these valves. However, power is removed and these valves are placed under administrative control as to not permit re-positioning after they have been leak-tested per Appendix J. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 12 of 60 7/21/2016

1.4.3 Check Valve Testing

Check valves tested under the jurisdiction of this program will be tested per Code requirements at the specified frequencies unless it has been determined to be impractical.

This section of the program document is to provide the CNS positions concerning interpretations, guidance, and other options and testing alternatives for check valves. 1.4.3.1 For check valves in series, where one of two valves is credited in the safety analysis, the verification that the pair of valves is capable of closing will be done on the basis of testing one of the check valves. 1.4.3.2 Category A and AJC valves (containment, pressure isolation, and other applicable check valves) will be leak tested in accordance with ISTC-3600. 1.4.3.3 Full stroke testing of check valves will not necessarily constitute the obturator contacting the back-stop. Where possible, sufficient flow will be passed through the valve to verify design basis accident flow. If full flow is not possible, then the licensee will perform correlation testing, partial stroking, or other alternatives as provided by ISTC-5220, Check Valves, and/or ISTC-5222, Condition Monitoring Program. Additionally, the Code allows use of indirect evidence (such as system pressure, flow, temperature, or level) or other positive means to verify flow or pressure requirements. These indirect methods will not be subject to the range and accuracy requirements of ISTC-3800. (Ref. ISTC-3530)

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

1.4.3.5 Check valves included in the Sample Disassembly portion of the IST Program will be disassembled and inspected under the provisions and guidelines given in ISTC-5221. . 1.4.3.6 Where applicable to the CNS IST Program, reverse flow testing of check valves will be performed by methods as follows:

Pump discharge check valves - verified closed by meeting a parallel pump's acceptance criteria while cross-connected;
Appendix J testing;
Measure back flow through the valve using an open vent on the backside of the valve or ultrasonic flow measurement techniques;
Pressure drop across a pump;
Pump wind-milling (when determined acceptable);
Observation of external indication on valve stem .
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1.4.3 Check Valve Testing (continued) 1.4.3.7 As an alternative to the testing and/or examination requirements of ISTC-3510,

ISTC-3520, ISTC-3530, ISTC-3550, and ISTC-5221, the licensee has developed a conditioning monitoring program for check valves. Details of the program may be found in the program document for the Catawba Check Valve Condition Monitoring Program (ref.: ISTC-5222).

1.4.3.8 The licensee recognizes the NRC's acceptance of non-intrusive techniques (N.l.T.) for testing check valves and will randomly apply N.l.T. to the check valve program. Validation that such equipment meets the plant's QA Program is the responsibility of the licensee. Therefore, N.l.T. remains a voluntary option and will be evaluated on an individual application basis. 1.4.4 Relief Valve Testing Relief valves tested under the jurisdiction of this program will be tested per Code requirements of ASME OM Code Appendix I, unless it has been determined to be impractical. Relief valves shall be considered for inclusion in the program if it performs a specific function or if it provides overpressure protection for portions of systems that perform a specific function in shutting down a reactor or in mitigating the consequences of an accident. 1.4.5 Leak Rate Testing All category A and A/C valves will be tested per ISTC-3600, except those valves which function in the course of plant operation in a manner that demonstrates functionally adequate seat leak-tightness need not be additionally leakage tested. In such cases, the valve record shall provide the basis for the conclusion that operational observation constitutes satisfactory demonstration. Category A and A/C containment isolation valves (CIVs) shall be tested per 10CFR50 Appendix J (Option B), which allows testing interval extension beyond the nominal 30 months for those CIVs with acceptable performance. The actual testing interval can be determined from the Leakrate Program. Where a valve is identified as a containment isolation valve in the Technical Specification or UFSAR and if it is determined to be an "active" valve with respect to this function, it will be exercised to both the open and closed positions. 1.4.6 Testing from Remote Location ISTC-3700 requires valves with remote position indication to be observed locally at least once every 2 years to verify that the valve operation is accurately indicated. Valves that have remote operating switches and/or power supplies shall also be tested and verified for proper indication from the remote location. Refer to Technical Position (Enclosure 10.11) for additional information. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 14 of 60 7/21/2016

1.4.7 Post Maintenance and Modification Testing (Retest)

Reference Nuclear System Directive 408 - Testing.

1.4.8 Fail-Safe Testing of Valves All Fail-Safe valves shall be tested in accordance with ISTC-3560. Valves used only for system control, are typically excluded from testing in the IST Program. However, if a control valve must change position to support a safety-related function and it has a fail-safe position, then it will be included in the program and tested to verify the ability to perform that function with power and/or air removed (or simulated power and/or air removal). Additionally, for power-operated control valves that only have a fail-safe safety function, the requirements for valve stroke-time measurement testing, the associated stroke time test acceptance criteria, and any corrective actions that would result from stroke-time testing need not be met (ISTC-5100). 1.4.9 Skid-Mounted Valves As specified in ISTC-1200, skid mounted valves will be excluded from the scope of IST test requirements provided they are adequately tested as part of the 'major' component. The licensee however, may opt to include certain components contained on these skids in the IST program for testing and trending purposes. In such cases, any program changes, exceptions, exemptions, or deferrals will not be submitted to the NRC for prior approval, but simply documented in the program plan. Examples of skid components include FD,

VG and LO system valves .

1.4.10 Valve Test Acceptance Criteria All valve test acceptance criteria (IST-TAC) will be developed in accordance with the provisions specified in ISTC-3300 and ISTC-5100. Where IST-TAC, other than that required by Code, is established for a given valve (e.g., additional N.l.T. diagnostics or GL 96-05 testing), the documentation of that criteria will be at the discretion of the licensee and not required to be part of the test record. IST-TAC should not be confused with the acceptance criteria specified in DBDs, DBD associated TAC Sheets, Technical Specifications, or UFSAR. Such acceptance criteria are the most limiting values and cannot be exceeded. IST-TAC is set to verify operational readiness of the valves and to identify valve degradation before the 'most limiting' acceptance criteria is exceeded. IST-TAC will be evaluated to verify that other acceptance criteria specified (UFSAR, DBD, TS, etc.) will not be exceeded. Leakage criteria for valves (other than those tested in accordance with 10CFR50 Appendix J, Technical Specification, or system specific criteria), will be determined based on leakage rates specified by the licensee or using the guidance provided in ISTC-3630. Relief valve IST-TAC will be established per Appendix I, or developed using licensee calculations as permitted by the OM Code .

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1.4.10 Valve Test Acceptance Criteria (continued) 1.4.10.1 Valve Stroke-Time Acceptance Criteria: The following cases present the options available for determining valve operability based on stroke time: CASE 1: The valve strokes within its acceptable stroke time. The valve is considered operable. CASE 2: The valve fails to change position on the first try or exceeds the LIMITING VALUE. The .valve shall. be immediately declared inoperable. CASE 3: The valve fails to meet the acceptance stroke time, but strokes in less than the LIMITING-VALUE. Per ISTC-5100, the valve shall be immediately stroked again to achieve an acceptable stroke time. Per the Catawba Valve Testing Program:

a. If the valve successfully strokes on the second stroke, the valve is considered operable. The cause of the initial deviation shall be analyzed and the results documented in the record of test (i.e. WO or Condition Report). A third valve stroke may be performed to demonstrate consistent valve operation.

b. If the valve does not fall within the acceptable range on the

second stroke, then the valve will be analyzed within 96 hours OR declared inoperable (if applicable). An evaluation must be performed to determine the cause of the failed test (deviation).

The evaluation may determine that either corrective maintenance must be performed on the valve or the new stroke data is acceptable and new baselines must be established. Such results must be documented in the record of test (i.e. WO or Condition Report).

c. In the event the initial stroke and the second test results are inconsistent, but the engineering evaluation shows the new stroke-time is acceptable, a third test may be performed to verify consistent behavior.

d. If a valve fails its stroke time, subsequent testing may be performed to reconfirm the original stroke time reference value and the faulted test may be determined invalid.

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 16 of 60 7/21/2016

1.4.10 Valve Test Acceptance Criteria (continued)

1.4.10.2 Valve Stroke-Time Measurements and Methods:

Valve stroke-times are measured with a stopwatch to the nearest second. The stopwatch is started when the valve is actuated and it is stopped when an indication light is received indicating that the valve has completed its full stroke. OAC measurement using the Response Time Test (RTT) function is also an acceptable means of valve stroke timing. 1.4.10.3 Limiting-Value Stroke-Time Acceptance Criteria: Limiting-Values for stroke-times will be established in accordance with guidance given in NUREG-1482, Section 4.2.1. It is the position of the licensee that these values will be determined as follows (with the limitations of Tech. Specs. and Safety Analysis limits being the most limiting): Valve Type Limiting Value Calculation MO (> 1Osecs.) 1.3R (to the nearest 0 or 5 sec.) MO (~ 1Osecs.) 1.5R (to the nearest 0 or 5 sec.) AO & EH(> 1Osecs.) 2.0R (to the nearest 0 or 5 sec.)

AO & EH (~ 1Osecs.) 2.25R (to the nearest 0 or 5 sec.)

Note: Where 'R' represents the valve reference value at acceptable operation. MO - Electric Motor Operated Valve EH - Electric Hydraulic Operated Valves AO - Pneumatic (air) Operated Valve

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1.5 PUMP PROGRAM 1.5.1 In-Service Testing (IST) Program As required by 10CFR50.55a certain pumps that are classified in accordance of NRC Regulatory Guide 1.26 as ISi Class A, B, or C, which corresponds to ASME Class 1, 2, or 3 respectively, under the scope of ISTA, are included in the IST Program. The following defines the criteria for inclusion of equipment in the IST Program: a) Pumps in systems specifically required by Technical Specifications to be tested per ASME OM Code ISTB. b) All pumps that fall within the Duke ISi Class A, B, or C boundaries that are required to perform a specific function in shutting down the reactor to a safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of the Design Basis Accidents (Design Basis Accidents are defined as those described in UFSAR Chapter 15). Certain pumps where the only required function is during non-Design Basis Events will be tested in the Augmented (10CFR50 Appendix B) Program. See Appendix B for a discussion of this program. 1.5.2 Pump Testing Program Exemptions and Position Statements Pumps tested under the jurisdiction of this program will be tested per Code requirements

of ISTB at the specified frequencies unless it has been determined to be impractical. The purpose of this section of the program document is to provide CNS positions on interpretations, guidance, and other options regarding testing alternatives.

5.2.1 OM ISTA-9230 identifies the minimum documentation requirements for a completed test or examination; which includes the signature of the person or persons responsible for conducting and analyzing the test. The dated initials of the person or persons responsible for conducting and analyzing the test may be used, provided the signature and initials are properly documented together within record of the tests. 5.2.2 Pumps whose only safety function is predicated on plant shutdown and recovery from a fire per commitments made as a result of NFPA-805 (Fire Protection) are not required to be included in the IST Program. The licensee will test these in accordance with NFPA-805 requirements. 5.2.3 Pumps that are not provided with an emergency source of power will not be required to meet IST requirements. The licensee however, may elect to include these pumps in the IST Program for testing purpose only. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 18 of 60 7/21/2016

1.5.3 Vibration Monitoring

Pump vibrations monitored under the jurisdiction of this program will be performed per Code requirements at the specified frequencies unless it has been determined to be impractical or a specific deviation from Code is needed and obtained.

1.5.4 Testing Required form Remote Locations (Not Applicable to Catawba Nuclear Station) 1.5.5 Post Maintenance and Modification Testing (Retest) Reference Nuclear System Directive 408 - Testing 1.5.6 Skid-Mounted Pumps As specified in ISTB-1200, skid mounted pumps will be excluded from the scope of IST Program Plan provided they are adequately tested as part of the 'major' component. The licensee however, may opt to include certain components contained on these skids in the IST Program Plan for testing and trending purposes. In such cases, any program changes, exceptions, exemptions, or deferrals will not be submitted to the NRC for prior approval, but may be documented in the program plan. 1.5.7 Pump Test Acceptance Criteria

All pump test acceptance criteria (IST-TAC) will be developed in accordance with the provisions specified in ISTB. The applicable acceptance criteria will be developed when the pump is known to be performing in a satisfactory manner. Where IST-TAC other than that required by Code is established for a given pump (i.e., pump curves), the documentation of that criteria will be at the discretion of the licensee and may not be part of the test record.

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

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1.5.8 Pump Group Classification ASME OM Code requires pumps be defined as Group A or Group B, which in turn defines

the test type and frequency. ISTB-2000, Supplement Definitions, provides the characteristic for identifying both group A and B pumps. ISTB-3400, Frequency of lnservice Tests, and ISTB-5120, lnservice Testing, provides the testing requirements for both groups.

Group A Group B KC CA ND NI NV NS RN SMP YC The following sump pumps are tested as part of the IST Program and are subject to Comprehensive Pump test requirements only (no Group B test required, ISTB-3430): WL- ND & NS Room Pit Sump Pumps WL - TD CA Pump Pit Sump Pumps WN - EOG Room Sump Pumps 1.5.9 Pump Design The ASME OM ISTB Code imposes different requirements depending on the pump design. There three basic designs: centrifugal or CP, positive displacement or PDP, and vertical

line shaft or VLS. The VLS pumps at CNS are the Nuclear Service Water pumps and sump pumps. The PDP pumps at CNS are the Standby Make-up Pumps. The remaining pumps are CP pumps. Code Table ISTB-5121-1, 5221-1, and 5321-2 provides the testing parameters and ranges based on pump design.

1.5.10 Standby Make-up Pumps The standby make-up pumps or SSF pumps are part of the Augmented Testing Program. These are non-safety, non-Code pumps and are therefore not subject to the full extent of Code testing. They are important for mitigation loss of control room events, SBO, etc. (non-Design Basis events) and will be testing accordingly. The extent of testing will be flow and dis~harge pressure only. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 20 of60 7/21/2016

1.5 SNUBBER PROGRAM

1.6.1 Purpose The intent of the !STD-Snubber Program is to determine and ensure snubber operational readiness through periodic examinations, testing, and service life monitoring. Title 10CFR50.55a invokes perservice and inservice testing of snubbers per ASME OM Code and establishes the requirements that each nuclear power plant must developed and implement a preservice and inservice examination and testing program for snubbers.

1.6.2 Scope The Snubber Program includes all snubbers installed at Catawba Nuclear Station Unit 1 and 2. Those snubbers testing in the program are selected and tested in accordance with the ASME OM Code, 2004 Edition of ISTA and ISTD, through the 2006 Addenda. Ref.: AD-EG-CNS-1618, CNS Snubber Program Plan 1.6 RELIEF REQUEST The purpose of a Relief Request is to request the NRC grant relief from those requirements of the existing Code that cannot be followed. NRC review and approval of the alternative testing is required. If the testing on the component cannot be performed due to plant configuration, plant safety, equipment limitations, type, or hazards to personnel,

relief from the Code will be requested. Submitted relief requests will:

a) b) give an alternative method that ensures an acceptable level of quality and safety, explain the hardship with meeting the Code requirement, c) provide a schedule or alternative test, frequency (or duration for interim Relief Request). At the end of each 'Ten Year Interval', all Relief Requests will be reviewed for next interval applicability Relief Requests will not be written for any non-Code Class components that are included in the IST Program at the licensee's discretion. 1.7.1 Implementing Relief Requests: When a Relief Request is submitted for those requirements which have been determined to be clearly impractical, the licensee reserves the right to implement the proposed alternative testing while the NRC is reviewing the Relief Request, providing the licensee has assured the alternative does not compromise the level of safety provided by the Code testing requirement. This position is referenced from NUREG-1482, section 2.5 .

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1.7.2 Code Cases In accordance with 10CFR50.50a(b), code cases referenced in Regulatory Guide (RG)

1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code" may be used without obtaining further review. RG 1.192 provides a list of code cases that are acceptable provided they are used in their entirety, with any supplemental conditions specified in the regulatory guide. In addition, RG 1.192 provides a list of code cases which are "conditionally acceptable", meaning that they are acceptable within the limitations described in RG 1.192.

1.7.2.1 Application of Code Cases

Code cases to be used during a preservice or inservice test or examination are listed in this IST Program.

When approved by the NRC (ref: Regulatory Guide 1.192, Operating And Maintenance Code Case Acceptability, ASME OM Code), Catawba Nuclear Station will adopt the frequency requirements for extending periods (grace) for inservice testing of pumps and valves specified in ASME OM Code Case OMN-20, lnservice Test Frequency.

Code cases used in this IST Program are applicable to code of record identified in paragraph 1.2.
Code cases shall be in effect.at the time this IST Program is filed, except as
provided below.
Code cases issued subsequent to filing this IST Program may be proposed for use in amendments to this IST Program.

1.7.2.2 Application of Revised Code Cases

Superseded code cases approved for use in accordance with paragraph 7.2.1 may continue to be used.

1.7.2.3 Application of Annulled Code Cases

Code cases approved for use in accordance with paragraph 7.2.1 or 7.2.2 may be used after annulment for the duration of this IST Program Interval Program Plan.

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1.8 JUSTIFICATION FOR DEFERRALS:

Justification for Deferrals (JFDs) will be written when a component cannot be tested at the specified frequency. This could be due to an impracticality of testing the component at power or due to plant safety concerns introduced by the testing configuration. The basis for determining the impracticality of testing at power and expanding the component's testing frequency to a Cold Shutdown (CSJ) or Refueling Outage (RFJ) frequency is documented in the Justification for Deferral.

In-Service Testing to be performed at Cold Shutdown shall: a) be performed during each cold shutdown when the planned length is of sufficient duration to establish the necessary test conditions and to perform the test, and b) be performed as to not impact the timely completion of the shutdown related activities and subsequent return to operation. *For outages when the planned length is not of sufficient duration to complete all tests, testing will start within 48 hours and proceed with "good faith" effort after reaching cold shutdown conditions, or c) be performed at the next available cold shutdown consistent with the above criteria if an opportunity to test t.he valve is not available. Completion of the IST is not a prerequisite to return to operation. Any testing required to be performed during a refueling outage shall be completed prior to

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

Retest and corrective actions shall be performed at the first available opportunity. Deferred Test Justifications are numbered in a "WWW-XX-YY-t#f' format where: WWW= Cold Shutdown Justification (CSJ) Refueling Outage Justification (ROJ) XX = Catawba Nuclear Station (CN) YY = System Acronym

           ##       = Unique sequential number; e.g., CSJ-CN-Nl-2 would be the second cold shutdown justification valves in the Safety Injection (NI) System

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1.8.1 Testing Deferral Justifications:

Purpose:

The purpose of the testing Justification for Deferral form is to document the reason that a pump or valve can only be tested at cold shutdown or at refueling outage. Valid reasons could be plant configuration for testing which would jeopardize the safety of plant operation, access to the component which would be against ALARA, access to the component due to the environmental conditions endangering personnel safety, or that plant configuration for testing would require the plant to be in a mode not suitable for power production, or testing renders systems inoperable for extended periods of time. It is not the intent of IST to cause unwarranted plant shutdowns or to unnecessarily challenge other safety systems. Note: The Justification of Deferral Form is found in Enclosure 10.3. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 24 of 60 7/21/2016

1.9 APPENDICES
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Appendix A: IST PROGRAM Responsibilities 1.0 Site IST Engineer: The IST Engineer position will be filled by a qualified individual knowledgeable of plant system operation. He/she ensures the site is in compliance by its performance testing and trending methods. The IST Engineer will accomplish this by maintaining consistency among the System Engineers and overall program management. The IST Engineer may publish an overall summary (as an annual summary), on the current status of the site performance monitoring of the valves and pumps tested under the requirements of the IST or 10CFR50, Appendix B Program. The IST Engineer will be responsible for:

notifying Regulatory Compliance of any changes to the Valve and Pump Testing Program described in this document, including changes to the data sheet information,
updating and maintaining the IST Database,
ensure all IST-TAC is accurate and not in conflict with other specified TAC, coordinating and implementing the program update and renewal per 10CFR50 every 10 years.

2.0 Corporate IST Coordinator: The Corporate IST Coordinator will be an individual responsible for overall corporate IST Program management. He/she ensures corporate strategies for the IST Program align with industry and regulatory standards. This individual is knowledgeable of each site's IST programs including program administration and will be responsible for ensuring each site is in compliance with the applicable ASME Codes and IST guidelines (ISTA, ISTB, ISTC, NRC Generic Letters, and NUREG-1482, etc.). The Corporate IST Coordinator is the technical consultant on any Code-related issues that require interpretation or involve Operability determinations (at the discretion of the IST Engineer and site management). The Corporate Coordinator will provide support for internal and external IST Program audits. The Corporate IST Coordinator will be the Single Point of Contact on any issues that involve site-site interaction and will be responsible for ensuring consistency where practical. The Corporate IST Coordinator will represent Duke Power's interest for Code development. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 26 of 60 7/21/2016

Appendix A: IST PROGRAM Responsibilities (Continued)

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

The Corporate IST Coordinator will see that progress addressing technical issues will be made by the IST Working Group (ISTWG). This includes defining appropriate tasks, tracking action items, conducting periodic meetings, interface with the appropriate BEST contacts, and maintaining overall group focus. 3.0 Site Engineering-i Site Engineering is responsible for the c9mponents within their systems which are in the program. If the status of a component changes, Site Engineering is responsible for initiating the required changes to the program (see Appendix C). Site Engineering is responsible for the following:

ensuring the accuracy of IST dataset information,
defining test acceptance criteria (TAC),
ensuring Code testing requirements are met,
documenting reasons for scope or Code deviation,
providing technical assistance for developing test procedures,
notifying the IST Engineer of maintenance that could affect the baseline data for any IST component,
overall administration of the relief valve testing program (Appendix I),
administrating the Check Valve Condition Monitoring program,
provide input when evaluating specific component issues (why failed test, baseline changed, etc.).

4.0 Operations Performance Test Group (OTG) and Operations Shift (OPS): This group is responsible for the following:

input data into procedure and IST database,
performing tests,
accurately recording and notifying Site Engineering of any testing problems,
initiating a Condition Report when a test is failed or a problem is encountered,
documenting test discrepancies on the procedure.

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

updating and maintaining all IST procedures,
verifying all technical changes with the IST Engineer .
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                                     *Appendix B:

10CFR50, Appendix B, Augmented Program Guidance Document

1.0 Scope

The Appendix B Program establishes the requirements for test programs that monitor plant structures, systems, and components. The Appendix B Program assures testing shall be performed in accordance with approved written test procedures that incorporate the requirements and acceptance limits contained in applicable design documents. This program shall include the following:

Periodic tests during plant operation of structures, systems, and components
Trending of test parameters at owner specified frequencies Test procedures shall include provisions for assuring that all perquisites and acceptance criteria for the given test have been met. In addition, adequate test instrumentation shall be used and testing performed under suitable environmental conditions (as per 10CFR50, App. B).

Deviations from "guidelines" will be documented in 6.0, "Appendix. B Program Positions/Exceptions". NOTE: CNS historically included "App. B Component" within the station's "Supplemental Testing Program". For CNS 4th 10yr Interval, this reference was changed to the "Augmented Testing Program". 2.0 Pump and Valve Test Selection Criteria: The pumps and valves in this program shall be limited to those pumps an.d valves not covered in the scope of the ASME OM Code.

pumps and valves not included in the IST Program, which are active in certain non-Design Basis Events,
are cold shutdown valves not associated with a UFSAR Chapter 15 event,
are significant to plant safety,
or are of economic importance.

3.0 Program Elements: Pump and Valve Selection - This task involves identifying all components that fall within the scope of 10CFR50, Appendix B scope. Testing Support - Develop acceptance criteria, necessary test procedures, and establish the correct frequencies for performing operational tests. Demonstrate Operability - Perform baseline testing (if applicable) of components to ensure functionality o~ the component and to obtain data for future surveillance activities . CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 28 of 60 7/21/2016

Appendix B: 10CFR50, Appendix B, Supplemental Program Guidance Document (continued)

Documentation and Trending -
Establish documentation and trending system for all Appendix B components,
Establish monitoring system for periodic surveillance testing and performance parameters,
Establish feedback mechanism to ensure that results and failures influence the frequency and extent of future testing.

4.0 Program Organization and Responsibilities: Corporate IST Coordinator - This is the individual responsible for the following:

General direction for program elements,
Program oversight and liaison,
Assistance in site program implementation,
Industry, regulatory, and corporate interface,
Assist stations in resolving generic issues,
Provide lead, coordinate and/or interface with other groups to ensure consistent implementation.

Site !ST/Engineering Contact- This is the site engineering support responsible for the following:

Pump and valve selection,
Categorizing for analysis and testing,
Resolution of Operability concerns,
Station modifications which affect components in the Appendix B program,
Operability testing of components,
Maintaining Appendix B engineering documents in an auditable format,
Maintain working procedures, guidelines, and other documents,
Final review and trending of component test data and acceptance criteria,
Implement test program changes in response to any corporate and industry direction.

5.0 Definitions active: valves that are required to change obturator position to accomplish a specific function in shutting down a reactor to the safe shutdown condition, maintaining the safe shutdown condition, or mitigating the consequences of an accident.

passive: valves that maintain obturator position and are not required to change obturator position to accomplish the required function(s) in shutting down a reactor to the safe shutdown condition, maintaining the safe shutdown condition, or mitigating the consequences of an accident.

safety-related: required to mitigate the consequences of an accident, shutdown, or maintain shutdown of the reactor.

component: an item in nuclear power plant such as a vessel, pump, valve, or piping system.

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Appendix B: 10CFR50, Appendix B, Supplemental Program Guidance Document (continued) cold shutdovvn; (see plant Technical Specifications) engineering evaluation: an evaluation of indications that exceed allowable acceptance standards to determine if the margins required by the design specifications and construction code are maintained. exercising (of a valve): the demonstration based on direct or indirect visual or other positive indication that the moving parts function satisfactorily. full stroke time: that time interval from initiation of the actuation signal to the end of the actuation cycle. test: a procedure to obtain information (through measurement or observation) to determine the operational readiness of a component or system while under controlled conditions. hot standby: (see plant Technical Specifications) operational readiness: the ability of a component or system to perform its intended function when required. ovvner: the organization owning or operating a facility where items are installed or used. normal plant operation conditions: the operating conditions during reactor startup,

operation at power, hot standby, and reactor shutdown conditions, as defined by plant technical specifications.

obturator: valve closure member (disk, gate, plug, ball, etc.). reference values: one or more values of test parameters measured or determined when the equipment is known to be operating correctly. 6.0 Appendix B Program Positions/Exceptions 6.1 The CNS 10CFR50, Appendix B Program may be administered using the ASME IST Code as guidance for testing and trending. 6.2 Relief Requests and Justification for Deferrals will not be submitted for Appendix B components. 6.3 Per Catawba's GL 89-04 response, 10 CFR50 Appendix B manual valves are only stroked during a refueling outage. (Ref: NUREG-1482, Section 4.4.3). 6.4 Deviations from standard test practices will be allowed only if substantiated in writing per the methods outlined in approved site directives and procedures . CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 30 of 60 7/21/2016

AppendixC: Notification of Program Changes

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

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

Changing the active/passive status of a component,
Changing the leakage requirements of the component,
Changing the piping classification of the component (Duke Class and ISi Class),
Something changes with how the component may be tested,
A commitment is made or changed for testing or operation of a component,
Taking credit for a new function, flow path, etc.,
A modification to the component is planned which can/will significantly affect the components baseline Test Acceptance Criteria (TAC),
A modification to a plant system that may add or delete a component.
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1.10 ENCLOSURES CNS ASME In-service Testing Program Rev. 08 Page 32 of 60 CNSSCOPE.DOC 7/21/2016

Enclosure 10.1-REVISING THE PROGRAM

1. Process for Revising the IST Program Plant Engineering Procedure No. 3.14, "Control of Tech Spec Required Program Documents Assigned to MCE Engineering", defines the process to be followed when changes to the IST Program should be made, how changes to the IST Program are made, and when changes should be forwarded for NRC review.

2. Inclusion of Flow Diagrams (reference NUREG-1482, Section 2.4.3)

The staff recommends that flow diagrams be included in the program submittal to assist in finding the pumps and valves included in the program. This information will assist the staff in reviewing relief requests or proposed alternatives. A partial submittal of the program containing relief requests should include applicable drawings to support the relief requests or to supersede previous IST flow diagrams. IST flow diagrams need not be updated regularly, but if drawings change because of modifications, or if relief requests are affected, the staff recommends drawings be revised and submitted to the NRC in the next periodic submittal of revisions to the IST Program. The staff also recommends licensees include applicable drawings with relief requests that are very detailed and are submitted to supplement the IST Program .

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Enclosure 10.2 Catawba Units 1and2. Relief Request Template Request Number: ASME Code Component(s) Affected:

Applicable Code Edition and Addenda

Applicable Code Requirement:

Reason for Request

Proposed Alternative and Basis for Use: Duration of Proposed Alternative: Precedents (Optional): References (Optional): Note: There are a number templates available. Template selection should be based on the reason for the request. See NUREG 1482 for additional information and formats.

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Enclosure 10.3 Catawba Units 1 and 2

Justification for Deferral NOTE: This format is applicable to both Cold Shutdown (CSJ) and Refueling Outage (ROJ)

Justifications. Item Number: Component Number (s): Flow Diagram (s): Code Category: ASME Class: Function (s): Test Requirement: Basis for Deferral:

Test Alternative & Frequency:
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Enclosure 10.4 Duke System Aping Classification (1) Safety Re.lated NRC Quality Group System Piping Classification Correlation Duke QA Condition ANSI Safety aass Code Des. Criteria (6) Seisnic Pressure Boundary Integrity Seisnic Category Norrrally Contains Radioactive Material A YES A Class 1, ASlllE Sect. Ill YES SC-I YES B YES B 2 Class 2, ASlllE Sect. Ill YES SC-I YES c YES c 3 Class 3, ASlllE Sect. Ill YES SC-I YES E 1\1() 0(3) 2(4) NNS(2) ANSIB31.1.0 1\1() NIA YES F 1\1() D 4 NNS(2) ANSI 831.1.0 YES SC-IF) 1\1() G 1\1() -(4) ANSI 831.1.0 1\1() NIA 1\1() H 1\1() -(4) Duke A:>w er Spec. 1\1() NIA l\IO. H(HVAC) YES -(6) Duke A:lw er Spec YES SC-I 1\1() NOTES: ( 1) Safety Related as used herein is in accordance with 10CFR50 Appendix A General Design Criteria for Nuclear A:>w er Rants and is applicable to function only; i.e., structures, systems, and corrponents required to function such that the

facility can be operated without undue risk to the health and safety of the public are safety related.

(2) NNS = Non-Nuclear Safety (3) aass E piping is equivalent to NRC Quality Group D; i.e., the system is designed to norrrally carry a radioactive fluid; how ever, is considered NNS as a corrponent failure would not result in a calculated potential exposure in excess of the linits established by 10 CFR PART 20. (4) Class E, G, and H piping systems rray also be assigned QA Condition 3 and/or 4 to denote additional requirerrents for fire protection of safety related corrponents and/ or seisnic structural integrity (except pressure boundary) to preclude adverse interactions with safety related structures, systems and corrponents, respectively; refer to Duke Nuclear Guide 1.29. (5) Code and Standards Applicability: Duke 81ergy establishes an "effective Code date" in accordance with 10CFRSO, par. 50.55a for Catawba Nuclear Station. Due to the nurrerous Codes and Standards references applicable to each station, no atterrpt is rrade to specifically identify these references as they are arrended, superseded, or substituted. Duke 81ergy reviews and corrplies with all or portions of the latest versions of the above Codes and Standards unless rraterials and/ or design cormitrrents have progressed to a stage that it is not practical to rrake a change. \Mien only portions of addenda to Codes and Standards are utilized, the appropriate engineering review of the entire agenda assures that the overall intent of the Code Standard is still rraintained. (6) HVAC Duct Systems rray be constructed of either sheet rretal or piping rraterials depending upon the design function and requirerrents. Non-Safety Related HVAC rray be assigned QA Condition 4, SC-II Support Restraints to preclude adverse interactions with safety related structures, systems, and corrponents. Refer to Duke Nuclear Guide 1.29. (7) aass F for piping systems is used when pressure boundary protection is required. Seisnic Category II hangers rray be use on Class E, G, or H piping systems when pressure boundary integrity is not required. See Duke Guide 1.29. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 36 of 60 7/21/2016

Enic:Josure 1 0.5 1 VALVE SlROKE 'TIME DA TA EVALUATIO:N IFLOW CHART OECLl1RE THE VM\t"E V.lt!..V.E *BTR03<:lE \'\'rrJ-llN! r'- - - t ' ! f INOPERABLE & REFERENO: RANGE I ooou1*.rENT IN TBAIL

                 .<oNALYZE                                     DECL.'IJRE TI-IE a.TROKE TIME &

o=ur.tENT NO INO~':illLE .s. .'IND RESUL7S OO!lUM'ENT IN TBAIL

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Enclosure 10.6

Subject:

CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING NC PORV Stroke Requirement Position Statement NC PORV Testing

Purpose:

The purpose of this letter is clarify testing requirements for the NC PO RVS Position Statement: The NC PORVs (NC32B, NC34A, and NC36B) are considered cold shutdown valves (TS 5.5.8). These valves are required to be full-stroke exercised, stroke timed in both the closed-to-open and open-to-closed direction "each"time the plant enters cold shutdown, but not more frequently than once every 92 days. This requirement to exercise CANNOT be deferred to a subsequent entry into cold shutdown, which is a practice that may be applied to other valves identified for cold shutdown testing. This exercise test should be an air stroke (tests all 3 PORVs), or a combination of air and nitrogen (air to NC36B and nitrogen to the others) to ensure all three valves are exercised. This exercise test may be performed using manual controls located within the main control room; however. at least once every 18 months. this exercise test should be performed using a jumper to simulate AUTO actuation of the PO RVs. This PORV full-stroke exercise, stroke time test can be performed prior to the entry into cold shutdown; thereby, a single PORV exercise could met the requirements of the (1) cold shutdown test, (2) LTOP entry test, and (3) hot stroke test. The NC PO RVs NC32B & NC34A are required to be full-stroke exercised, stroke timed in all cases prior

to entering LTOP conditions, except not more frequently than once every 92 days (References 2 - 4).

This can be an air or nitrogen stroke for the LTOP valves. This exercise test may be performed using manual controls located within the main control room. This LTOP PORV exercise test can satisfy the requirements of the ( 1) cold shutdown test, (2) LTOP entry test, and (3) hot stroke test. The NC PZR PORVs (NC32B, NC34A, NC36B) are required to be full stroke exercised a complete cycle once every 18 months with NC system cold legs > 200°F (TS SR 3.4.11.2). This PORV exercise is performed using manual controls located within the main control room and does not required stroke timing. This "hot stroke" can be accomplished with the air stroke if performed prior to entering LTOP and the temperature conditions are satisfied. A nitrogen stroke must be performed every 18 months for NC32B and NC34A. This can satisfy the cold shutdown stroke and the LTOP stroke (if performed prior to LTOP) for the applicable PORVs. (TS SR 3.4.11.3) The NC PORVs (NC32B, NC34A, NC36B) actuators are equipped with springs to assist valve closure; however, there are no situations where this actuator spring function is required to act alone to close these valves during a postulated design basis accident (Reference 7). To ensure equipment reliability, a freedom-of-movement exercise from full-open to full-closed under spring force alone within a reasonable time (60 seconds) will be performed once every 18 months. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 38 of 60 7/21/2016

Enclosure 10.6 (continued)

CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING NC PORV Stroke Requirement Position Statement If maintenance is performed, a post-maintenance stroke is required. This post~maintenance exercise should be air and nitrogen if NC32B or NC34A had maintenance, or air only for NC36B. In addition, a freedom-of-movement exercise from full-open to full-closed under spring force alone within a reasonable time (60 seconds) will be performed (ref. IP/*/A/3121/022).

References:

(1) NRC SER Letter, Subject "Transmittal of Safety Evaluation R~port and Technical Evaluation Report Regarding Pump and Valve lnservice Testing Program - Catawba Nuclear Station Unit 1 and 2, January 8, 1987 (2) NRC GL 90-06, Subject " Resolution of Generic Issue 70, Power-Operated Relief Valve and Block Valve Reliability, and Generic Issue 94, Additional Low-temperature Overpressure Protection for Light-Water Reactors, Pursuant to 10CFR10.54(f)", June 25, 1990 (3) Catawba Response to NRC GL 90-06, wl NRC RAls, December 20, 1990, May 9, 1991, and February 6, 1992. (4) NRC SER Letter, Subject" Issuance of Amendment No. 95 to Facility Operating License NPF;-35 and Amendment No. 89 to Facility Operating License NPF Catawba Nuclear Station, Units 1 and 2, April 14, 1992 (5) NUREG-1482, Guideline for lnservice Testing at Nuclear Power Plants, Revision 1, Published:

January 2005 (6) ASME Code for Operation and Maintenance of Nuclear Power Plants, 2004 Addition through 2006 Addenda (7) CNC-1513.07-00-0001, Safety Evaluation of Interim Revision of PT/1/A/4200/032A to Change PORV Fail-Safe Closure, Revision 1
CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 39 of 60 7/21/2016

Enclosure 10.7

Subject:

CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING MSIV Stroke Requirement Position Statement Main Steam Isolation Valves (MSIVs)

Purpose:

The purpose of this letter is clarify testing requirements for the MS IVs Position Statement: The MSIV (SM1, SM3, and SM5 SM?) are considered cold shutdown valves (TS 5.5.8). These valves are required to be full-stroke exercised, stroke timed, and fail-safe actuated in the open-to-closed direction during startup after the plant enters cold shutdown. During startup and prior to entering Mode of Applicability (TS 3.7.2 LCO), MSIV full stroke exercise, stroke time test (i.e., air assist closure, not fail-safe) shall include separate actuation of the independent safety train solenoids (Train A/B). MSIV Train A actuation may be performed using manual controls located within the main control room. MSIV Train B actuation may be performed using a jumper to simulate AUTO actuation (NOTE: MSIV Train B safety solenoid does not have manual controls within the control room). These MSIV exercise tests at COLD conditions ensures valve operational readiness including actuation of the independent safety train solenoid (OM Code, ISTA-2000, Skid-mounted Pumps and Valves). This MSIV "COLD" full stroke exercise, stroke time test shall be included within the list of tests to be performed during unplanned entry into the cold shutdown condition; as such, this MSIV * "COLD" exercise test may be deferred to subsequent entries into cold shutdown based on the shutdown duration and the priority of cold shutdown valve testing. During startup prior to entering Mode 2 (TS SR 3.7.2.1 ), MSIV full stroke exercise, stroke time, and fail-safe actuation is required. This MSIV exercise test at HOT conditions ensures the MSIV is capable of responding with spring force alone (fail-safe) in the open-to-closed direction within the response time limit specified in the safety analysis. This MSIV exercise test may be performed using manual controls located within the main control room with actuation of the Train A safety solenoid (NOTE: MSIV Train B safety solenoid does not have manual controls within the control room). This MSIV "HOT" full stroke exercise, stroke time, fail safe actuation test shall be performed during startup after "each" time the plant enters the cold shutdown condition, but not more frequently than once every 92 days. This MSIV "HOT" (Train A) exercise test should not be deferred to a subsequent entry into cold shutdown, which is a practice that may be applied to the MSIV "COLD" exercise and other valves identified for cold shutdown testing. This "each cold shutdown" exercise is justified based on the limited margin for MSIV fail-safe actuation and to ensure equipment reliability. In certain situations (i.e., an extended forced cold shutdown condition OR a refueling outage with limited valve maintenance) where judgment has determined that shutdown activities had no impact on valve performance, the MSIV "COLD" exercise test may be deferred to the "HOT" condition. For these situations, the MSIV "HOT" exercise test shall include independent actuation of each safety train solenoid (Train A/B). The MSIV Train A full stroke exercise, stroke time, fail safe actuation test (i.e., spring force alone for closure) shall be performed using manual controls located within the main control room. The MSIV Train B full stroke exercise, stroke time test (i.e., air assist closure, not fail-safe) may be performed

using a jumper to simulate AUTO actuation.

CNS ASME In-service Testing Program Rev. 08 Page 40 of 60 CNSSCOPE.DOC 7/21/2016

Enclosure 10.7 (continued)

CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING MSIV Stroke Requirement Position Statement If maintenance is performed that potentially affects valve performance, the MSIV "COLD" (Train AJB) full stroke exercise, stroke time test shall be performed to ensure operational readiness prior to entering the Mode of Applicability (TS 3.7.2 LCO). Subsequently, the MSIV "HOT" (Train A) full stroke, stroke time, fail safe actuation test shall be performed to ensure the valve's response meets the response time limit specified in the safety analysis.

References:

(1) NRC SER Letter, Subject "Transmittal of Safety Evaluation Report and Technical Evaluation Report Regarding Pump and Valve lnservice Testing Program - Catawba Nuclear Station Unit 1 and 2", January 8, 1987 (2) NUREG-1431, Volume 2, Standard Technical Specifications - Westinghouse Plants: Bases, Revision 3, Published: June 2004 (3) NUREG-1482, Guideline for lnservice Testing at Nuclear Power Plants, Revision 1, Published: January 2005 (4) NRC IN 94-44, Main Steam Isolation Valve Failure To Close On Demand Because Of Inadequate Maintenance And Testing [McGuire], June 16, 1994 (5) ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code}, 2004 Addition through 2006 Addenda

(6) Various Industry Operation Experience (PIP C 10-1060)
CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 41 of 60 7/21/2016

Enclosure 10.8

Subject:

CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING SA-1&4 (Gate) AND SA-3&6 (Stop Check) Position Statement I Periodic lnservice Testing of SA-1 & SA-4 (Gate) and SA-3 & SA-6 (Stop Check) Valves

Purpose:

The purpose of this letter is to document Engineering's position for the inservice testing of manual valves SA-1 & SA-4 (Gate) and SA3 & SA-6 (Stop Check); which are installed in the steam supply line to Auxiliary Feedwater Pump Turbine. Position Statement: Valves SA-1 (Main Steam B to CAPT Maintenance Isolation) and SA-4 (Main Steam C to CAPT Maintenance Isolation) are manual gate valves located in the Interior Doghouse immediately downstream of the respective SM piping. SA-1 and SA-4 are currently listed in Catawba Technical Specification, as Containment Isolation Valves. The valves are locked open and capable of local manual operation only. These valves are required to be open to supply steam to the CAPT from the respective SM piping for Engineered Safety Features (ESF) operation of the CAPT.. However, CAPT operation can continue with one of these valves closed providing that steam is available from the opposite SM piping. Valves SA-3 (1 B S/G Main Steam to CAPT Stop Check) and SA-6 (1C SIG Main Steam to CAPT Stop Check) are stop check valves with manual handwheels located in the mechanical penetration room (ELE 543), downstream (CAPT side) of valves SA-1 and SA-4 respectively. SA-1 and SA-4 are within the

system piping boundary designated as ASME Class II (Duke Class B) and are capable of functioning an alternative means for establishing Containment Isolation. These valves are locked open and capable of local manual operation only. These valves are required to, be open to supply steam to the CAPT from the respective SM piping for Engineered Safety Features (ESF) operation of the CAPT. However, CAPT operation can continue with one of these valves closed providing that steam is available from the opposite SM piping.

The following two accident scenarios require the isolation of one steam supply to the CAPT due to current dose assessment limitations and CA System operation requirements:

1) Steam Generator Tube Rupture (SGTR)

And

2) Main Steam Line Break.

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 42 of 60 7/21/2016

Enclosure 10.8 (continued)

CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING SA-1&4 (Gate) AND SA-3&6 (Stop Check) Position Statement The dose calculations for Main Steam Line Break and SGTR scenarios assume limited release of main steam to the atmosphere. Operator action is taken as directed within current Emergency Operating Procedures (EP's) and/or Abnormal Operating Procedures (AP's) to manually close SA-3 and/or SA-6 as applicable in these scenarios. These valves may be used in the EP's and AP's as opposed to SA-1 and SA-4 due to more assured accessibility as discussed previously - SA-1 and SA-4 are located in the Interior Doghouse and would not be accessible in the event of a high energy line break (i.e. Main Steam Line Break) in this Doghouse. However, SA-1 and SA-4 are the closest isolation valves to containment.

If accessible, SA-1 and SA-4 can also be closed in a shorter time frame than SA-3 and SA-6. During a SGTR, the time required to manually close stop check valves SA-3 and SA-6 may increase due to "dress-out" requirements and increased radiation monitoring prior to entering the area due to contamination and increased dose in the mechanical penetration room. Therefore, if accessible, closing SA-1 and SA-4 would be preferable over SA-3 and SA-6. In each of these accident scenarios, the time required for an Operator to close the applicable valve has been estimated and factored into the Accident Analyses and resultant dose calculations. Calculated off-site doses are within allowable values for these scenarios. For the SGTR scenario, failure to isolate steam to the CAPT from the SIG with the tube rupture would

allow indefinite release of main steam to the atmosphere via the CAPT exhaust, which would consequently exceed the current dose calculations. Assuming no high energy line break in the Interior Doghouse during a SGTR accident, closing SA-1 and SA-4 would be preferable over SA-3 and SA-6.

For the Main Steam Line Break scenario, SA-3 or SA-6 (depending on the break scenario) would automatically close (stop check valves) to prevent the diversion of steam from an intact steam line to the faulted piping and then to the atmosphere or into containment (depending on the location of the break) effectively depressurizing a second SIG, rendering the CAPT inoperable due to the loss of all steam supply, and also affecting the operation I flow balance of the Motor Driven CA pumps. The applicable SA line is isolated as a precaution in case of the check valve fails to close and isolate the faulted steam line. Unless the steam line break is located in the Interior Doghouse, closing SA-1 and SA-4 would be preferable over SA-3 and SA-6.

Conclusion:

Based on the scenario, operator response procedures (EP and AP) may provide direction to manually close any one of the four manual valves located in the steam supply line to the auxiliary feedwater pump turbine. Therefore, all four of these manual valves are considered within the scope of periodic inservice testing. SA-1 and SA-4 are gate valves with a manual handwheel that is maintained in the lock open position during normal plant operation. These gate valves are included within the scope of periodic inservice testing in accordance with para. ISTC-3540. Manual Valve, of the ASME OM Code. SA-3 and SA-6 are stop check valves with a manual handwheel that is maintained in the lock open position during normal plant operation. These stop check valves are included within the scope of periodic inservice testing in accordance with para. ISTC-3540, Manual Valve, and Appendix 11, Check Valve Condition Monitoring Program, of the ASME OM Code . CNS ASME In-service Testing Program Rev. 08 Page 43 of 60 CNSSCOPE.DOC 7/21/2016

Enclosure 10.8 (continued)

References:

CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING SA-1&4 (Gate) AND SA-3&6 (Stop Check) Position Statement * (1) PIP 1-C-90-0008, Expansion of Containment Penetration Boundaries to SA-3 and SA-6 (2) CNS Containment Integrity Review, lnterstation Letter, Dated: January 15, 1996, File No.: CN-208.32 (3) NRC SER Letter, Subject - CNS - Issuance of Exemption to 10CFR Part 50, Appendix A, General Design Criteria 57 (TAC NOS. M99561 and M99562), Dated: December 29, 1998 CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 44 of 60 7/21/2016

Enclosure 10.9

Subject:

CATAWBA NUCLEAR STATION PROGRAMS ENGINEERING Containment Penetration Check Valve Position Statement Periodic Testing of Containment Penetration Check Valves in accordance with ASME OM Code Appendix II, Check Valve Condition Monitoring, and 10CFR50 Appendix-J, Primary Reactor Containment Leakage Testing.

Purpose:

This technical position defines Catawba's practice for establishing and implementing periodic testing of check valves that function as containment isolation valves in meeting the requirements of ASME OM Code Mandatory Appendix II, Check Valve Conditioning Monitoring, and 10CFR50 Appendix-J, Primary Reactor Containment Leakage Testing. Applicability Catawba's Check Valve lnservice Testing Program has been developed in accordance with the ASME OM Code, 2004 Edition through 2006 Addenda, Mandatory Appendix II, Check Valve Condition Monitoring. As modified by 10CFR50.55a(b)(3)(iv), this program shall include the following testing requirements and frequencies. Valve opening and closing functions must be demonstrated when flow testing or examination methods (non-intrusive, or disassembly and inspection) are used.

If sufficient information is not available to support optimization of condition monitoring, the initial interval of tests and associated examinations may not exceed two fuel cycles or 3 years, whichever is longer.

If sufficient information is available to support optimization of condition monitoring, extension of the initial interval of tests and associated examinations may not exceed one fuel cycle per extension with the maximum interval not to exceed 10 years.

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

Catawba's Containment Leak Rate Test Program has been developed in accordance with 10CFR50 Appendix-J, Regulatory Guide 1-163, and NEI 94-01.

Acceptable performance is demonstrated by a measured leak rate less than the predetermined administrative limit, which is assigned to each valve to provide an indication of potential degradation.

The initial interval for tests shall be performed at a frequency of at least once per 30 months (one fuel cycle), until completion of initial tests and adequate performance has been demonstrated .

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 45 of 60.

7/21/2016

Enclosure 10.9 CATAWBA NUCLEAR STATION PROGRAMS ENGINEERING Containment Penetration Check Valve Position Statement The initial interval of tests may be increased based upon completion of two consecutive periodic as-found Type-C tests where the result of each test is within the allowable administrative Umit. After two successful consecutive periodic as-found leak rate tests, the test interval may be extended to 60 months or three fuel cycles (ref.: Regulatory Guide 1-163, Position 2). Position Statement: When jointly applied, 10CFR 50 Appendix-J requires an additional test over an initial period of two fuel cycles, and is considered the more conservative test requirement. Specifically, by limiting the initial interval of testing to not exceed 30 months, 10CFR50 Appendix-J requires leak rate testing of check valve during two consecutive refueling outages prior to extending the test interval to once every 3 refueling outages (i.e., 60 months). In contrast, ASME Check Valve Condition Monitoring specifies an initial interval with at least one test in two fuel cycles or 3 years, whichever is longer. Basically, 10CFR50 Appendix-J requires two tests when ASME Check Valve Condition Monitoring requires only one test during the specified initial period of two fuel cycles. To comply with the. parallel requirements of ASME Check Valve Conditioning Monitoring and 10CFR50 Appendix-J, Catawba will apply the more conservation periodic testing requirements and frequency.

Whenever test results for an individual component will support extended interval testing, Catawba will extend the periodic test interval for subsequent refueling outages in accordance with the frequency specified within 10CRF50 Appendix-J (1st, 2nd, 5th, 8th, etc.). Whenever it is determined that test results for an individual component does not support extended interval testing, Catawba will remove that component's periodic test from extended interval until the condition that caused to poor performance is evaluated and appropriate corrective action is taken. Once the condition causing the poor performance is corrected and subsequent periodic testing shows acceptable performance, the periodic test for the individual component may be returned to extended interval of testing.*

For ASME Check Valve Condition Monitoring (CKCM) and 10CFR50 Appendix-J (AppJ), the table below compares the periodic frequency of extended interval testing whenever a component test results are determined acceptable. Also shown in the table, Catawba will apply the more conservative requirement and extend a component interval of periodic testing consistent with the requirements of 10CFR50 Appendix-J. Refueling 1st 2nd 3rd 4th 5th 6th 7th 8th 9th AppJ Test Test Test Test CKCM Test Test Test Catawba Test Test Test Test CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 46 of 60 7/21/2016

Enclosure 10.9 (continued)

CATAWBA NUCLEAR STATION PROGRAMS ENGINEERING Containment Penetration Check Valve Position Statement Industry Support of Position At Millstone, 10CFR50 Appendix-J and ASME Check Valve Conditioning Monitoring periodic testing are considered to be identical testing requirements. When 10CFR50 Appendix-J requires a change in frequency (initial interval testing due to unacceptable leakage or extended interval testing due to good performance), then component periodic testing is adjusted to credit testing at the appropriate 10CFR50 Appendix-J frequency. The ASME Check Valve Condition Monitoring Program specifies that the component's periodic test frequency is determined by 10CFR50 Appendix-J.

Summary: For check valves that function as containment isolation valve, 10CFR50 Appendix-J specifies the more conservative periodic testing requirements and frequency. Therefore, for these certain check valves and groups of check valves, Catawba will implement the testing requirement and frequency of 10CFR50 Appendix-J in lieu of the requirement of ASME Check Valve Conditioning Monitoring (i.e., Check Valve Condition Monitoring will credit completion of test at the frequency specified by the 10CFR50 Appendix-J Program).

References:

(1) ASME OM Code, 2004 Edition through 2006 Addenda, Mandatory Appendix II, Check Valve Condition Monitoring (2) 10CFR50 Appendix-J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors (3) NRC Regulatory Guide 1.163 (1995), Performance-Based Containment Leak-Test Program (4) NEI 94-01, Revision 0, Industry Guideline for Implementing Performance Based Option of 10CFR50 Appendix J (5) (FILE: CN-122.12, CN-257.46) EMAIL:

Subject:

Coordinating Appendix J and Condition Monitoring CVCM Position Paper.pdf, from Thomas R. Ickes, IST Engineer, Millstone Power Station, Dated: Monday, December 05, 2011 8:17 AM

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 47 of60 7/21/2016

Enclosure 10.10 CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING Priority for Cold Shutdown Valve Testing During Unplanned Entry into Mode 5 The following table provides guidance relative to the order in which cold shutdown testing should occur. The order, or priority, is based on possible system conditions during Mode 5, placing of jumpers and sliding of links, etc. Valves should be tested in the order listed (if possible) so that the valves tested in the unit's preceding cold shutdown will be the last ones tested during the unit's next cold shutdown. Should a valve be unavailable for testing and subsequently passed over during any given forced entry into Mode 5, that valve should be one of the first tested during the unit's cold shutdown outage. Following a refueling outage, the testing sequence re-starts at item one. Valve Valve Valve Valve 1 1(2)NC0032B 26 1(2)ND0001 B 51 1(2)NV0188A 76 1(2)NV0089A 2 1(2)NC0034A 27 1(2)ND0002A 52 1(2)NV0189B 77 1(2)NV0091 B 3 1(2)NC0036B 28 1(2)ND0036B 53 1(2)NV0202B 78 1(2)KC0338B 4 1(2)NI01 OOB 29 1(2)ND0037 A 54 1(2)NV0203A 79 1(2)KC0424B 5 1(2)NI0103A 30 1(2)NI0173A 55 1(2)NV0312A 80 1(2)KC0425A 6 1(2)NI0144A 31 1(2)NI0178B 56 1(2)NV0314B 81 1(2)RN0437B 7 1(2)NI0147B 32 1(2)NV0252A 57 1(2)NV0010A 82 1(2)RN0484A 8 1(2)NI0162A 33 1(2)NV0253B 58 1(2)NV0011A 83 1(2)RN0487B 9 1(2)NI0121 A 34 1(2)SM0001 59 1(2)NV0013A 84 1(2)RF0389B 10 1(2)NI0152B 35 1(2)SM0003 60 1(2)V10077B 85 1(2)RF0447B 11 1(2)NI0332A 36 1(2)SM0005 61 -- 86 1(2)BB008A 12 1(2)NI0333B 37 1(2)SM0007 62 -- 87 1(2)BB001 OB 13 1(2)NI0334B 38 2CA0149 63 -- 88 1(2)BB0019A 14 1(2)KC0320A 39 2CA0150 64 1(2)NI0009A 89 1(2)BB0021B 15 1(2)KC0332B 40 2CA0151 65 1(2)NI001 OB 90 1(2)BB0056A 16 1(2)KC0333A 41 2CA0152 66 1(2)NI0184B 91 1(2)BB0057B 17 1(2)NC0250A 42 1(2)CF0033 67 1(2)NI0185A 92 1(2)BB0060B 18 1(2)NC0251 B 43 1(2)CF0042 68 1(2)CF0028 93 1(2)BB0061B 19 1(2)NC0252B 44 1(2)CF0051 69 1(2)CF0030 20 1(2)NC0253A 45 1(2)CF0060 70 1(2)CF0037 21 1(2)NV0015B 46 1(2)NS0038B 71 1(2)CF0039 22 1(2)NV001A 47 1(2)NS0043A 72 1(2)CF0046 23 1(2)NV002A 48 1(2)ND0028A 73 1(2)CF0048 24 1(2)ND0032A 49 1(2)NI0136B 74 1(2)CF0055 25 1(2)ND0065B 50 1(2)NI0183B 75 1(2)CF0057 CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 48 of 60 7/21/2016

Enclosure 10.10 (continued)

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

(1) Valves 1(2)KC0338B, 1(2)KC0424B, 1(2)KC0425A, 1(2)RN0437B, 1(2)RN0484A, 1(2)RN0487B, 1(2)NV0089A and 1(2)NV0091 B are considered Cold Shutdown valves. However, exercising these valves while the reactor coolant pumps are in operation could result in pump damage. OM ISTC-3521 allows the test interval for these valves to be extended to refueling outages when the tests cannot be practically performed during power operations or cold shutdown outages (reference NUREG 1482, section 3.1.1.4). (2) The PZR PO RVs (1 (2)NC0032B, 1(2)NC0034A, 1(2)NC0036B) are considered Cold Shutdown and are stroked EACH time the Unit enters Cold Shutdown. See Enclosure 9.6 in the IST Program Document for further guidance for testing valves 1(2)NC0032B, 1(2)NC0034A, and 1(2)NC0036B. The MS IVs (1 (2)SM1, 1(2)SM3, 1(2)SM5, and 1(2) SM?) are considered Cold Shutdown Valves and are stroked during startup (Mode 3) following EACH time the Unit enters Cold Shutdown. See Enclosure 9.7 in the IST Program Document for further guidance for testing valves 1(2)SM1, 1(2)SM3, 1(2)SM5, and

1(2)SM7 .
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Enclosure 10.11 CATAWBA NUCLEAR STATION PROGRAMS ENGINEERING Position Indication Testing of Manual Actuated Pneumatic Valve Position Statement

Subject:

Position Indication Testing of Manual Actuated Pneumatic Valve (i.e. Position Indication on Instrument Panels in the Auxiliary Building)

Purpose:

This technical position is to establish the station position for exempting certain Manual Actuated Pneumatic Valve from the requirements of Position Indication Testing (ISTC-3700). These valve's position indication is provided on instrument panels in the general area of the auxiliary building conveniently located for safety. These valves are not required to perform a specific function as described in ISTA-1100 (Scope) and are used only for operating convenience such as vent, drain, instrument, and test activities (ISTC-1200 - Exemptions). Applicability This technical position is applicable to Manual Actuated Pneumatic Valve with Remote Position Indication on instrument panels in the general area of the auxiliary building conveniently located for safety (i.e. Electrical Reach Rods). This does NOT apply to the valve position indication on the Auxiliary Shutdown Panels or the Control Room Main Control Board.

Position Statement:

The ASME OM Code 2004 Edition through 2006 Addenda section ISTA-1100 identifies that the requirement for preservice and inservice testing is applied to "pumps and valves that are required to perform a specific safety function in (i) shutting down the reactor to the safe shutdown condition, (ii) maintaining the reactor in the safe shutdown condition, or (iii) mitigating the consequences of an accident". The ASME OM Code 2004 Edition through 2006 Addenda section ISTC-1200 further states:

  "The following are excluded from this Subsection, provided that the valves are not required to perform a specific function as described in ISTA-1100:

a) valves used only for operating convenience such as vent, drain, instrument, test valves b) valves used only for system control, such as pressure regulating valves c) valves used only for system and component maintenance". CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 50 of 60 7/21/2016

Enclosure 10.11 (continued)

CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING Position Indication Tests of Manual Actuated Pneumatic Valve Position Statement Manual Pneumatic Actuators are installed on certain valves at branch connections on various piping system which are designated nuclear safety related (ASME Class 2 and 3). These manual pneumatic actuators function as electrical reach rods; whereby, valves located in potentially unsafe work areas or highly radioactive areas can be remotely actuated. For these valves, a manual pneumatic solenoid and the valve position indication are located remotely (outside the room) on an instrument panel in the general area of the auxiliary building. These manual pneumatic actuators are a plant design feature that reduces unsafe conditions and radiation exposure (ALARA) to plant personnel whenever these valves need to be operated.

These manual pneumatic actuated valves function as the safety class (Nuclear Safety to Non-Nuclear Safety) pressure boundary for these systems and are maintained in the closed position during normal plant operation. These branch connections include piping connections to other system, which may. include the Reactor Makeup Water (NB) System, Floor Drain Header (WL) System, and Nuclear Sampling (NM) System. Each of these connected systems are routinely monitored for increased fluid radiation level that would be an indication of intersystem leakage. Should increase fluid radiation :levels be observed, these branch connections would be evaluated to identify the radioactive fluid leak source. This monitoring provides reasonable assurance that the pressure boundary between these connected

system is functionaliy intact with minimal, if any, radioactive fluid leak by .

During normal system operation, these manual pneumatic actuated valves on these branch connections are normally mainlined in the closed position. These valves may be opened on some periodicity to support system operation. This operation may include system makeup, flush, drain, slough, and sample activities. As such, the valves provide a support function (operating convenience) that maintain the system's operating condition, but does not perform a function required for normal system operation. Therefore, these valves may be exempt from the requirements of inservice testing per ISTC-1200 (a). These manual pneumatic actuated valves are maintained in the closed position during the postulated design basis accident (OBA). Beyond remaining closed to maintain a system pressure boundary, these valves do not required to perform a specific safety function in (i) shutting down the reactor to the safe shutdown condition, (ii) maintaining the reactor in the safe shutdown condition, or (iii) mitigating the consequences of an accident. Therefore, these valves are not required to perform a safety function as described in ISTA-1100 .

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Enclosure 10.11 (continued) CATAWBA NUCLEAR STATION MECHANICAL CIVIL ENGINEERING Position Indication Tests of Manual Actuated Pneumatic Valve Position Statement Section 4.2.8 of NUREG-1482 Revision 2 refers to the requirements for verifying position indication of passive valves. It states "the licensee is responsible for developing and implementing a method to verify that valve operation is accurately indicated as required by ISTC-3700. The extent of verification necessary for valve operation to satisfy ISTC-3700 will depend on the type of valve, the sophistication of the diagnostic equipment used in testing the valve, possible failure modes of the valve, and the operating history of the valve and similar valve types". It adds "The Code does not require licensees to verify the indication at the remote panels. However, verification at remote panels is a good practice and provides confidence in the remote indication". Based on the overall operation of these valves combined with their overall safety function and their applicability to ISTA-1100, it is concluded that these valves are not subject to the requirements of ISTC-3700. Summary: Manual Actuated Pneumatic Valve (as described above) are not required to perform a specific function as described in ISTA-1100 (Scope), are used only for operating convenience as described in ISTC-1200 (Exemptions) and are exempt from the requirements of inservice testing. Likewise, these valve's remote position indication in remote locations of the general areas of the auxiliary 'building conveniently

located for safety (i.e. Electrical Reach Rods) are not subject to inservice testing as described in ISTC-3700 (Position Indication Testing).

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 52 of 60 7/21/2016

Enclosure 10.12

Subject:

CATAWBA NUCLEAR STATION PROGRAMS ENGINEERING SG PORV Stroke Requirement Position Statement Open Stroke Testing of Steam Generator Power-Operated Relief Valves

Purpose:

This technical position is to establish the station position for excluding the open stroke time tests of the Steam Generator Power-Operated Relief Valves (PORVs) from the requirements of PORVValve Stroke Testing (ISTC-5113). Applicability This technical position is applicable to the Catawba Nuclear Stations (CNS) Steam Generator (SG) Power-Operated Relief Valves (PORVs). The safety functions of.the SG PORV are to (Ref.: CNS-1593.SM-00-0001, Rev.36):

1. Contribute to mitigating the consequences of a Steam Generator Tube Rupture (SGTR) accident concurrent with Loss of Offsite Power (LOOP). During this event, the Control Room Operator is expected to determine that a SGTR has occurred and then initiate, within 5 minutes, natural circulation cooldown of the primary system.

Contribute to achieving an average RCS temperature of 350°F (ND system initiation) during design basis events that require a cooldown to cold shutdown conditions such as SGTR, rod ejection, or

SBLOCA.

In addition, the SG PORVs are to (non-safety functions):

1. Prevent lifting of the safety valves during mild pressure transients.

2. Assist reseating actuated safety valve(s).

3. Provide a means for plant cooldown when the steam dump system is not operable.

The SG PORVs are not required for overpressure protection. These valves receive a main steam isolation signal to remain closed to prevent uncontrolled steam flow from the steam generators to the environment in the event of a high energy line break in its Doghouse. The pressure boundary defined by the PORVs is Duke Class B. (Ref.: para. 3.1.1.5; CNS-1593.SM-00-0001, Rev.36) The PORVs can be actuated by either a pneumatic piston operator or local handwheel. The pneumatic operator has two modes of operation. One mode provides nonadjustable automatic pressure control. This mode of operation is nonsafety. The safety grade mode of operation is provided by depressing the "normal" pushbutton on the main control board and allowing valve modulation using a (safety related) potentiometer. The safety grade air supply (nitrogen) is provided by seismically mounted cylinders located in the doghouse. (Ref.: para. 3.1.1.5; CNS-1593.SM-00-0001, Rev.36)

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 53 of 60 7/21/2016

Enclosure 10.12 (continued) CATAWBA NUCLEAR STATION PROGRAMS ENGINEERING SG PORV Stroke Requirement Position Statement Position Statement: The ASME OM Code 2004 Edition through 2006 Addenda section ISTC-5110 identify the requirement for inservice testing of Power-Operated Relief Valves. Specific to these valves, ISTC-5113 further defines stroke time testing of active valves. Catawba's PO RVs are air-operated fail close valves. Design Basis Specification CNS-1593.SM-00-0001 specifies each PORVs ESF Position is closed with a maximum stroke time close of eight (8) seconds as listed in the Safety Analysis Inputs Manual. UFSAR 10.3.2 depicts a maximum stroke close time of 20 seconds or less after receiving ~closure signal. The SM PORV main control room controls are located on 1MC2. These controls perform both safety and nonsafety related functions. The safety related functions of the instrumentation and controls are to:

1. permit modulation of the PO RVs from the control room and,

2. to ensure closure of the valves upon receipt of a safety signal.

The nonsafety opening/closure of the SM PORVs in response to steam line pressure is accomplished via pressure switch inputs to non-safety solenoid valves located on instrument air supply lines to the PORV actuator. The safety related nitrogen bottle system is not connected to these solenoids in any manner. The SM PORV main control room controls consists of a potentiometer located on 1MC2. This is a safety related device that outputs an electrical signal to an electro-pneumatic converter and then on to the valve positioner. This is the safety related instrumentation that permits modulation of the SM PO RVs from the main control room. While operating from the main control room, SSPS output relay contacts have been wired to ensure that safety related solenoid valves are de-energized upon receipt of SSPS signal (i.e. failing the SG PORV to the CLOSED position). Upon receipt of this SSPS signal, the SM PORV response is closed with a maximum stroke time close of eight (8) seconds as listed in the Safety Analysis Inputs Manual. (iaw Steam Line Isolation Response Time; MNS & CNS Safety Analysis Inputs Manual, Rev. 6) The SM PORV nonsafety opening/closure feature along with the inherent design of the safety related potentiometer (turn knob) are the key elements that prevent routine open stroke timing of each SG PORV. Operation of each potentiometer by design results in a slow response (manual cycle to open position) of each SM PORV. This slow response prevents large swings in valve operation thereby allowing the operator to fine tune the position of the PORV during the postulated accident (DBA/SGTR, etc.). Once the SM PORV is manually cycled to the fully open position, the steam line isolation signal is simulated and the valve's stroke time response (open-to-close) is confirmed. CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 54 of 60 7/21/2016

Enclosure 10.12 (continued)

CATAWBA NUCLEAR STATION PROGRAMS ENGINEERING SG PORV Stroke Requirement Position Statement WESTINGHOUSE PORV REQUIREMENTS The SG PORVs shall be capable of modulating full stroke within 20 seconds over an inlet pressure range from the main steam system design pressure to 100 psia in order to adequately reduce steam pressure transients. This 20 second stroke time is for full close to full open. The full open to full close stroke should be consistent with the opening requirements to prevent overcooling of the NC system. This criteria applies to the non-safety related automatic function of the valve.

(Ref.: Section 4-1 of reference 2.5.2.2.1; CNS-1593.SM-00-0001, Rev.36) Catawba Technical Specifications 3.4.11 and 3.7.4 require each PORV to be manually cycled in accordance with the surveillance control program. These Technical Specifications along with the OM Code ISTC-3700 requirement for Position Verification Testing provide a proper verification of operational readiness. As part of the Position Verification Testing performance, any abnormal or erratic action (ISTC-5113(d) will be identified locally by the operator during the cycling of the valve to confirm accurate indication. Summary The SM PORVs perform both safety and nonsafety related functions. To ensure their operational

readiness, the SM PORV safety related functions will be confirmed by inservice tests that includes:

1. Stroke Time and Fail Safe Actuation from the full-open to the full-closed positions, and

2. Remote Manual (CR & Local) Full Stroke Exercising in the full-open and full-closed directions.

SM PORV main control room controls include a safety related potentiometer (turn knob) as the method for remote manual (CR) and full stroke exercising. Via its inherent design, these controls do not provide a consistent means for routine stroke timing from the full-closed to the full-open positions of each SG PORV. The SM PORVautomatic response (closed-to-open) is a non-credited safety function for system overpressure protection. Therefore, SM PORV stroke time testing in the closed-to-open direction is not a required inservice test.

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 55 of 60 7/21/2016

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Enclosure 10.13

Pump Group TABLE OF ABBREVIATIONS Pump and Valve Summary Tables Database

                                           *Standardization Group A                          A Group B                          B Augmented                        AUG Exempt                        Exempt Skid Mounted                      SKID Pump Code Class ASME Class 1                          1 ASME Class 2                         2 ASME Class 3                         3 Not Applicable                     NA Non Code                         NC Pump Type Centrifuaal Horizontal                  C-H Centrifuaal Vertical                   C-V Positive Displacement                   PD Reciprocatina Positive Displacement           PD-R Reciprocatina Positive Displacement           RPO Vertical Line Shaft                  VLS Pump Driver Motor Driven                     MTR Turbine Driven                    TURB Gear                        GEAR Pump Test Type Discharge Pressure                     Pd Differential Pressure                  dP Flow Rate                         a Speed                           s Skid                         SKID Vibration                        v Pump Test Freq Cold Shutdown                       cs Quarterly                         a Refueling                        RO Eigthteen Months                     18M Two Year                          2Y

CNS ASME In-service Testing Program Rev. 08 CNSSCOPEDOC Page 55 of 59 3/31/2016

Enclosure 10.13 (continued) > *. ( TABLE OF ABBREVIATIONS Pump and Valve Summary Tables Valve Code Class

                                        . *******< * *J:>atabase
                                       **. >     .St~ndardization ASME Class 1                                  1 ASME Class 2                                  2 ASME Class 3                                  3 Non Code                                  NC Valve Category A - Seat Leakage Limited                            A A/C Both Categories A and C                          A/C B - Seat Leakage Not Required                           B B/C - Both Categories Band C                          B/C C - Self Actuating Valves                          c D - Single Use Valves                             D Augmented                                AUG Exempt                                Exempt Skid Mounted                              SKID Valve Type Ball                                   BL Butterfly                                 BF Check                                   CK Diaphragm                                 DA Explosive                                 EX Flow Control                                FC Gate                                   GA Globe                                   GL Not Applicable                              NIA Needle                                  ND Plug                                   PL Power Operated Relief                           PORV Relief or Safety                             RV Rupture Disk                               RD Solenoid                                  sv Three-way                                 3W Vacuum Breaker                                VB Excess Flow Check                              XCK CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 56 of 59 3/31/2016

Enclosure 10.13 (continued)

.*><*.Valve Normal Position TABLE OF ABBREVIATIONS Pump and Valve Summary Tables

                                                <>     Database

<<.::-::::::::.. ..... Standardization Closed c Locked Closed LC Locked Open LO Locked Throttled LT No Safety Related Position N/A Open 0 Open or Closed O/C System Condition Dependent System Dependent Throttled T Valve Safety Position Closed c Locked Closed LC Locked Open LO Locked Throttled LT No Safetv Related Position N/A

Open Open and Closed Valve Fail Position Closed Fail As-is 0

O/C c FAI Open 0 No Safety Related Position N/A Valve Actuator Type . Air AO Electro-Hydraulic 0 perator EH Explosive charge EXP Hand ( manual) MA Hydraulic HO Motor MO Motor/Self Actuated MO/SA Not Aoolicable N/A Self (svstem) actuated SA Self/Air Actuated SA/SO Solenoid so

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 57 of 59 3/31/2016

Enclosure 10.13 (continued) TABLE OF ABBREVIATIONS Pump and Valve Summary Tables Valve.TestType Database*.

    .     .        "'*{**;.... . **:.

Standardization Check Valve Bi-directional Closed BOC Check Valve Bi-directional Open BOO Check Valve Close eve Check Valve Open cvo Check Valve Partial Stroke Test CVP Condition Monitoring CM Diagnostic Test DIAG Disassembly & Inspect DA Exercise Test Closed ETC Exercise Test Open ETO Explosive Test EXP Fail Safe Closed (P/F) FC Fail Safe Closed FC Fail Safe Open (P/F) FO Fail Safe 0 pen FO Full Stroke Exercise Closed Full Stroke Exercise Open Full Stroke Exercise Open/Closed Partial Stroke Exercise Functional Verification FSC FSO FSO/C FSP FV Leak Rate Test App J LTJ Leak Rate Test LT Leak Rate Test PIV LTP Leak Rate Test CIV LTC Manual Stroke Exercise MS No Test Required NTR Partial Stroke Close PSC Partial Stroke Open PSO Partial Stroke Exercise PSE Remote Position Indication RPI Relief Valve Test RV Rupture Disk RD Seat Tightness Test STT Skid Mounted SKID Stroke Time Closed ST-C Stroke Time Open ST-0 CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 58 of 59 3/31/2016

Enclosure 10.13 (continued)

**>*:*. ****/.**./*** ***** /.>*.

          * * *."*.*' :*>:/:*:*./;..*

TABLE OF ABBREVIATIONS Pump and Valve Summary Tables

                                       .Frequency
                                                             .. .*:. ...... Database Standardization Appendix J                                  J Aooendix I                                   I Appendix II                                 II As Required (Procedure Triaaer)                                       AR Cold Shutdown                               cs Condition Monitorino                               CM Every 1O years                              10Y Every 2 years                               2Y Every 5 years                               5Y Every 6 years                               6Y Every 18 Months                               18M Every 6 Months                              6M Normal Operation                              N-OP Not Reauired                               NR Per the MOV Prooram                                 MOV

Quarterly Refuelino Outaoe Every 2nd Refuel Skid Mounted Q

RO 2R SK

CNS ASME In-service Testing Program Rev. 08 CNSSCOPE.DOC Page 59 of 59 3/31/2016

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Catawba 4t.erval Standar de ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 13 Pump Summary Listing Page 1 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ OYCPUCW1 CONTROL ROOM AREA CHILLED CN-1578-02.00 A 3 Centrifugal, Fixed GE600 dP 2Y WATER PUMP (1CRA-P-1) Horizontal Q 2Y v 2Y dP Q Q Q v Q OYCPUCW2 CONTROL ROOM AREA CHILLED CN-1578-02.02 A 3 Centrifugal, Fixed GE600 dP 2Y WATER PUMP (2CRA-P-1) Horizontal Q 2Y v , 2Y - dP Q Q Q v Q

Catawba 4th Interval Standard Code ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 2 of 13 Pump Summary Listing Page 2 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 1CAPUA 1A CA PUMP CN-1592-01.00 B 3 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q 1CAPUB 18 CA PUMP CN-1592-01.00 B 3 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q 1CAPUTD CAPT#1 CN-1592-01.00 B 3 Centrifugal, Var GE600 dP 2Y Horizontal Q 2Y s 2Y

v 2Y dP Q Q Q s Q 1KCPUA1 1A1 COMPONENT COOLING CN-1573-01.00 A 3 Centrifugal, Fixed GE600 dP 2Y PUMP Horizontal Q 2Y v 2Y dP Q ~

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Catawba 4~erval Standa de ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 3 of 13 Pump Summary Listing Page 3 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 1KCPUA2 1A2 COMPONENT COOLING CN-1573-01.00 A 3 Centrifugal, Fixed GE600 dP 2Y PUMP Horizontal Q 2Y v 2Y dP Q Q Q v Q 1KCPU81 181 COMPONENT COOLING CN-1573-01.00 A 3 Centrifugal, Fixed GE600 dP 2Y PUMP Horizontal Q 2Y v 2Y dP Q Q Q v Q 1KCPU82 182 COMPONENT COOLING CN-1573-01.00 A 3 Centrifugal, Fixed GE600 dP 2Y PUMP Horizontal Q 2Y V. 2Y

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Catawba 4th Interval Standard Code ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 4 of 13 Pump Summary Listing Page 4 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 1NDPUA 1A RESIDUAL HEAT REMOVAL CN-1561-01.00 A 2 Centrifugal, Fixed GE600 dP 2Y PUMP Vertical Q 2Y v 2Y dP Q Q Q v Q 1NDPUB 18 RESIDUAL HEAT REMOVAL CN-1561-01.01 A 2 Centrifugal, Fixed GE600 dP 2Y PUMP Vertical Q 2Y v 2Y dP Q Q Q v Q 1NIPUA 1A SAFETY INJECTION PUMP CN-1562-01.02 B 2 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q 1NIPUB 1B SAFETY INJECTION PUMP CN-1562-01.02 B 2 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q 1 ',*

Catawba 419erval Standa de ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 5 of 13 Pump Summary Listing Page 5 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 1NSPUA 1A NS PUMP CN-1563-01.00 8 2 Centrifugal, Fixed GE600 dP 2Y Vertical Q 2Y v 2Y dP Q Q Q 1NSPU8 18 NS PUMP CN-1563-01.00 8 2 Centrifugal, Fixed GE600 dP 2Y Vertical Q 2Y v 2Y dP Q Q Q 1NVPUACC 1A NV PUMP CN-1554-01.07 A 2 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q v Q 1NVPU8CC 18 NV PUMP CN-1554-01.07 A 2 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q v Q

Catawba 4th Interval Standard Code ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 6 of 13 Pump Summary Listing Page 6 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES ORVAR. SPEED REQ 1RNPUA 1A NUCLEAR SERVICE WATER CN-1574-01.00 A 3 Vertical Line Fixed GE600 dP 2Y PUMP Shaft Q 2Y v 2Y dP Q Q Q v Q 1RNPUB 18 NUCLEAR SERVICE WATER CN-1574-01.02 A 3 Vertical Line Fixed GE600 dP 2Y PUMP Shaft Q 2Y v 2Y dP Q Q Q v Q 1WLPUANS 1A ND & NS SUMP PUMP CN-1565-01.01 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y 1WLPUATS TURBINE DRIVEN AUX CN-1565-02.02 B 3 Vertical Line Fixed GE600 dP 2Y FEEDWATER PUMP SUMP PUMP Shaft 1A Q 2Y v 2Y 1WLPUBNS 1B ND & NS SUMP PUMP CN-1565-01.01 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y

Catawba 491erval Standa de ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 7 of 13 P,ump Summary Listing Page 7 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 1WLPUBTS TURBINE DRIVEN AUX CN-1565-02.02 B 3 Vertical Line Fixed GE600 dP 2Y FEEDWATER PUMP SUMP PUMP Shaft 18 Q 2Y v 2Y 1WNPUA1 1A D/G ENG SUMP PUMP 1A1 CN-1609-07.00 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y 1WNPUA2 1A D/G ENG SUMP PUMP 1A2 CN-1609-07.00 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y 1WNPUB1 18 DIG ENG SUMP PUMP 181 CN-1609-07.00 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y 1WNPUB2 1B D/G ENG SUMP PUMP 182 CN-1609-07.00 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y

Catawba 4th Interval Standard Code ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 8 of 13 Pump Summary Listing Page 8 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 2CAPUA 2A AUX FEEDWATER PUMP CN-2592-01.00 B 3 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q 2CAPUB 28 AUX FEEDWATER PUMP CN-2592-01.00 B 3 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q 2CAPUTD CAPT#2 CN-2592-01.00 B 3 Centrifugal, Var GE600 dP 2Y Horizontal - Q 2Y s 2Y v 2Y dP Q Q Q s Q 2KCPUA1 2A1 COMPONENT COOLING CN-2573-01.00 A 3 Centrifugal, Fixed GE600 dP 2Y WATER PUMP Horizontal

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Catawba 4l9erval Stand a de ISTB Catawba Nuclear Plant Interval 4 *1sT 1.0.6 Page 9 of 13 Pump Summary Listing Page 9 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 2KCPUA2 2A2 COMPONENT COOLING CN-2573-01.00 A 3 Centrifugal, Fixed GE600 dP 2Y WATER PUMP Horizontal Q 2Y v 2Y dP Q Q Q v Q 2KCPU81 281 COMPONENT COOLING CN-2573-01.00 A 3 Centrifugal, Fixed GE600 dP 2Y WATER PUMP Horizontal Q 2Y v 2Y dP Q Q Q v Q 2KCPU82 282 COMPONENT COOLING CN-2573-01.00 A 3 Centrifugal, Fixed GE600 dP 2Y WATER PUMP Horizontal Q 2Y v 2Y dP Q Q Q v Q

Catawba 4th Interval Standard Code ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 10 of 13 Pump Summary Listing Page 10 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 2NDPUA 2A RESIDUAL HEAT REMOVAL CN-2561-01.00 A 2 Centrifugal, Fixed GE600 dP 2Y PUMP Vertical Q 2Y v 2Y dP Q Q Q v Q 2NDPU8 28 RESIDUAL HEAT REMOVAL CN-2561-01.01 A 2 Centrifugal, Fixed GE600 dP 2Y PUMP Vertical Q 2Y v 2Y dP Q Q Q v Q 2NIPUA 2A SAFETY INJECTION PUMP CN-2562-01.02 8 2 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q 2NIPU8 28 SAFETY INJECTION PUMP CN-2562-01.02 8 2 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q

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Catawba 419erval Standa de ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 11 of 13 Pump Summary Listing Page 11 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 2NSPUA 2A CONTAINMENT SPRAY PUMP CN-2563-01.00 8 2 Centrifugal, Fixed GE600 dP 2Y Vertical Q 2Y v 2Y dP Q Q Q 2NSPU8 28 CONTAINMENT SPRAY PUMP CN-2563-01.00 8 2 Centrifugal, Fixed GE600 dP 2Y Vertical Q 2Y v 2Y dP Q Q Q 2NVPUACC 2A NV PUMP CN-2554-01.07 A 2 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q v Q 2NVPU8CC 28 NV PUMP CN-2554-01.07 A 2 Centrifugal, Fixed GE600 dP 2Y Horizontal Q 2Y v 2Y dP Q Q Q v Q

Catawba 4th Interval Standard Code ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 12 of 13 Pump Summary Listing Page 12 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 2RNPUA 2A NUCLEAR SERVICE WATER CN-1574-01.00 A 3 Vertical Line Fixed GE600 dP 2Y PUMP Shaft Q 2Y v 2Y dP Q Q Q v Q 2RNPU8 28 NUCLEAR SERVICE WATER CN-1574-01.02 A 3 Vertical Line Fixed GE600 dP 2Y PUMP Shaft Q 2Y v 2Y dP Q Q Q v Q 2WLPUANS 2A ND & NS SUMP PUMP CN-1565-01.01 8 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y 2WLPUATS CAPT #2 SUMP PUMP 2A CN-2565-02.02 8 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y 2WLPU8NS. 28 ND & NS SUMP PUMP CN-1565-01 :01 8 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y

Catawba 4tWerval Standar de ISTB Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 13 of 13 Pump Summary Listing Page 13 of 13 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 2WLPUBTS TURBINE DRIVEN AUX CN-2565-02.02 B 3 Vertical Line Fixed GE600 dP 2Y FEEDWATER PUMP SUMP PUMP Shaft 28 Q 2Y v 2Y 2WNPUA1 2A DIG ENG SUMP PUMP 2A 1 CN-2609-07.00 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y 2WNPUA2 2A DIG ENG SUMP PUMP 2A2 CN-2609-07.00 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y 2WNPUB1 28 DIG ENG SUMP PUMP 281 CN-2609-07.00 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y

v 2Y 2WNPUB2 28 DIG ENG SUMP PUMP 282 CN-2609-07.00 B 3 Vertical Line Fixed GE600 dP 2Y Shaft Q 2Y v 2Y

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Catawba ,..._,.. Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 222 Valve Summary Listing Page 1 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1BB008A 1D SIG SLOWDOWN CN-1580-01.001 B ACT 2 4 GA MO 0 c FAI RPI 2Y INSIDE CONT ISOL K-05 FSC cs CSJ-CN 01 ST-C cs CSJ-CN-BB-01 1880108 SIG 1D BLOWN CONT CN-1580-01.00 I B ACT 2 4 GA MO 0 c FAI RPI 2Y ISOLOTSD K-07 FSC cs CSJ-CN 01 ST-C cs CSJ-CN 01 1BB019A 1B SIG SLOWDOWN CN-1580-01.00 I B ACT 2 4 GA MO 0 c FAI RPI 2Y INSIDE CONT ISOL C-05 FSC cs CSJ-CN 01 ST-C cs CSJ-CN 01 188021 B SIG 1B BLOWN CONT CN-1580-01.00 I B ACT 2 4 GA MO 0 c FAI RPI 2Y ISOLOTSD C-07 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 188052 1D SIG SLOWDOWN CN-1580-01.00 I c ACT 2 0.75 CK SA OIC OIC NIA eve II CONT ISOL PRESS K-05 RELIEF CHECK cvo II 188053 1A SIG SLOWDOWN CN-1580-01.0011- c ACT 2 0.75 CK SA OIC OIC NIA eve II CONT ISOL PRESS 05 RELIEF CHECK cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 2 of 222 Valve Summary Listing Page 2 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 188054 1C S/G SLOWDOWN CN-1580-01.00 IF- c ACT 2 0.75 CK SA OIC O/C N/A eve II CONT ISOL PRESS 05 RELIEF CHECK cvo II 188055 1B SIG SLOWDOWN CN-1580-01.00 I c ACT 2 0.75 CK SA OIC OIC N/A eve II CONT ISOL PRESS D-05 RELIEF CHECK cvo II 1BB056A S/G 1A BLOWN CONT CN-1580-01.00 I B ACT 2 4 GA MO 0 c FAI RPI 2Y ISOL INSD H-05 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-J 01 1880578 SIG 1A BLOWN CONT CN-1580-01.00 I B ACT 2 4 GA MO 0 c FAI RPI 2Y ISOLOTSD H-07 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 1BB060A 1C SIG SLOWDOWN CN-1580-01.00 IF- B ACT 2 4 GA MO 0 c FAI RPI 2Y INSIDE CONT ISOL 05 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 1880618 S/G 1C BLOWN CONT CN-1580-01.00 I F- B ACT 2 4 GA MO 0 c FAI RPI 2Y ISOLOTSD 07 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01

                                                                         *                                                      . *~ ..

Catawba 4' terval Stand a "de ISTC Catawba Nuclear Plant Interval 4 £.: IST 1.0.6 Page 3 of 222 Valve Summary Listing Page 3 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1BB147B SIG 10 BLOWN CONT CN-1580-01.00 I B ACT 2 4 GL MO c c FAI RPI 2Y ISOL BYP K-07 FSC Q ST-C Q 1BB148B SIG 1A BLOWN CONT CN-1580-01.00 I B ACT 2 4 GL MO c c FAI RPI 2Y ISOL BYP H-07 FSC Q ST-C Q 1BB149B SIG 1C BLOWN CONT CN-1580-01.00 I B ACT 2 4 GL MO c c FAI RPI 2Y ISOL BYP E-07 FSC Q ST-C Q 1BB150B SIG 1B BLOWN CONT CN-1580-01.00 I B ACT 2 4 GL MO c c FAI RPI 2Y ISOL BYP C-07 FSC Q ST-C Q 1CA008 CAPT #1 SUCTION CN-1592-01.00 I c ACT 3 10 CK SA O!C O/C N/A eve II CHECK 0-09 cvo II 1CA010 1B CA PUMP SUCTION CN-1592-01.00 I c ACT 3 6 CK SA c OIC N/A eve II CHECK 0-05 cvo II 1CA012 1A CA PUMP SUCTION CN-1592-01.00 I c ACT 3 6 CK SA OIC OIC N/A eve II CHECK 0-01 cvo II 1CA015A CA PUMP 1A SUCT FRM CN-1592-01.00 I B ACT 3 10 GA MO c 0 FAI RPI 2Y RN ISOL 0-02 FSO Q ST-0 .a

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 4 of 222 Valve Summary Listing Page 4 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CA0188 CA PUMP 18 SUCT FRM CN-1592-01.00 I 8 ACT 3 6 GA MO c 0 FAI RPI 2Y RN ISOL D-06 FSO Q ST-0 Q 1CA020 CAPT #1 MINIFLOW CN-1592-01.00 /I- c ACT 3 6 CK SA O/C O/C NIA eve Q CONTROL 11 cvo Q 1CA023 CAPT #1 MINI FLOW TO CN-1592-01.00 I J- c ACT 3 2.5 CK SA OIC OIC NIA eve II UST DOME CHECK 10 cvo II 1CA027 1A CA PUMP MINIFLOW CN-1592-01.00 11- c ACT 3 4 CK SA OIC OIC NIA eve Q CONTROL 04 cvo Q 1CA028 1A CA PUMP MINIFLOW CN-1592-01.00 I J- c ACT 3 2 CK SA OIC OIC NIA eve II TO UST DOME CHECK 03 cvo II 1CA032 18 CA PUMP MINIFLOW CN-1592-01.00 11- c ACT 3 4 CK SA O/C OIC NIA eve Q CONTROL 08 cvo Q 1CA033 18 CA PUMP MINIFLOW CN-1592-01.00 I J- c ACT 3 2 CK SA OIC OIC NIA eve II TO UST DOME CHECK 07 cvo II 1CA036 CA PUMP #1 FLOW TO CN-1592-01.01 / 8 ACT 3 4 FC AO 0 0 0 RPI 2Y SIG 1D C-12 FO Q FSO Q ST-0 Q 1CA037 CA PUMP #1 (TD) DISCH CN-1592-01.011 c ACT 2 4 CK SA OIC OIC NIA eve II TO 1D SIG CHECK G-12 cvo II

Catawba terval Stand a' odelSTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 5 of 222 Valve Summary Listing Page 5 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CA038A CA PMP 1 DISCH TO SIG CN-1592-01.01 I B ACT 2 4 GA MO 0 OIC FAI RPI 2Y 1D ISOL H-12 FSC Q FSO Q ST-C Q ST-0 Q 1CA040 CA PUMP 1B FLOW TO CN-1592-01.01 I J- B ACT 3 4 FC AO 0 0 0 RPI 2Y SIG 1D 12 FO Q FSO Q ST-0 Q 1CA041 18 CA PUMP (MD) DISCH CN-1592-01.01 /I- c ACT 2 4 CK SA N/A OIC N/A eve II TO 1D SIG CHECK 12 cvo II 1CA042B CA PMP B DISCH TO SIG CN-1592-01.01 /I- B ACT 2 4 GA MO 0 OIC FAI RPI 2Y 1D ISOL 12 FSC Q FSO Q ST-C Q ST-0 Q 1CA044 CA PUMP 1B FLOW TO CN-1592-01.01 /J- B ACT 3 4 FC AO 0 0 0 RPI 2Y SIG 1C 09 FO Q FSO Q ST-0 Q 1CA045 1B CA PUMP (MD) DISCH CN-1592-01.01 11- c ACT 2 4 CK SA OIC Ole N/A eve II e TO 1 SIG CHECK 09 evo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 6 of 222 Valve Summary Listing Page 6 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CA046B CA PMP B DISCH TO SIG CN-1592-01.01 /I- B ACT 2 4 GA MO 0 O/C FAI RPI 2Y 1CISOL 09 FSC Q FSO Q ST-C Q ST-0 Q 1CA048 CA PUMP #1 FLOW TO CN-1592-01.01 I B ACT 3 4 FC AO 0 0 0 RPI 2Y SIG 1C C-09 FO Q FSO Q ST-0 Q 1CA049 CA PUMP #1 (TD) DISCH CN-1592-01.011 c ACT 2 4 CK SA OIC O/C NIA eve II TO 1C SIG CHECK G-09 cvo II 1CA050A CA PMP 1 DISCH TO SIG CN-1592-01.011 B ACT 2 4 GA MO 0 OIC FAI RPI 2Y 1CISOL H-09 FSC Q FSO Q ST-C Q ST-0 Q 1CA052 CA PUMP #1 FLOW TO CN-1592-01.011 B ACT 3 4 FC AO 0 0 0 RPI 2Y SIG 18 C-06 FO Q FSO Q ST-0 Q 1CA053 CA PUMP #1 (TD) DISCH CN-1592-01.01 I c ACT 2 4 CK SA O/C OIC N/A eve II TO 1 B SIG CHECK G-06 cvo II

Catawba 4 terval 1 Stand a de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 7 of 222 Valve Summary Listing Page 7 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CA0548 CA PMP 1 DISCH TO SIG CN-1592-01.01 / 8 ACT 2 4 GA MO 0 OIC FAI RPI 2Y 18 ISOL H-06 FSC Q FSO Q ST-C Q ST-0 Q 1CA056 CA PUMP 1A FLOW TO CN-1592-01.01 I J- 8 ACT 3 4 FC AO 0 0 0 RPI 2Y SIG 18 06 FO Q FSO Q ST-0 Q 1CA057 1A CA PUMP (MD) DISCH CN-1592-01.01 / I- c ACT 2 4 CK SA OIC OIC N/A eve II TO 18 S/G CHECK 06 cvo II 1CA058A CA PMP A DISCH TO SIG CN-1592-01.01 /I- 8 ACT 2 4 GA MO 0 O/C FAI RPI 2Y 18 ISOL 06 FSC Q FSO Q ST-C Q ST-0 Q 1CA060 CA PUMP 1A FLOW TO CN-1592-01.01 I J- 8 ACT 3 4 FC AO 0 0 0 RPI 2Y S/G 1A 03 FO Q FSO Q ST-0 Q 1CA061 1A CA PUMP DISCH TO CN-1592-01.01 /I- c ACT 2 4 CK SA OIC O/C N/A eve II 1A SIG CHECK 03 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 8. of 222 Valve Summary Listing Page 8 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CA062A CA PMP A DISCH TO S/G CN-1592-01.01 /I- B ACT 2 4 GA MO 0 OIC FAI RPI 2Y 1A ISOL 03 FSC Q FSO Q ST-C Q ST-0 Q 1CA064 CA PUMP #1 FLOW TO CN-1592-01.01 I B ACT 3 4 FC AO 0 0 0 RPI 2Y S/G 1A C-03 FO Q FSO Q ST-0 Q 1CA065 CAPT #1 DISCH TO 1A CN-1592-01.01 I c ACT 2 4 CK SA OIC OIC N/A eve II SIG CHECK G-03 cvo II 1CA066B CA PMP 1 DISCH TO SIG CN-1592-01.01 / B ACT 2 4 GA MO 0 OIC FAI RPI 2Y 1A ISOL H-03 FSC Q FSO Q ST-C Q ST-0 Q 1CA0858 CA PUMP #1 suer FRM CN-1592-01.00 I B ACT 3 6 GA MO c 0 FAI RPI 2Y RN HOR B D-07 FSO Q ST-0 Q 1CA116A CA PUMP #1 SUCT FRM CN-1592-01.00 I B ACT 3 6 GA MO c 0 FAI RPI 2Y RN HOR A D-08 FSO Q ST-0 Q

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Catawba terval Stand a de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 9 of 222 Valve Summary Listing Page 9 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CA149 1A S/G CF BYPASS TO CA CN-1592-01.01 /I- B ACT 2 6 GA AO 0 c c RPI 2Y NOZZLE 01 FC Q FSC Q ST-C Q 1CA150 1 B S/G CF BYPASS TO CA CN-1592-01.01 /I- B ACT 2 6 GA AO 0 c c RPI 2Y NOZZLE 05 FC Q FSC Q ST-C Q 1CA151 1C SIG CF BYPASS TO CA CN-1592-01.01 /I- B ACT 2 6 GA AO 0 c c RPI 2Y NOZZLE 08 FC Q FSC Q ST-C Q 1CA152 1D SIG CF BYPASS TO CA CN-1592-01.01 /I- B ACT 2 6 GA AO 0 c c RPI 2Y NOZZLE 11 FC Q FSC Q ST-C Q 1CA173 RC TO CA SUCTION CN-1592-01.00 I c ACT 3 8 CK SA OIC c N/A BOO II CHECK E-07 eve II 1CA174 RC TO CA SUCTION ISOL CN-1592-01.00 I B PASS 3 8 BF AO c c 0 RPI 2Y E-07

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 10 of 222 Valve Summary Listing Page 1O of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CA185 1A SIG CF TEMPERING CN-1592-01.011 B ACT 2 2 GA AO 0 c c RPI 2Y FLOW TO CA NOZZLE E-01 FC Q FSC Q ST-C Q 1CA186 1B SIG CF TEMPERING CN-1592-01.01 I B ACT 2 2 GA AO 0 c c RPI 2Y FLOW TO CA NOZZLE* E-05 FC Q FSC Q ST-C Q 1CA187 1C SIG CF TEMPERING CN-1592-01.011 B ACT 2 2 GA AO 0 c c RPI 2Y FLOW TO CA NOZZLE E-08 . FC Q FSC Q ST-C Q 1CA188 10 SIG CF TEMPERING CN-1592-01.011 B ACT 2 2 GA AO 0 c c RPI 2Y FLOW TO CA NOZZLE E-11 FC Q FSC Q ST-C Q 1CA255 1A CA PUMP SUCTION CN-1592-01.00 I c ACT 3 .75 RV SA c O/C N/A RV I RELIEF VALVE E-01 1CA256 1B CA PUMP SUCTION CN-1592-01.00 IF- c ACT 3 .75 RV SA c OIC N/A RV I RELIEF VALVE 04 1CA257 CAPT #1 SUCTION CN-1592-01.oo IF- c ACT 3 0.75 RV SA. c OIC NIA RV I RELIEF VALVE 08 1CA291 RN TO CA X-OVER TRAIN CN-1592-01.00 I c ACT 3 6 CK SA O/C O/C NIA eve II 1A CHECK D-8 cvo II

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Catawba 4 'terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 11 of 222 Valve Summary Listing Page 11 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CA292 RN TO CA X-OVER TRAIN CN-1592-01.001 c ACT 3 6 CK SA OIC OIC NIA eve II 1B CHECK D-7 cvo II 1CF028 1A SIG CF CONTROL CN-1591-01.011 J- B ACT 3 16 FC AO 0 c c RPI 2Y 13 FC cs CSJ-CN-CF-04 FSC cs CSJ-CN-CF-04 ST-C cs CSJ-CN-CF-04 1CF030 1A S/G CF BYPASS CN-1591-01.011 J- B ACT NC 6 FC AO 0 c c RPI 2Y CONTROL 11 FC cs CSJ-CN-CF-05 FSC cs CSJ-CN-CF-05 ST-C cs CSJ-CN-CF-05 1CF031 1A SIG FEEDWATER CN-1591-01.01 I c ACT 2 18 CK SA OIC c NIA BOO II CONTAINMENT ISOL G-13 INLET CHECK eve II 1CF033 1A SIG FEEDWATER CN-1591-01.01 IF- B ACT 2 18 GA HO 0 c c RPI 2Y CONTAINMENT ISOL 13 FC cs CSJ-CN-CF-01 FSC cs CSJ-CN-CF-01 ST-C cs CSJ-CN-CF-01 1CF037 1B SIG CF CONTROL CN-1591-01.011 J- B ACT 3 16 FC AO 0 c c RPI 2Y 09 FC cs CSJ-CN-CF-04 FSC cs CSJ-CN-CF-04 ST-C cs CSJ-CN-CF-04

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 12 of 222 Valve Summary Listing Page 12 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CF039 1B SIG CF BYPASS CN-1591-01.01 I J- B ACT NC 6 FC AO 0 c c RPI 2Y CONTROL 11 FC cs CSJ-CN-CF-05 FSC cs CSJ-CN-CF-05 ST-C cs CSJ-CN-CF-05 1CF040 1 B SIG FEEOWATER CN-1591-01.01 / c ACT 2 18 CK SA OIC c N/A BOO II CONTAINMTNE ISOL G-09 INLET CHECK eve II 1CF042 1B SIG FEEOWATER CN-1591-01.01 IF- B ACT 2 18 GA HO 0 c c RPI 2Y CONTAINMENT ISOL 09 FC cs CSJ-CN-CF-01 FSC cs CSJ-CN-CF-01 ST-C cs CSJ-CN-CF-01 1CF046 1C S/G CF CONTROL CN-1591-01.01 I J- B ACT 3 16 FC AO 0 c c RPI 2Y 06 FC cs CSJ-CN-CF-04 FSC cs CSJ-CN-CF-04 ST-C cs CSJ-CN-CF-04 1CF048 1C S/G CF BYPASS CN-1591-01.01 I J- B ACT NC 6 FC AO 0 c c RPI 2Y CONTROL 05 FC cs CSJ-CN-CF-05 FSC cs CSJ-CN-CF-05 ST-C cs CSJ-CN-CF-05 1CF049 1C SIG FEEOWATER CN-1591-01.01 / c ACT 2 18 CK SA OIC c N/A BOO II CONTAINMENT ISOL G-06 INLET CHECK eve II

Catawba terval Standa Catawba Nuclear Plant Interval 4 Valve Summary Listing Page 13 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CF051 1C SIG FEEDWATER CN-1591-01.01 I F- B ACT 2 18 GA HO 0 c c RPI 2Y CONTAINMENT ISOL . 06 FC cs CSJ-CN-CF-01 FSC cs CSJ-CN-CF-01 ST-C cs CSJ-CN-CF-01 1CF055 1D SIG CF CONTROL CN-1591-01.01 I J- B ACT 3 16 FC AO 0 c c RPI 2Y 03 FC cs CSJ-CN-CF-04 FSC cs CSJ-CN-CF-04 ST-C cs CSJ-CN-CF-04 1CF057 1D S/G CF BYPASS CN-1591-01.01 / J- B ACT NC 6 FC AO 0 c c RPI 2Y CONTROL 04 FC cs CSJ-CN-CF-05 FSC cs CSJ-CN-CF-05 ST-C cs CSJ-CN-CF-05 1CF058 10 S/G FEEDWATER CN-1591-01.01 / c ACT 2 18 CK SA OIC c NIA BOO II CONTAINMENT ISOL G-03 INLET CHECK eve II 1CF060 1D SIG FEEDWATER CN-1591-01.01 IF- B ACT 2 18 GA HO 0 c c RPI 2Y CONTAINMENT ISOL 03 FC cs CSJ-CN-CF-01 FSC cs CSJ-CN-CF-01 ST-C cs CSJ-CN-CF-01

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 14 of 222 Valve Summary Listing Page 14 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CF087 1D SIG CF CONTAINMENT CN-1591-01.01 I F- B ACT 2 2 GA AO c c c RPI 2Y ISOL BYPASS CONTROL 02 FC Q FSC Q ST-C Q 1CF088 1C S/G CF CONTAINMENT CN-1591-01.01 / F- B ACT 2 2 GA AO c c c RPI 2Y ISOL BYPASS CONTROL 06 FC Q FSC Q ST-C Q 1CF089 1B SIG CF CONTAINMENT CN-1591-01.01 I F- B ACT 2 2 GA AO c c c RPI 2Y ISOL BYPASS CONTROL 09 FC Q FSC Q ST-C Q 1CF090 1A SIG CF CONTAINMENT CN-1591-01.01 / F- B ACT 2 2 GA AO c c c RPI 2Y ISOL BYPASS CONTROL 13 FC Q FSC Q ST-C Q 5~~

Catawba 491erval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 15 of 222 Valve Summary Listing Page 15 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1FD022 1A DIG ENG FUEL OIL CN-1609-03.00 I B ACT 3 2 sv so c 0 c RPI 2Y DAY TANK 1A FILL H-12 FC Q

                                             -                                                           FSO    Q ST-0    Q 1FD023  1A D/G ENG FUEL OIL    CN-1609-03.00 I J-   B   ACT   3       2    PL  MA     c    O/C     NIA   FS   2Y DAY TANK 1A FILL VALVE        13 BYPASS 1FD062  1B D/G ENG FUEL OIL     CN-1609-03.01 I     B   ACT   3       2    sv   so    c     0       c   RPI   2Y DAY TANK 1B FILL             H-12 FC    Q FSO    Q ST-0   Q 1FD063  1B D/G ENG FUEL OIL    CN-1609-03.01 I J-   B   ACT   3       2    PL   MA    c    OIC     N/A   FS   2Y DAY TANK 1B FILL VALVE        12 BYPASS 1FW001A  FWLOOP ISOL            CN-1571-01.00 I J-   B   ACT   2       8    GA   MO    c     c      FAI   RPI  2Y 13 FSC    Q ST-C  Q 1FW004  FW PUMP RETURN TO      CN-1571-01.00 IL-    A  PASS   2       6    GA   MA    c     c      N/A   LTJ  J REFUELING CAVITY              07 OUTSIDE CONTAINMENT ISOL 1FW005  FW PUMP RETURN TO      CN-1571-01.00 I L-  A/C  ACT   2       6    CK   SA   OIC   OIC     NIA  eve    II REFUELING CAVITY              05 CHECK
                                                                         -                               cvo    II LTJ   J 1FW011  REFUELING CAVITY TO    CN-1571-01.00 I J-   A  PASS   2       4     PL  MA    c      c     NIA   LTJ    J FW PUMP INSIDE CONT           04 ISOL

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 16 of 222 Valve Summary Listing Page 16 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1FW013 REFUELING CAVITY TO CN-1571-01.00 I J- A PASS 2 4 PL MA c c N/A LTJ J FW PUMP OUTSIDE 05 CONTAINMENT ISOL 1FW027A NDPUMP1ASUCTFROM CN-1571-01.00 IF- 8 ACT 2 12 GA MO 0 O/C FAI RPI 2Y FWST 03 FSC Q FSO Q ST-C Q ST-0 Q 1FW028 1A ND PUMP SUCTION CN-1571-01.00 IF- c ACT 2 12 CK SA OIC OIC N/A eve II FROM FWST CHECK 02 cvo II 1FW0328 FWLOOP ISOL CN-1571-01.00 I J- 8 ACT 2 8 GA MO c c FAI RPI 2Y 13 FSC Q ST-C Q 1FW033A FWST RECIRC LOOP CN-1571-01.00/ 8 ACT 2 2 GL MO 0 c FAI RPI 2Y ISOL 8-11 FSC Q ST-C Q 1FW0498 FWST RECIRC LOOP CN-1571-01.00 I

                                             .      8   ACT    2      2  GL   MO      0     c      FAI   RPI  2Y ISOL                       8-07 FSC    Q ST-C  Q 1FW052    NS/NI TEST LINE TO    CN-1571-01.00/     c   ACT   NC      4  CK    SA    OIC    0      N/A  BOC    II FWST CHECK                 E-10 cvo    II
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Catawba terval Standa ode ISTC 1 Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 17 of 222 Valve Summary Listing Page 17 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1FW055B NDPUMP1BSUCTFROM CN-1571-01.00/ B ACT 2 12 GA MO 0 O/C FAI RPI 2Y FWST H-03 FSC Q FSO Q ST-C Q ST-0 Q 1FW056 1B ND PUMP SUCTION CN-1571-01.00/ c ACT 2 12 CK SA OIC OIC N/A eve II FROM FWST CHECK H-02 cvo II 1FW096 1A ND PUMP SUCTION CN-1571-01.00 I c ACT 2 0.75 CK SA OIC OIC NIA eve II HOR PRESSURE E-02 CONTROL CHECK cvo II 1FW097 1B ND PUMP SUCTION CN-1571-01.00 I c ACT 2 0.75 CK SA OIC O/C N/A eve II HOR PRESSURE G-02 CONTROL CHECK cvo II 11ACK5340 UPPER PERSONNEL AIR CN-1499-1A.01-01 NC ACT 2 0.5 CK SA OIC c N/A BOO II LOCK CONTROL I eve II LTJ J 11ACK5350 LOWER PERSONNEL AIR CN-1499-1A.01-01 NC ACT 2 0.5 CK SA OIC c N/A BOO II LOCK CONTROL I eve II LTJ J 11ACK5360 UPPER PERSONNEL AIR CN-1499-1A.01-01 NC ACT 2 0.5 CK SA OIC c N/A BDO II LOCK CONTROL I eve II LTJ J

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 18 of 222 Valve Summary Listing Page 18 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 11ACK5370 LOWER PERSONNEL AIR CN-1499-1A.01-01 AIC ACT 2 0.5 CK SA OIC c N/A BOO II LOCK CONTROL I eve II LTJ J 11ACK5380 UPPER PERSONNEL AIR CN-1499-1A.01-01 A/C ACT 2 0.5 CK SA OIC c N/A BOO II LOCK CONTROL I eve II LTJ J 11ACK5390 LOWER PERSONNEL AIR CN-1499-1A.01-01 AIC ACT 2 0.5 CK SA OIC c NIA BOO II LOCK CONTROL I eve II LTJ J 11ASV5080 UPPER PERSONNEL AIR CN-1499-1A.01-01 A ACT 2 0.5 sv so 0 c c RPI 2Y LOCK CONTROL I LTJ J FC Q FSC Q ST-C Q 11ASV5160 LOWER PERSONNEL AIR CN-1499-1A.01-01 A ACT 2 0.5 sv so 0 c c RPI 2Y LOCK CONTROL I LTJ J FC Q FSC Q ST-C Q

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Catawba 491erval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 19 of 222 Valve Summary Listing Page 19 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ. NORM SAFE FAIL 11ASV5400 UPPER PERSONNEL AIR CN-1499-1 A.01-01 A ACT 2 0.5 sv so 0 c c RPI 2Y LOCK CONTROL I LTJ J FC Q FSC Q ST-C Q 11ASV5410 LOWER PERSONNEL AIR CN-1499-1A.01-01 A ACT 2 0.5 sv so 0 c c RPI 2Y LOCK CONTROL I LTJ J FC Q FSC Q ST-C Q 1KC001A AUX BLDG NON- CN-1573-01.00 I B ACT 3 20 BF MO 0 c FAI RPI 2Y ESSENTIAL RETURN C-06 HEADERISOL FSC Q ST-C Q 1KC002B AUX BLDG NON- CN-1573-01.00 I B ACT 3 20 BF MO 0 c FAI RPI 2Y ESSENTIAL RETURN C-09 HEADERISOL FSC Q ST-C Q 1KC003A RX BLDG NON- CN-1573-01.00 I B ACT 3 10 GA MO 0 c FAI RPI 2Y ESSENTIAL RETURN C-06 HEADERISOL FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 20 of 222 Valve Summary Listing Page 20 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1KC005 1A1 KC PUMP DISCH CN-1573-01.00 I c ACT 3 16 CK SA O/C OIC N/A eve II CHECK E-04 cvo II 1KC008 1A2 KC PUMP DISCH CN-1573-01.00/ c ACT 3 16 CK SA OIC OIC N/A eve II CHECK E-05 cvo II 1KC011 1B1 KC PUMP DISCH CN-1573-01.00 I c ACT 3 16 CK SA O/C O/C N/A eve II CHECK E-11 cvo II 1KC014 1 B2 KC PUMP DISCH CN-1573-01.00 I c ACT 3 16 CK SA OIC OIC N/A eve II CHECK E-12 cvo II 1KC018B RX BLDG NON- CN-1573-01.00 I B ACT 3 .10 GA MO 0 c FAI RPI 2Y ESSENTIAL RETURN C-09 HEADERISOL FSC Q ST-C Q 1KC047 RX BLDG DRAIN HEADER CN-1573-01.05 / A/C ACT 2 0.75 CK SA OIC OIC N/A eve II PRESSURE H-04 EQUALIZATION CHECK cvo II LTJ J 1KC050A AUX BLDG NON- CN-1573-01.00 I B ACT 3 20 BF MO 0 c FAI RPI 2Y ESSENTIAL HEADER ISOL K-07 FSC Q ST-C Q 1KC053B AUX BLDG NON- .CN-1573-01.00 I B ACT 3 20 BF MO 0 c FAI RPI 2Y ESSENTIAL HEADER ISOL K-08 FSC Q

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Catawba terval Standa delSTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 21 of 222 Valve Summary Listing Page 21 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1KC056A KC TO ND HX 1A SUP CN-1573-02.00 I B ACT 3 16 BF MO c 0 FAI RPI 2Y

         !SOL                         E-03 FSO    Q ST-0   Q 1KC057A  1A ND HX FLOW          CN-1573-02.00 /I-    B   ACT   3       16   BL  AO     0    0       0   RPI   2Y CONTROL                       03 FO    Q FSO    Q ST-0  Q 1KC061 1A ND HX OUTLET         CN-1573-02.00  I    c   ACT   3        4   RV   SA    c   OIC     N/A   RV   I RELIEF                       H-04 1KC079 1A ND PUMP MECH SEAL   CN-1573-02.00 /I-    c   ACT   3     0.75   RV   SA    c   OIC     NIA   RV   I HX RELIEF                     06 1KC081B KC TO ND HX 1B SUP      CN-1573-02.01  I    B   ACT   3     . 16   BF   MO    c    0      FAI   RPI  2Y ISOL                          E-3 FSO    Q ST-0  Q 1KC082B  1B ND HXFLOW          CN-1573-02.01  I J-  B   ACT   3       12   BL   AO    0    0       0    RPI  2Y CONTROL                      03 FO     Q FSO     Q ST-0  Q 1KC086  1B ND HX OUTLET        CN-1573-02.01 /     c   ACT   3      0.75  RV   SA    c   OIC     N/A   RV    I RELIEF                      H-06 1KC104  1B ND PUMP MECH SEAL   CN-1573-02.01 /     c   ACT   3      0.75  RV   SA    c   OIC     N/A   RV    I HX RELIEF                   H-06 1KC228B  RX BLDG NON-          CN-1573-01.00/ L-    B   ACT   3        8   GA   MO    0    c      FAI   RPI   2Y ESSENTIAL HEADER ISOL        08 FSC     Q ST-C  Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 22 of 222 Valve Summary Listing Page 22 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1KC230A RX BLDG NON- CN-1573-01.00 IL- B ACT 3 8 GA MO 0 c FAI RPI 2Y ESSENTIAL HEADER ISOL 07 FSC Q ST-C Q 1KC279 NC PUMPS RETURN CN-1573-01.03 / AIC ACT 2 1 CK SA OIC OIC N/A eve II HEADER PRESSURE K-05 EQUALIZATION CHECK cvo II LTJ J 1KC280 NCDT HX COOLING CN-1573-01.03 / c ACT 2 1 CK SA OIC OIC N/A eve II WATER RETURN E-01 PRESSURE EQUALIZATION CHECK cvo II 1KC281 NC PUMPS SLOWDOWN CN-1573-01.03 / c ACT 2 3 RV SA c O/C N/A RV I HX'S RETURN HEADER K-03 RELIEF 1KC3058 EXS LETDN HX SUPPLY CN-1573-01.03 / A ACT 2 4 GA MO c c FAI RPI 2Y CONT ISOL D-13

                                               .                                                            LT  2Y FSC     Q ST-C  Q 1KC313    EXCESS LETDN HX       CN-1573-01.03 /I-   c   ACT   3     0.75   RV   SA    c    O/C     N/A   RV    I OUTLET RN TO KC DRN          12 SUMP 1KC3158    EXS LETDN HX RET      CN-1573-01.03 / L-  A   ACT   2      4     GA  MO     c     c      FAI   RPI   2Y CONT ISOL                    13 LT  2Y FSC     Q ST-C  Q
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Catawba 491erval Stand a de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 23 of 222 Valve Summary Listing Page 23 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1KC320A NCDT HX COOL SUPPLY CN-1573-01.03 / A ACT 2 4 GA MO 0 c FAI RPI 2Y CONT ISOL 8-10 LT - 2Y FSC cs CSJ-CN-KC-01 ST-C cs CSJ-CN-KC-01 1KC322 NCDT HX SUP HOR CN-1573-01.03 / c ACT 2 4 CK SA O/C OIC N/A eve II CHECK 8-08 cvo II 1KC330 NCDT HX OUTLET RELIEF CN-1573-01.03 / c ACT 3 0.75 RV SA c O/C N/A RV I TO KC DRAIN SUMP 8-01 1KC3328 NCDT HX COOLING CN-1573-01.03/ A ACT 2 4 GA MO 0 c FAI RPI 2Y RETURN CONT ISOL E-02 LT 2Y FSC cs CSJ-CN-KC-01 ST-C cs CSJ-CN-KC-01 1KC333A NCDT HX COOL RET CN-1573-01.03 / A ACT 2 4 GA MO 0 c FAI RPI 2Y CONT ISOL G-02 LT 2Y FSC cs CSJ-CN-KC-01 ST-C cs CSJ-CN-KC-01 1KC3388 NC PUMPS SUP HOR CN-1573-01.03/ A ACT 2 8 GA MO 0 c FAI RPI 2Y CONT ISOL D-12 LT 2Y FSC cs CSJ-CN-KC-02 ST-C cs CSJ-CN-KC-02

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 24 of 222 Valve Summary Listing Page 24 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1KC340 NC PUMPS SUPPLY CN-1573-01.03 / F- A/C ACT 2 8 CK SA OIC O/C N/A eve II HEADER CHECK 12 cvo II LTJ J 1KC344 1 C NC PUMP THERMAL CN-1573-01.07 / c ACT 2 2 CK SA OIC c N/A BDO II BARRIER INLET CHECK K-13 eve II 1KC355 NC PUMP 1C MTR LWR CN-1573--01.07 I c ACT 3 0.75 RV SA c O/C NIA RV I BRG CLR RN TO KC DRN K-10 SUMP 1KC361 1C NC PUMP MOTOR CN-1573--01.07 I c ACT 3 0.75 RV SA c OIC N/A RV I UPPER BRG COOLER H--08 RELIEF TO KC DRAIN SUMP 1KC363 1B NC PUMP THERMAL CN-1573--01.07 I c ACT 2 2 CK SA OIC c N/A BDO II BARRIER INLET CHECK K-06 eve II 1KC374 1B NC PUMP MOTOR CN-1573-01.07 / c ACT 3 0.75 RV SA c O/C N/A RV I LOWER BRG COOLER K-04 RELIEF TO KC DRAIN SUMP 1KC380 NC PUMP 1B MTR UPR CN-1573-01.07 / c ACT 3 0.75 RV SA c OIC N/A RV I BRG CLR RN TO KC DRN H-02 SUMP 1KC386 1A NC PUMP MOTOR CN-1573-01.04 / c ACT 3 0.75 RV SA c OIC N/A RV I UPPER BRG COOLER H-12 RELIEF TO KC DRAIN SUMP 1KC392 1A NC PUMP MOTOR CN-1573-01.04 / c ACT 3 0.75 RV SA c OIC N/A RV I LOWER BRG COOLER K-10 RELIEF TO KC DRAIN SUMP 1KC393 1A NC PUMP THERMAL CN-1573-01.04/ c ACT 2 2 CK SA OIC c N/A BDO II BARRIER INLET CHECK K-09 eve II 1KC404 1D NC PUMP MOTOR CN-1573-01.04 / c ACT 3 0.75 RV SA c OIC N/A RV I UPPER BRG COOLER H-06

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Catawba ., Catawba Nuclear Plant Interval 4 Stand a de ISTC IST 1.0.6 Page 25 of 222 Valve Summary Listing Page 25 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1KC410 1D NC PUMP MOTOR CN-1573-01.04 / J- c ACT 3 0.75 RV SA c OIC N/A RV I LOWER BRG COOLER 04 RELIEF TO KC DRAIN SUMP 1KC412 1D NC PUMP THERMAL BARRIER INLET CHECK CN-1573-01.04 / J-03 c ACT 2 2 CK SA O/C c N/A BOO II . eve II 1KC424B NC PUMPS RETURN CN-1573-01.03 / L- A ACT 2 8 GA MO 0 c FAI RPI 2Y HEADER CONT ISOL 05 LT 2Y FSC cs CSJ-CN-KC-02 ST-C cs CSJ-CN-KC-02 1KC425A NC PUMPS RET HOR CN-1573-01.03 / L- A ACT 2 8 GA MO 0 c FAI RPI 2Y CONT ISOL 07 LT 2Y FSC cs CSJ-CN-KC-02 ST-C cs CSJ-CN-KC-02 1KC429B RX BLDG DRAIN HEADER CN-1573-01.05 / A ACT 2 2 GL MO 0 c FAI RPI 2Y CONT ISOL H-03 LTJ J FSC Q ST-C Q 1KC430A RX BLDG ORN HOR CONT CN-1573-01.05 / J- A ACT 2 2 GL MO 0 c FAI RPI 2Y ISOL 03 LTJ J FSC Q ST-C Q 1KC494 1A KC SURGE TANK CN-1573-01.01 / B ACT 3 4 PL MA c OIC N/A FS 2Y EMERGENCY RN MIU H-02

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 26 of 222 Valve Summary Listing Page 26 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1KC497 1B KC SURGE TANK CN-1573-01.01 I B ACT 3 4 PL MA c OIC NIA FS 2Y EMERGENCY RN MIU H-13 1KC814 KC ORN HOR RN CN-1573-01.05/ c ACT NC 0.75 RV SA c OIC NIA RV I G-01 1KCC37A 1A KC MINI FLOW ISOL CN-1573-01.00 I B ACT 3 6 GL MO c OIC FAI RPI 2Y C-03 FSC Q FSO Q ST-C Q ST-0 Q 1KCC40B 1B KC MINIFLOWISOL CN-1573-01.00 I B ACT 3 6 GL MO c OIC FAI RPI 2Y D-10 FSC Q FSO Q ST-C Q ST-0 Q 1KCC42 RADIATION MONITOR CN-1573-01.00 I .C ACT 3 0.75 CK SA OIC c NIA BOO II 1EMF-46A OUTLET K-01 CHECK eve II 1KCC43 RADIATION MONITOR 1 EMF-46B OUTLET CN-1573-01.00 E-10 I c ACT 3 0.75 CK SA OIC c NIA BOO II . CHECK eve II 1KD006 1A DIG ENG DRIVEN CN-1609-01.00 I J- c ACT 3 8 CK SA OIC OIC N/A eve II JACKET WATER 10 CIRCULATION PUMP DISCH CHECK cvo II 1KD021 1B D/G ENG DRIVEN CN-1609-01.00 I c ACT 3 8 CK SA OIC O/C NIA eve II JACKET WATER E-10 CIRCULATION PUMP DISCH CHECK cvo II

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Catawba 4.terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 27 of 222 Valve Summary Listing Page 27 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1KF097 1A KF ASSURED FUEL CN-1570-01.00 /I- B ACT 3 4 PL MA c OIC NIA FS 2Y POOL MIU ISOL 12 1KF101 B FWST TO SPENT FUEL CN-1570-01.00 I B ACT 2 4 GA MO c c FAI RPI 2Y POOL H-14 FSC Q ST-C Q 1KF103A FWST TO SPENT FUEL CN-1570-01.00 I B ACT 2 4 GA MO c c FAI RPI 2Y POOL H-12 FSC Q ST-C Q 1KF104 1B KF ASSURED FUEL CN-1570-01.00 I B ACT 3 4 PL MA c O/C N/A FS 2Y POOL M/U ISOL H-12 1 KF172 FWST OVERFLOW TO CN-1570-01.00 I J- B ACT 3 3 GA MA 0 c N/A FS 2Y SPENT FUEL POOL 12 1LD017 1A DIG ENG LUBE OIL CN-1609-02.00 I c ACT 3 6 CK SA OIC 0 N/A BOC II STRAINER 1A1 CHECK K-5 cvo II 1LD018 1A DIG ENG LUBE OIL CN-1609-02.00 I J- c ACT 3 6 CK SA OIC 0 N/A BOC II STRAINER 1A2 CHECK 6 cvo II 1LD047 1B D/G ENG LUBE OIL CN-1609-02.02 / c ACT 3 6 CK SA OIC 0 N/A BOC II STRAINER 1B1 CHECK K-5 cvo II 1LD048 1B D/G ENG LUBE OIL CN-1609-02.02 / J- c ACT 3 6 CK SA O/C 0 N/A BOC II STRAINER 1B2 CHECK 6 cvo II 1MIMV6470 ILRT ISO VALVE I A PASS 2 GA MA c c N/A LTJ J . 1MIMV6471 ILRT ISOL I A PASS 2 GA MA c c N/A LTJ J 1MIMV6480 ILRT ISO VALVE I A PASS 2 GA MA c c N/A LTJ J 1MIMV6481 ILRT ISOL I A PASS 2 GA MA c c N/A LTJ J

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 28 of 222 Valve Summary Listing Page 28 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ *PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1MIMV6490 ILRT ISO VALVE I A PASS 2 GA MA c c N/A LTJ J 1MIMV6491 ILRT ISOL I A PASS 2 GA MA c c N/A LTJ J 1MISV0150 HYDROGEN MONITOR I A PASS NC sv so c c c LTJ J SAMPLE SELECTION

      .. TRAIN A 1MISV0160  HYDROGEN MONITOR            I       A  PASS  NC          sv   so      c    c      c    LTJ   J SAMPLE SELECTION TRAIN B 1MISV0170  HYDROGEN MONITOR            I       A  PASS  NC          sv   so      c    c      c    LTJ   J SAMPLE SELECTOR TRAIN A 1MISV0180  HYDROGEN MONITORING         I       A  PASS  NC          sv    so     c    c      c    LTJ   J SAMPLE SELECTOR TRAIN B 1MISV5230  CONT EMF SUP OTSD           I       A   ACT   2          sv    so     0    c      c    RPI  2Y CONT ISOL LTJ  J FC   Q FSC   Q ST-C  Q 1MISV5231  CONT EMF SUP INSD           I       A   ACT   2          sv    so     0    c      c    RPI  2Y CONT ISOL LTJ  J FC   Q FSC   Q ST-C  Q e:::.
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Catawba Catawba Nuclear Plant Interval 4 de ISTC IST 1.0.6 Page 29 of 222 Valve Summary Listing Page 29 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1MISV5232 CONT EMF RET OTSD I A ACT 2 sv so 0 c c RPI 2Y CONT ISOL LTJ J FC Q FSC Q ST-C Q 1MISV5233 CONT EMF RET INSD I A ACT 2 sv so 0 c c RPI 2Y CONT ISOL LTJ J FC Q FSC Q ST-C Q 1NB103 RELIEF HEADER CHECK CN-1556-01.03 / c ACT 3 6 CK SA OIC 0 NIA BOC II TO RHT E-11 cvo II 1NB134 RECYCLE EVAP FEED CN-1556-01.03 / J- B ACT 3 1 GL MA OIC c N/A FS 2Y PUMP A RECIRC 08 1NB223 NB EVAP CONDENSER CN-1556-01.04 / B ACT 3 2 PL AO/M OIC c N/A FS 2Y FILTER OUTLET TO NB D-07 A EVAP FEED DEMIN 1NB260B RMWST CONT ISOL CN-1556-02.00 I A ACT 2 1 GL MO c c FAI RPI 2Y G-04 LTJ J FSC Q ST-C Q 1NB262 RMWST REACTOR BLDG CN-1556-02.00 I A/C ACT 2 1 CK SA OIC OIC N/A eve II SUPPLY HEADER CHECK G-06 cvo II LTJ J 1NB331 RMWST REACTOR BLDG CN-1556-02.00 I c ACT NC 1 RV SA c O/C N/A RV I SUPPLY HEADER RELIEF G-08 TO NCDT

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 30 of 222 Valve Summary Listing Page 30 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NB382 LEAKOFF HEADER TO CN-1556-01.06 / I- c ACT 3 1 CK SA OIC c NIA BOO II RHT CHECK 12 eve II 1NB383 RECYCLE EVAP FEED . CN-1556-01.03 / J- B ACT 3 1 GL MA OIC c N/A FS 2Y PUMP B RECIRC 08 1NB447 RECIRC TO RECYCLE CN-1556-01.02 / J- B ACT 3 1 PL MA OIC c N/A FS 2Y HOLDUP TANK A ISOL 14 1NB448 RECIRC TO RECYCLE CN-1556-01.02 /I- B ACT 3 1 PL MA OIC c N/A FS 2Y HOLDUP TANK B ISOL 14 1NB800 RMWST AND BAT CN-1556-01.01 / c ACT 3 4 CK SA OIC c N/A BOO II OVERFLOW CHECK H-05 eve II 1NC001 UNIT 1 PZR SAFETY CN-1553-01.01 / c ACT 1 6 RV SA c OIC N/A RV I RELIEF K-03 1NC002 UNIT 1 PZR SAFETY CN-1553-01.01 / c ACT 1 6 RV SA c O/C NIA RV I RELIEF K-04 1NC003 UNIT 1 PZR SAFETY CN-1553-01.01 I c ACT 1 6 RV SA c OIC N/A RV I RELIEF K-05 1NC031B UNIT 1 PZR PORV ISOL CN-1553-01.01 IF- B ACT 1 4 GA MO 0 OIC FAI RPI 2Y 04 FSC Q FSO Q ST-C Q ST-0 Q 1NC032B UNIT 1 PZR PORV CN-1553-01.01 / B ACT 1 4 PORV AO c O/C c STT 2Y G-04 FC cs CSJ-CN-NC-02 FSC cs CSJ-CN-NC-02 FSO cs CSJ-CN-NC-02 ST-C cs CSJ-CN-NC-02 ST-0 cs CSJ-CN-NC-02

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Catawba 4 terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 31 of 222 Valve Summary Listing Page .31 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NC033A UNIT 1 PZR PORV ISOL CN-1553-01.01 IF- B ACT 1 4 GA MO 0 OIC FAI RPI 2Y 03 FSC Q FSO Q ST-C Q ST-0 Q 1NC034A UNIT 1 PZR PORV CN-1553-01.01 / B ACT 1 4 PORV AO c OIC c STT 2Y G-03 FC cs CSJ-CN-NC-02 FSC cs CSJ-CN-NC-02 FSO cs CSJ-CN-NC-02 ST-C cs CSJ-CN-NC-02 ST-0 cs CSJ-CN-NC-02 1NC035B UNIT 1 PZR PORV ISOL CN-1553-01.01 IF- B ACT 1 4 GA MO 0 OIC FAI RPI 2Y 02 FSC Q FSO Q ST-C Q ST-0 Q 1NC036B UNIT 1 PZR PORV CN-1553-01.01 I B ACT 1 4 PORV AO c OIC c STT 2Y G-02 FC cs . CSJ-CN-NC-02 FSC cs CSJ-CN-NC-02 FSO cs CSJ-CN-NC-02 ST-C cs CSJ-CN-NC-02 ST-0 cs CSJ-CN-NC-02

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 32 of 222 Valve Summary Listing Page 32 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NC053B N2 TO PRT CONT ISOL CN-1553-01.01 I A ACT 2 1 GL MO c c FAI RPI 2Y K-11 LTJ J FSC Q ST-C Q 1NC054A NITROGEN TO PZR CN-1553-01.01 I A ACT 2 1 GL MO c c FAI RPI 2Y RELIEF TANK K-09 CONTAINMENT ISOL LTJ J FSC Q ST-C Q 1NC056B RMW PUMP DISCH CONT CN-1553-01.01 /I- A ACT 2 3 GA MO c c FAI RPI 2Y ISOL 13 LT 2Y FSC Q ST-C Q 1NC057 PZR RELIEF TANK SPRAY CN-1553-01.01 /I- NC ACT 2 3 CK SA OIC OIC N/A eve II SUPPLY CHECK 12 cvo II LTJ J 1NC141 UNIT 1 NC MOTOR OIL CN-1553-01.03 / J- A PASS 2 2 GA MA c c N/A LTJ J DRAIN PUMP INSIDE 08 CONTAINMENT ISOL 1NC142 NC MTR OIL ORN PMP CN-1553-01.03/ A PASS 2 2 GA MA c c N/A LTJ J OUTSIDE CONT ISOL K-08

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Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 33 of 222 Valve Summary Listing Page 33 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NC195B NC PUMP MTR OIL FILL CN-1553-01.03 / A ACT 2 2 GA MO c c FAI RPI 2Y ISOL D-07 LTJ J FSC Q ST-C Q 1NC196A UNIT 1 NC PUMP MOTOR CN-1553-01.03/ A ACT 2 2 GA MO c c FAI RPI 2Y OIL FILL ISOL D-07 LTJ J FSC Q ST-C Q 1NC250A UNIT 1 REACTOR HEAD CN-1553-01.01 IL- B ACT 1 1 GL MO c OIC FAI RPI 2Y VENT BLOCK 07 FSC cs CSJ-CN-NC-03 FSO cs CSJ-CN-NC-03 ST-C cs CSJ-CN-NC-03 ST-0 cs CSJ-CN-NC-03 1NC251B UNIT 1 REACTOR HEAD CN-1553-01.01 IL- B ACT 1 1 GL MO c O/C FAI RPI 2Y VENT 06 FSC cs CSJ-CN-NC-03 FSO cs CSJ-CN-NC-03 ST-C cs CSJ-CN-NC-03 ST-0 cs CSJ-CN-NC-03

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 34 of 222 Valve Summary Listing Page 34 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NC252B UNIT 1 REACTOR HEAD CN-1553-01.01 / B ACT 1 1 GL MO c O/C FAI RPI 2Y VENT BLOCK K-07 FSC cs CSJ-CN-NC-03 FSO cs CSJ-CN-NC-03 ST-C cs CSJ-CN-NC-03 ST-0 cs CSJ-CN-NC-03 1NC253A RX HEAD VENT CN-1553-01.01 I B ACT 1 1 GL MO c O/C FAI RPI 2Y K-06 FSC cs CSJ-CN-NC-03 FSO cs CSJ-CN-NC-03 ST-C cs CSJ-CN-NC-03 ST-0 cs CSJ-CN-NC-03 1ND001B ND PUMP 1A SUCT FRM CN-1561-01.00 I L- A ACT 1 12 GA MO c 0 FAI RPI 2Y LOOP B 13 LT 2Y FSO cs CSJ-CN-ND-01 ST-0 cs CSJ-CN-ND-01 1ND002A ND PUMP 1A SUCT FRM CN-1561-01.00 I J- A ACT 1 12 GA MO c 0 FAI RPI 2Y LOOP B 13 LT 2Y FSO cs CSJ-CN-ND-01 ST-0 cs CSJ-CN-ND-01 1ND003 1A ND PUMP SUCTION CN-1561-01.00 /I- c ACT 2 4 RV SA c O/C N/A RV I FROM NC LOOP B 13

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Catawba 49terval Standa'W>de ISTC Catawba Nu'Clear Plant Interval 4 . IST 1.0.6 Page 35 of 222 Valve Summary Listing Page 35 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1ND010 1A ND PUMP DISCH CN-1561-01.00/ c ACT 2 8 CK SA O/C OIC N/A eve II CHECK G-10 cvo II 1ND024A 1A ND HX OUTLET TO CN-1561-01.00 I B PASS 2 2 GL MO c c FAI RPI 2Y LETDOWN HX G-05 1ND025A 1A ND PUMP MINIFLOW CN-1561-01.00 I B ACT 2 2 GL MO c OIC FAI RPI 2Y E-13 FSC Q FSO Q ST-C Q ST-0 Q 1ND026 1A ND HX OUTLET CN-1561-01.00/ B ACT 2 8 FC AO 0 0 0 RPI 2Y CONTROL G-04 FO Q FSO Q ST-0 Q 1ND027 1A ND HX BYPASS CN-1561-01.00 I J- B ACT 2 8 FC AO c c c RPI 2Y CONTROL 06 FC Q FSC Q ST-C Q 1ND028A ND SUPPLY TO NV & 1A CN-1561-01.00 I B ACT 2 8 GA MO c O/C FAI RPI 2Y NI PUMPS H-04 FSC cs CSJ-CN-ND-05 FSO cs CSJ-CN-ND-05 ST-C cs CSJ-CN-ND-05 ST-0 cs CSJ-CN-ND-05

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 36 of 222 Valve Summary Listing Page 36 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1ND031 1A ND TRAIN COLD LEG CN-1561-01.00/ c ACT 2 4 RV SA c OIC NIA RV I INJ RETURN SAFETY G-02 RELIEF 1ND032A ND TRAIN 1A HOT LEG CN-1561-01.00 IF- B ACT 2 8 GA MO 0 O/C FAI RPI 2Y INJ ISOL 03 FSC cs CSJ-CN-ND-04 FSO cs CSJ-CN-ND-04 ST-C cs CSJ-CN-ND-04 ST-0 cs CSJ-CN-ND-04 1ND035 ND HOT LEG INJ RETURN CN-1561-01.00 I c ACT 2 1 RV SA c OIC N/A RV I SAFETY RELIEF D-02 1ND036B ND PUMP 1B SUCT FRM CN-1561-01.01 / L- A ACT 1 12 GA MO c 0 FAI RPI 2Y LOOPC 13 LT 2Y FSO cs CSJ-CN-ND-02 ST-0 cs CSJ-CN-ND-02 1ND037A ND PUMP 1B SUCT FRM CN-1561-01.01 I J- A ACT 1 12 GA MO c 0 FAI RPI 2Y LOOP C 13 LT 2Y FSO cs CSJ-CN-ND-02 ST-0 cs CSJ-CN-ND-02 1ND038 1B ND PUMP SUCTION CN-1561-01.01 /I- c ACT 2 4 RV SA c O/C N/A RV I FROM NC LOOP C 13 HEADER RELIEF 1ND044 1B ND PUMP DISCH CN-1561-01.01 / c ACT 2 8 CK SA OIC OIC N/A eve II CHECK G-10

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Catawba lerval Standa-ode ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 37 of 222 Valve Summary Listing Page 37 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1ND058B 1 B ND HX OUTLET TO CN-1561-01.01 / B PASS 2 2 GL MO c c FAI RPI -2Y LETDOWN HX G-05 1ND059B 18 ND PUMP MINIFLOW CN-1561-01.01 / B ACT 2 2 GL MO c OIC FAI RPI 2Y E-13 FSC Q FSO Q ST-C Q ST-0 Q 1ND060 18 ND HX OUTLET CN-1561-01.01 / B ACT 2 8 FC AO 0 0 0 RPI 2Y CONTROL G-04 FO Q FSO Q ST-0 Q I 1ND061 18 ND HX BYPASS CN-1561-01.01 I J- B ACT 2 8 FC AO c c c RPI 2Y CONTROL 06 FC Q FSC Q ST-C Q 1ND064 18 ND TRAIN COLD LEG CN-1561-01.01 I c ACT 2 4 RV SA c O/C N/A RV I INJ RETURN SAFETY H-02 RELIEF 1ND065B ND TRAIN 1B HOT LEG. CN-1561-01.01 /F- B ACT 2 8 GA MO 0 OIC FAI RPI 2Y INJ ISOL 03 FSC cs CSJ-CN-ND-04 FSO cs CSJ-CN-ND-04 ST-C cs CSJ-CN-ND-04 ST-0 cs CSJ-CN-ND-04

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 38 of 222 Valve Summary Listing Page 38 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1ND090 1A ND TRAIN AUX PZR CN-1561-01.00 I B PASS 2 2 GL MO c c FAI RPI 2Y SPRAY ISOL E-09 1ND091 18 ND TRAIN AUX PZR CN-156Hl1.00 I B PASS 2 2 GL MO c c FAI RPI 2Y SPRAYISOL E-09 1ND116 OVERPRESSURE CHECK CN-1561-01.00 I c ACT 2 0.75 CK SA O/C OIC N/A eve II VALVE AROUND 1ND-1B K-12 cvo II 1ND117 OVER PRESSURE CHECK CN-1561-01.01 / c ACT 2 0.75 CK SA OIC O/C N/A eve II VALVE AROUND 1ND-36B K-12 cvo II 1NF228A GLYCOL SUPPLY CN-1558-02.00 I A ACT 2 4 GA AO 0 c c RPI 2Y OUTSIDE CONTAINMENT H-14 ISOL LTJ J FC Q FSC Q ST-C Q 1NF229 NF AHU GLY SUPPLY CN-1558-02.00 IF- A/C ACT 2 4 CK SA OIC O/C N/A eve II HOR CHECK 14 CVO II LTJ J 1NF2338 GLYCOL RET CONT ISOL CN-1558-02.00 IL- A ACT 2 4 GA MO 0 c FAI RPI 2Y 10 LTJ .J FSC Q ST-C Q

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Catawba 4 terval Stand a de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 39 of 222 Valve Summary Listing Page 39 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NF234A GLYCOL RETURN CN-1558-02.00 IL- A ACT 2 4 GA AO 0 c c RPI 2Y CONTAINMENT ISOL 12 LTJ J FC Q FSC Q ST-C Q 1NF235 NF AHU GLYCOL RETURN CN-1558-02.00 I AIC ACT 2 0.5 CK SA OIC OIC NIA eve II C/I PRESS RELIEF CHECK K-10 cvo II LTJ J 1NF895 NF AHU GLYCOL SUPPLY CN-1558-02.06 / c ACT NC 0.75 RV SA c OIC NIA RV I RELIEF G-02 1NI009A NV PMP C/L INJ ISOL CN-1562-01.00 I B ACT 2 4 GA MO c OIC FAI RPI 2Y D-09 FSC cs CSJ-CN-NI-01 FSO cs CSJ-CN-NI-01 ST-C cs CSJ-CN-NI-01 ST-0 cs CSJ-CN-NI-01 1NI010B NV PMP C/L INJ ISOL CN-1562-01.00 I B ACT 2 4 GA MO c O/C FAI RPI 2Y D-06 FSC cs CSJ-CN-NI-01 FSO cs CSJ-CN-NI-01 ST-C cs CSJ-CN-NI-01 ST-0 cs CSJ-CN-NI-01 1NI012 NV PUMPS TO COLD LEG CN-1562-01.00 IF- c ACT 2 3 CK SA OIC OIC N/A eve II CHECK 07 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 40 of 222 Valve Summary Listing Page 40 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NI015 NV PUMPS TO A COLD CN-1562-01.00 I J- c ACT 1 1.5 CK SA OIC O/C N/A eve II LEG CHECK 10 cvo II 1Nl017 NV PUMPS TO B COLD CN-1562-01.00 I J- c ACT 1 1.5 CK SA OIC OIC N/A eve II LEG CHECK 09 cvo II 1NI019 NV PUMPS TO C COLD CN-1562-01.00 I J- c ACT 1 1.5 CK SA OIC OIC NIA eve II LEG CHECK 07 cvo II 1NI021 NV PUMPS TO D COLD CN-1562-01.00 I J- c ACT 1 1.5 CK SA OIC OIC N/A eve II LEG CHECK 05 cvo II 1NI047A C-LEG ACCUM N2 SUP CN-1562-01.01 / A ACT 2 1 GL MO c c FAI RPI 2Y CONT ISOL K-09 LTJ J FSC Q ST-C Q 1NI048 COLD LEG CN-1562-01.01 / NC ACT 2 1 CK SA OIC c N/A BDO II ACCUMULATOR N2 K-08 SUPPLY CONT CHECK eve II LTJ J 1N1052 1A COLD LEG CN-1562-01.01 /I- c ACT 2 1 RV SA c OIC N/A RV I ACCUMULATOR RELIEF 03 1NI054A C-LEG ACCUM A DISCH CN-1562-01.01 IF- B ACT 1 10 GA MO 0 O/C FAI RPI 2Y ISOL 01 FSC RO ROJ-CN-NI-25 FSO RO. ROJ-CN-NI-

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Catawba _terval Standa lode ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 41 of 222 Valve Summary Listing Page 41 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NI059 1A ACCUMULATOR CN-1562-01.01 I A/C ACT 1 10 CK SA OIC OIC N/A LT 2Y DISCH CHECK D-02 eve II CVO II 1NI060 1A ACCUMULATOR CN-1562-01.01 I AIC ACT 1 10 CK SA O/C OIC N/A LT 2Y DISCH CHECK C-02 eve II cvo II 1NI063 ACCUM 18 RELIEF CN-1562-01.01 /I- c ACT 2 1 RV SA c OIC N/A RV I 05 1Nl0658 C-LEG ACCUM 8 DISCH CN-1562-01.01 IF- 8 ACT 1 10 GA MO 0 OIC FAI RPI 2Y ISOL 05 FSC RO ROJ-CN-NI-25 FSO RO ROJ-CN-NI-25 ST-C RO ROJ-CN-NI-25 ST-0 RO ROJ-CN-NI-25 1NI070 18 COLD LEG CN-1562-01.01 I A/C ACT 1 10 CK SA OIC O/C N/A LT 2Y ACCUMULATOR DISCH D-05 CHECK eve II cvo II 1Nl071 18 COLD LEG CN-1562-01.01 I A/C ACT 1 10 CK SA OIC O/C N/A LT 2Y ACCUMULATOR DISCH C-05 CHECK eve II cvo II 1Nl074 1C COLD LEG CN-1562-01.01 /I- c ACT 2 1 RV SA c OIC N/A RV I ACCUMULATOR RELIEF 08

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 42 of 222 Valve Summary Listing Page 42 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl076A C-LEG ACCUM C DISCH CN-1562-01.01 / B ACT 1 10 GA MO 0 OIC FAI RPI 2Y ISOL G-07 FSC RO ROJ-CN-NI-25 FSO RO ROJ-CN-NI-25 ST-C RO ROJ-CN-NI-25 ST-0 RO ROJ-CN-NI-25 1 NI081 1C COLD LEG CN-1562-01.01 I AIC ACT 1 10 CK SA OIC OIC NIA LT 2Y ACCUMULATOR DISCH D-07 CHECK eve II cvo II 1Nl082 1C COLD LEG CN-1562-01.01 / AIC ACT 1 10 CK SA OIC OIC NIA LT 2Y ACCUMULATOR DISCH C-07 CHECK eve II cvo II 1NI086 1D COLD LEG CN-1562-01.01 /I- c ACT 2 1 RV SA c OIC NIA RV I ACCUMULATOR RELIEF 11 1NI088B C-LEG ACCUM D DISCH CN-1562-01.01 / B ACT 1 10 GA MO 0 OIC FAI RPI 2Y ISOL G-10 FSC RO ROJ-CN-NI-25 FSO RO ROJ-CN-NI-25 ST-C RO ROJ-CN-NI-25 ST-0 RO ROJ-CN-NI-25 1NI093 1D COLD LEG CN-1562-01.01 I . AIC ACT 1 10 CK SA OIC OIC NIA LT 2Y ACCUMULATOR DISCH D-10 CHECK eve II CVO II 1NI094 1D COLD LEG CN-1562-01.01 I AIC ACT 1 .. 10 CK SA OIC OIC N/A LT 2Y ACCUMULATOR DISCH C-10

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Catawba 49terval 1: Standa9>de ISTC Catawba Nuclear Plant Interval 4 : IST 1.0.6 Page 43 of 222 Valve Summary Listing Page 43 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NI095A COLD LEG CN-1562-01.01 IF- A ACT 2 0.75 GA MO c c FAI RPI 2Y ACCUMULATOR CHECK 12 VALVE TEST ISOL LTJ J FSC Q ST-C Q 1NI0968 C-LEG ACCUM CHK VLV CN-1562-01.01 I A ACT 2 0.75 GL MO c c FAI RPI 2Y TST ISOL H-13 LTJ J FSC Q ST-C Q 1Nl1008 NI PMPS SUCT FROM CN-1562-01.02 / B ACT 2 8 GA MO 0 O/C FAI RPI 2Y FWST G-13 FSC cs CSJ-CN-NI-08 FSO cs CSJ-CN-NI-08 ST-C cs CSJ-CN-NI-08 1Nl101 FWST TO SUCTION CN-1562-01.02 I c ACT 2 8 CK SA O/C O/C N/A eve II HEADER OF NI PUMPS G-13 CHECK cvo II 1Nl102 NI PUMPS SUCTION CN-1562-01.02 / c ACT 2 1.5 RV SA c O/C N/A RV I HEADER RELIEF H-14 1Nl103A 1A NI PUMP SUCTION CN-1562-01.02 /I- B ACT 2 6 GA MO 0 OIC FAI RPI 2Y 13 FSC cs CSJ-CN-NI-24 FSO cs CSJ-CN-NI-24 ST-C cs CSJ~CN-NI-24 ST-0 cs CSJ-CN-NI-24

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 44 of 222 Valve Summary Listing Page 44 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl114 1A NI PUMP RECIRC CN-1562-01.02 /I- c ACT 2 3 CK SA OIC OIC N/A eve II CHECK 08 cvo II 1Nl115A NI PUMP 1A MINIFLOW CN-1562-01.02 / B ACT 2 2 GL MO 0 O/C FAI RPI 2Y ISOL H-08 FSC Q FSO Q ST-C Q ST-0 Q 1Nl116 1A NI PUMP DISCH CN-1562-01.02 / J- c ACT 2 4 CK SA OIC OIC NIA eve II CHECK 08 cvo II 1Nl118A NI PUMP 1A TO C-LEG INJ CN-1562-01.02 / B ACT 2 4 GA MO 0 OIC FAI RPI 2Y ISOL H-06 FSC Q FSO Q ST-C Q ST-0 Q 1Nl119 1A NI PUMP DISCH CN-1562-01.02 / c ACT 2 1.5 RV SA c OIC N/A RV I HEADER RELIEF K-06 1Nl1208 NI PMPS TO C-LEG CN-1562-01.02 /I- A ACT 2 0.75 GL MO c c FAI RPI 2Y ACCUM FILL 05 LTJ J FSC Q ST-C Q

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Catawba terval de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 45 of 222 Valve Summary Listing Page 45 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl121A 1A NI PUMP TO HOT CN-1562-01.02 I J- B ACT 2 4 GA MO c OIC FAI RPI 2Y LEGS B&C 05 FSC cs CSJ-CN-NI-21 FSO cs CSJ-CN-NI-21 ST-C cs CSJ-CN-NI-21 ST-0 cs CSJ-CN-NI-21 1Nl1228 HOT LEG INJECTION CN-1562-01.02 / J- B ACT 2 0.75 GL MO c c FAI RPI 2Y CHECK VALVE TEST ISOL 04 FSC Q ST-C Q 1Nl124 NI PUMPS TO C HOT LEG CN-1562-01.02 /I- A/C ACT 1 2 CK SA OIC OIC N/A LT 2Y CHECK 04 eve II cvo II 1Nl125 ND TO C HOT LEG CN-1562-01.02 / AIC ACT 1 8 CK SA O/C O/C N/A LT 2Y CHECK H-04 eve II cvo II 1Nl126 1C HOT LEG INJECTION CN-1562-01.02 /I- A/C ACT 1 6 CK SA OIC OIC N/A LT 2Y CHECK 01 eve II cvo II 1Nl128 NI PUMPS TO B HOT LEG CN-1562-01.02 / A/C ACT 1 2 CK SA O/C OIC N/A LT 2Y CHECK K-04 eve II cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 46 of 222 Valve Summary Listing Page 46 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl129 ND TO 8 HOT LEG CHECK CN-1562-01.02 / J- AJC ACT 1 8 CK SA OIC OIC NIA LT 2Y 03 eve II cvo II 1Nl134 18 HOT LEG INJECTION CN-1562-01.02 / AJC ACT 1 6 CK SA OIC OIC N/A LT 2Y CHECK K-01 eve II cvo II 1Nl1358 18 NI PUMP SUCTION CN-1562-01.02 / 8 ACT 2 6 GA MO 0 OIC FAI RPI 2Y E-13 FSC Q FSO Q ST-C Q ST-0 Q 1Nl1368 ND SUPPLY TO NI PUMP CN-1562-01.02 / 8 ACT 2 8 GA MO c OIC FAI RPI 2Y 18 D-13 FSC cs CSJ-CN-NI-19 FSO cs CSJ-CN-NI-19 ST-C cs CSJ-CN-NI-19 ST-0 cs CSJ-CN-NI-19 1Nl143 18 NI PUMP RECIRC CN-1562-01.02/ c ACT 2 3 CK SA OIC OIC N/A eve II CHECK E-08 cvo II 1Nl144A NI PUMP 18 MINIFLOW CN-1562-01.02 / F- 8 ACT 2 2 GL MO 0 OIC FAI RPI 2Y ISOL 08 FSC cs CSJ-CN-NI-

                                                                          "                                                          22 FSO   cs                  CSJ-CN-NI-22
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Catawba 4.terval Stand a ~de ISTC Catawba Nuclear Plant Interval 4 . IST 1.0.6 Page 47 of 222 Valve Summary Listing Page 47 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl1478 NI MINI FLOW HOR TO CN-1562-01.02 / 8 ACT 2 2 GL MO 0 OIC FAI RPI 2Y FWSTISOL G-09 FSC cs CSJ-CN-NI-09 FSO cs CSJ-CN-Nlc 09 ST-C cs CSJ-CN-NI-09 1Nl148 18 NI PUMP DISCH CN-1562-01.02 / c ACT 2 4 CK SA O/C O/C N/A eve II CHECK D-08 cvo II 1Nl1508 NI PUMP 18 C-LEG INJ CN-1562-01.02 / F- 8 ACT 2 4 GA MO 0 OIC FAI RPI 2Y ISOL 06 FSC Q FSO Q ST-C Q ST-0 Q 1Nl151 18 NI PUMP DISCH CN-1562-01.02/ c ACT 2 1.5 RV SA c OIC N/A RV I RELIEF E-06 1Nl1528 NI PUMP 18 TO H-LEGS CN-1562-01.02 / 8 ACT 2 4 GA MO c OIC FAI RPI 2Y A&D D-05 FSC cs CSJ-CN-NI-21 FSO cs CSJ-CN-NI-21 ST-C cs CSJ-CN-NI-21 ST-0 cs CSJ-CN-NI-21 1Nl153A HOT LEG INJECTION CN-1562-01.02 / 8 ACT 2 0.75 GL MO c c FAI RPI 2Y CHECK VALVE TEST ISOL D-04 FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 48 of 222 Valve Summary Listing Page 48 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl154B ND TO HOT LEGS CHECK CN-1562-01.02 / B ACT 2 12 GL MO c c FAI RPI 2Y VALVE TEST ISOL H-03 FSC Q ST-C Q 1Nl156 1B NI PUMP TO HOT LEG CN-1562-01.02/ A/C ACT 1 6 CK SA OIC O/C N/A LT 2Y D CHECK E-03 eve II cvo II 1Nl157 1A HOT LEG INJECTION CN-1562-01.02 / AIC ACT 1 2 CK SA OIC O/C N/A LT 2Y CHECK E-01 eve II cvo II 1Nl159 1B NI PUMP TO HOT LEG CN-1562-01.02 / AIC ACT 1 2 CK SA O/C O/C N/A LT 2Y D CHECK C-02 eve II cvo II 1Nl160 1D HOT LEG INJECTION CN-1562-01.02 / A/C ACT 1 6 CK SA OIC OIC N/A LI 2Y. CHECK C-01 eve II cvo II 1Nl161 NI TO COLD LEGS RELIEF CN-1562-01.03 / c ACT 2 1.5 RV SA c OIC N/A RV I K-07 1Nl162A NI TO C-LEGS INJ HDR CN-1562-01.03 / J- A ACT 2 4 GA MO 0 O/C FAI RPI 2Y ISOL 08 LT 2Y FSC cs CSJ-CN-NI-12 FSO cs CSJ-CN-NI-12 ST-C cs CSJ-CN-NI-12

Catawba terval Standa' de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 49 of 222 Valve Summary Listing Page 49 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ ~LASS SIZE TYPE ACT POSITION TEST' FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL

1Nl165 COLD LEG DISCH CN-1562-01.03 / AJC ACT 1 2 CK SA OIC O/C N/A L-T 2Y HEADER TO COLD LEG A G-03 CHECK eve II cvo II 1Nl167 COLD LEG DISCH CN-1562-01.03/ AJC ACT 1 2 CK SA OIC OIC N/A LT 2Y HEADER TO COLD LEG B G-06 CHECK

      -                                                                                               eve    II cvo    II 1Nl169 COLD LEG DISCH         CN-1562-01.03 /  AJC  ACT   1       2   CK    SA   OIC   O/C     N/A   LT   2Y HEADER TO COLD LEG D         G-09 CHECK eve    II cvo    II 1Nl171 COLD LEG DISCH          CN-1562-01.03 I AJC  ACT   1       2   CK    SA   OIC   OIC     N/A   LT   2Y HEADER TO COLD LEG C         G-12 CHECK eve     II cvo     II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 50 of 222 Valve Summary Listing Page 50 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl173A ND HEADER 1A TO COLD CN-1562-01.03/ A ACT 2 8 GA MO, 0 OIC FAI RPI 2Y LEGS C & D E-10 LT 2Y FSC cs CSJ-CN-NI-15 FSO cs CSJ-CN-NI-15 ST-C cs CSJ-CN-NI-15 ST-0 cs CSJ-CN-NI-15 1N1175 ND HOR 1A TO CC-LEG CN-1562-01.03 / F- AIC ACT 1 6 CK SA OIC OIC NIA LT 2Y CHK 11 eve II cvo II 1Nl176 1A ND HEADER TOD CN-1562-01.03 / F- AIC ACT 1 6 CK SA OIC OIC NIA LT 2Y COLD LEG CHECK 09 eve II cvo II 1Nl178B ND HOR 1B TO COLD CN-1562-01 .'03 / A ACT 2 8 GA MO 0 OIC FAI RPI 2Y LEGS A&B E-04 LT 2Y FSC cs CSJ-CN-NI-15 FSO cs CSJ-CN-NI-15 ST-C cs CSJ-CN-NI-15 ST-0 cs CSJ-CN-NI-15

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Catawba 4Wterval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 51 of 222 Valve Summary Listing Page 51 of 222 VALVE ID FUNCTION DRAWING/COOR . CAT .ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl180 1B ND HEADER TO B CN-1562-01.03 / F- AIC ACT 1 6 CK SA OIC OIC N/A LT 2Y COLD LEG CHECK 05 eve II cvo II 1Nl181 1B ND HEADER TO A CN-1562-01.03 / F- A/C ACT 1 6 CK SA OIC OIC N/A LT 2Y COLD LEG CHECK 04 eve II cvo II 1Nl183B ND HOR A&B HOT LEG CN-1562-01.02 / A ACT 2 12 GA MO c OIC FAI RPI 2Y INJ ISOL G-04 LT 2Y FSC cs CSJ-CN-NI-16 FSO cs CSJ-CN-NI-

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                                                                                                                              ,16 ST-0  cs                   CSJ-CN-NI-16 1Nl184B ND PUMP 1B CONT SUMP    CN-1562-01.03 /    B   ACT 2     18   GA   MO     c    OIC     FAI   RPI   2Y SUCT                         C-10 FSC   cs                   CSJ-CN-NI-17 FSO   cs                   CSJ-CN-NI-17 ST-C  cs                   CSJ-CN-NI-17 ST-0  cs                   CSJ-CN-NI-17

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 52 of 222 Valve Summary Listing Page 52 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl185A ND PUMP 1A CONT SUMP CN-1562-01.03/ B ACT 2 18 GA MO c OIC FAI RPI 2Y SUCT C-05 FSC cs CSJ-CN-NI-17 FSO cs CSJ-CN-NI-17 ST-C cs CSJ-CN-NI-17 ST-0 cs CSJ-CN-NI-17 1N1332A NI PUMP SUCT X-OVER CN-1562-01.02 / L- B ACT 2 6 GA MO c OIC FAI RPI 2Y FROM ND 12 FSC cs CSJ-CN-NI-18 FSO cs CSJ-CN-NI-18 ST-C cs CSJ-CN-NI-18 ST-0 cs CSJ-CN-NI-18 1Nl333B NI PUMP SUCT FROM ND CN-1562-01.02 / B ACT 2 6 GA MO c OIC FAI RPI 2Y K-12 FSC cs CSJ-CN-NI-18 FSO cs CSJ-CN-NI-18 ST-C cs CSJ-CN-NI-18 ST-0 cs CSJ-CN-NI-18 I;~

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Catawba terval Standa' 'ode ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 53 of 222 Valve Summary Listing Page .53 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl334B NI PUMP SUCT X-OVER CN-1562-01.02 / B ACT 2 6 GA MO 0 O/C FAI RPI 2Y FROM ND K-11 FSC cs CSJ-CN-NI-23 FSO cs CSJ-CN-NI-23 ST-C cs CSJ-CN-NI-23 ST-0 cs CSJ-CN-NI-23 1Nl342 ND TO SUCTION OF 1B NI CN-1562-01.02/ c ACT 2 8 CK SA OIC O/C N/A eve II PUMP CHECK D-13 cvo II 1Nl351 NV PUMPS TO A COLD CN-1562-01.00 /I- c ACT 1 1.5 CK SA O/C OIC N/A eve II LEG CHECK 10 cvo II 1Nl352 NV PUMPS TO B COLD CN-1562-01.00 /I- c ACT 1 1.5 CK SA OIC OIC N/A eve II LEG CHECK 09 cvo II 1Nl353 NV PUMPS TO C COLD CN-1562-01.00 /I- c ACT 1 1.5 CK SA OIC OIC NIA eve II LEG CHECK 07 cvo II 1Nl354 NV PUMPS TO D COLD CN-1562-01.00 /I- c ACT 1 1.5 CK SA OIC OIC N/A eve II LEG CHECK 05 cvo II 1Nl391 1A COLD LEG INJ CHECK CN-1562-01.01 / A PASS 2 0.75 GL AO c c c LT 2Y VALVE TEST !SOL C-03 1Nl392 18 COLD LEG INJECTION CN-1562-01.01 / A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL C-04 1Nl393 1C COLD LEG INJECTION CN-1562-01.01 I A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL C-08 1Nl394 1D COLD LEG INJECTION CN-1562-01.01 / A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL C-11

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 54 of 222 Valve Summary Listing Page 54 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl395 1A HOT LEG INJ CHECK CN-1562-01.02 / A PASS 2 0.75 GL AO c c c LT 2Y VALVE TEST ISOL E-01 1N1396 18 HOT LEG INJECTION CN-1562-01.02 / A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL K-01 1Nl397 1C HOT LEG INJECTION CN-1562-01.02 /I- A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL 01 1Nl398 1 D HOT LEG INJECTION CN-1562-01.02 / A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL C-01 1Nl438A EMER N2 FROM CLA A TO CN-1562-01.01 I B ACT 2 1 GL MO c OIC FAI RPI 2Y 1NC-34A K-01 FSC Q FSO Q ST-C Q ST-0 Q 1Nl439B EMER N2 FROM CLA B TO CN-1562-01.01 I B ACT 2 1 GL MO c OIC FAI RPI 2Y 1NC-32B K-05 FSC Q FSO Q ST-C Q ST-0 Q 1Nl471 COLD LEG CN-1562-01.01 IF- NC ACT 2 0.75 CK SA O/C O/C N/A eve II ACCUMULATOR CHECK 13 VALVE TEST ISOL BYPASS CHECK cvo II LTJ J 1Nl481 CONTAINMENT CN-1562-01.01 / c ACT NC 0.75 RV SA c O/C N/A RV I PENETRATION M-322 D-12 t.n; RELIEF

Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 55 of 222 Valve Summary Listing Page 55 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl485 NI PUMPS TO COLD LEG CN-1562-01.03 / A/C ACT 2 1 CK SA O/C O/C N/A eve II VENT CHECK H-07 cvo II LTJ J 1Nl495 18 ND HEADER PRESS CN-1562-01.03 / A/C ACT 2 0.5 CK SA O/C OIC N/A eve II RELIEF LINE CHECK E-05 cvo II LTJ J 1Nl501 1A ND HEADER PRESS CN-1562-01.03 / A/C ACT 2 0.5 CK SA O/C O/C N/A eve II RELIEF LINE CHECK E-09 cvo II LTJ J 1Nl515 1A ECCS SUMP PIPING CN-1562-01.03 / A PASS 2 1 GL MA c c N/A LTJ J DRAIN FIRST ISOL C-05 1Nl516 1A ECCS SUMP PIPING CN-1562-01.03/ A PASS 2 GL MA c c N/A LTJ J DRAIN SECOND ISOL 8-05 1Nl517 1A ECCS SUMP PIPING CN-1562-01.03 / A PASS 2 1 GL MA c c N/A LTJ J VENT FIRST ISOL C-06 1Nl518 1A ECCS SUMP PIPING CN-1562-01.03 / A PASS 2 GL MA c c N/A LTJ J VENT SECOND ISOL 8-06 1Nl519 1Nl185A RESERVOIR CN-1562-01.03/ A PASS 2 GL MA c c N/A LTJ J DRAIN FIRST ISOL A-06 1Nl520 1Nl185A RESERVOIR CN-1562-01.03 / A PASS 2 GL MA c c N/A LTJ J DRAIN SECOND ISOL A-06 1Nl521 1NI185A RESERVOIR CN-1562-01.03 / A PASS 2 GL MA c c NIA LTJ J VENT FIRST ISOL 8-06 1Nl522 1Nl185A RESERVOIR CN-1562-01.03 / A PASS 2 GL MA c c N/A LTJ J VENT SECOND ISOL 8-07 1Nl523 18 ECCS SUMP PIPING CN-1562-01.03 / A PASS 2 1 GL MA c c N/A LTJ J DRAIN FIRST ISOL C-10 1Nl524 18 ECCS SUMP PIPING CN-1562-01.03/ A PASS 2 GL MA c c N/A LTJ J DRAIN SECOND ISOL C-10 1Nl525 18 ECCS SUMP PIPING CN-1562-01.03 / A PASS 2 1 GL MA c c N/A LTJ J VENT FIRST ISOL C-09 1Nl526 18 ECCS SUMP PIPING CN-1562-01.03 / A PASS 2 GL MA c c N/A LTJ J VENT SECOND ISOL 8-09

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 56 of 222 Valve Summary Listing Page 56 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Nl527 1Nl1848 RESERVOIR CN-1562-01.03 / A PASS 2 GL MA c c N/A LTJ J DRAIN FIRST ISOL 8-12 1Nl528 1Nl1848 RESERVOIR CN-1562-01.03 / A PASS 2 GL MA c c N/A LTJ J DRAIN SECOND ISOL 8-12 1Nl529 1Nl1848 RESERVOIR CN-1562-01.03 / A PASS 2 GL MA c c N/A LTJ J VENT FIRST ISOL 8-10 1Nl530 1Nl1848 RESERVOIR CN-1562-01.03 / A PASS 2 1 GL MA c c N/A LTJ J VENT SECOND ISOL 8-10 1Nl532 1D CLA CHECK VALVE CN-1562-01.03 / A/C ACT 2 0.5 CK SA OIC OIC N/A eve II VENT LINE CHECK G-10 cvo II LTJ J 1Nl537 1A CLA CHECK VALVE CN-1562-01.03/ A/C ACT 2 0.5 CK SA OIC O/C N/A eve II VENT LINE CHECK G-04 cvo II LTJ J 1NM003A PZR LIQ SMPL LINE CONT CN-1572-01.00 I A ACT 2 0.5 GL MO c c FAI RPI 2Y ISOL K-03 LTJ J FSC Q ST-C Q 1NM006A PZR STEAM SAMPLE CN-1572-01.00 I J- A ACT 2 0.5 GL MO c c FAI RPI 2Y LINE CONTAINMENT ISOL 03 LTJ J FSC Q ST-C Q 1NM0078 PZR SMPL HDR CONT CN-1572-01.00 I A ACT 2 0.5 GL MO c c FAI RPI 2Y ISOL K-6 LTJ J FSC Q ST-C Q

Catawba terval Standa_.ode ISTC

Catawba Nuclear Plant Interval 4 . IST 1.0.6 Page 57 of 222 Valve Summary Listing Page 57 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NM022A 1A HOT LEG SAMPLE CN-1572-01.00 I J- A ACT 2 0.5 GL MO 0 c FAI RPI 2Y CONTAINMENT ISOL 12 LTJ J FSC Q ST-C Q 1NM025A 1C HOT LEG SAMPLE

CN-1572-01.00/ A ACT 2 0.5 GL MO c c FAI RPI 2Y CONTAINMENT ISOL K-12 LTJ J FSC Q ST-C Q 1NM026B HOT LEG SMPL HOR CN-1572-01.00 I A ACT 2 0.5 GL MO 0 c FAI RPI 2Y CONT ISOL K-8 LTJ J FSC Q ST-C Q 1NM069 UNIT 1 NI ACCUMULATOR CN-1572-01.01 / AIC ACT 2 0.75 RV SA c OIC N/A RV I SAMPLE LINE RELIEF G-10 LTJ J 1NM072B 1A ACCUMULATOR CN-1572-01.01 / I- A ACT 2 0.75 GL MO c c FAI RPI 2Y SAMPLE LINE 06 CONTAINMENT ISOL LTJ J FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 58 of 222 Valve Summary Listing Page 58 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NM075B 18 ACCUMULATOR CN-1572-01.01 /I- A ACT 2 0.75 GL MO c c FAI RPI 2Y SAMPLE LINE 08 CONTAINMENT ISOL LTJ J FSC Q ST-C Q 1NM078B 1C ACCUMULATOR CN-1572-01.01 / I- A ACT 2 0.75 GL MO c c FAI RPI 2Y SAMPLE LINE 10 CONTAINMENT ISOL LTJ J

                                              .                                                                         FSC   Q ST-C  Q 1NM081B        1D ACCUMULATOR                   CN-1572-01.01 /I-   A   ACT   2      0.75    GL  MO    c    c      FAI  RPI  2Y SAMPLE LINE                             11 CONTAINMENT ISOL LTJ  J FSC   Q ST-C  Q 1NM082A        ACCUMSMPLHDRCONT                  CN-1572-01.01 /    A   ACT   2      0.75    GL  MO    c    c      FAI  RPI  2Y ISOL                                   E-09 LTJ  J FSC   Q ST-C  Q
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Catawba 491erval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 59 of 222 Valve Summary Listing Page 59 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NM187A 1A SIG UPPER SHELL CN-1572-01.04/ S ACT 2 0.5 GL MO c c FAI RPI 2Y SAMPLE CONTAINMENT K-01 ISOL FSC Q ST-C Q 1NM190A 1A S/G SLOWDOWN CN-1572-01.04 / S ACT 2 0.5 GL MO 0 c FAI RPI 2Y SAMPLE CONTAINMENT K-02

         !SOL                                                                                          FSC    Q ST-C  Q 1NM191S  1A SIG SAMPLE HEADER   CN-1572-01.04 / I-  S   ACT   2      0.5  GL   MO     c    c      FAI   RPI  2Y CONTAINMENT ISOL              02 FSC    Q ST-C  Q 1NM197S  1S S/G UPPER SHELL      CN-1572-01.04/     S   ACT   2      0.5  GL   MO     c    c      FAI   RPI  2Y SAMPLE CONTAINMENT           K-05
          !SOL FSC    Q ST-C  Q 1NM200S   1S S/G SLOWDOWN        CN-1572-01.04 /    S   ACT   2      0.5  GL    MO    0    c      FAI   RPI  2Y SAMPLE CONTAINMENT          K-06 ISOL                                                                                          FSC    Q ST-C  Q 1NM201A   1S SIG SAMPLE HEADER  CN-1572-01.04 /I-   S   ACT   2      0.5  GL    MO    c    c      FAI   RPI  2Y CONTAINMENT ISOL             06 FSC    Q ST-C  Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 60 of 222 Valve Summary Listing Page 60 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NM207A 1 C SIG UPPER SHELL CN-1572-01.04/ S ACT 2 0.5 GL MO c c FAI RPI 2Y SAMPLE CONTAINMENT K-08 ISOL FSC Q ST-C Q 1NM210A 1 C SIG SLOWDOWN CN-1572-01.04 / S ACT 2 0.5 GL MO 0 c FAI RPI 2Y SAMPLE CONTAINMENT K-09 ISOL FSC Q ST-C Q 1NM211S 1 C SIG SAMPLE HEADER CN-1572-01.04 /I- S ACT 2 0.5 GL MO c c FAI RPI 2Y CONTAINMENT ISOL 09 FSC Q ST-C Q 1NM217S 1D SIG UPPER SHELL CN-1572-01.04 / S ACT 2 0.5 GL MO c c FAI RPI 2Y SAMPLE CONTAINMENT K-11 ISOL FSC Q ST-C Q 1NM220S 1 D SIG SLOWDOWN CN-1572-01.04 / S ACT 2 0.5 GL MO 0 c FAI RPI 2Y SAMPLE CONTAINMENT K-12 ISOL FSC Q ST-C Q 1NM221A 1D SIG SAMPLE HEADER CN-1572-01.04 /I- S ACT 2 0.5 GL MO c c FAI RPI 2Y CONTAINMENT ISOL 12 FSC Q ST-C Q t

Catawba 41 terval Stand a' de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 61 of 222 Valve Su_mmary Listing Page 61 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NM424 PZR SAMPLE LINE CN-1572-01.00 / I- A/C ACT 2 0.5 CK SA OIC OIC N/A eve II BYPASS CHECK 03 cvo II LTJ J 1NM425 1C HOT LEG SAMPLE CN-1572-01.00 I A/C ACT 2 0.5 CK SA OIC OIC NIA eve II CONTAINMENT ISOL K-12 BYPASS CHECK cvo II LTJ J

1NM426 1A S/G SAMPLE CN-1572-01.04 / c ACT 2 0.5 CK SA O/C O/C N/A eve II CONTAINMENT ISOL K-02 BYPASS CHECK cvo II 1NM427 1 B SIG SLOWDOWN CN-1572-01.04 / c ACT 2 0.5 CK SA OIC O/C N/A eve II SAMPLE CONTAINMENT K-05 ISOL BYPASS CHECK cvo II 1NM428 1C S/G UPPERSHELL CN-1572-01.04 / c ACT 2 0.5 CK SA O/C OIC N/A eve II SAMPLE CONTAINMENT K-09 ISOL BYPASS CHECK ' cvo II 1NM429 1 D S/G UPPERS HELL CN-1572-01.04 / c ACT 2 0.5 CK SA OIC OIC N/A eve II SAMPLE CONTAINMENT K-12 ISOL BYPASS CHECK cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 62 of 222 Valve Summary Listing Page 62 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NS0018 NS PMP 8 SUCT FROM CN-1563-01.00 I B .ACT 2 12 GA MO c OIC FAI RPI 2Y CONT SUMP C-13 FSC Q FSO Q ST-C Q ST-0 Q 1NS002 1B NS PUMP SUCTION CN-1563-01.00 I c ACT 2 0.75 RV SA c OIC N/A RV I RELIEF 8-13 1NS003B NSPUMP1BSUCTFROM CN-1563-01.00 I B ACT 2 12 GA MO 0 c FAI RPI 2Y FWST E-13 FSC Q ST-C Q 1NS004 FWST TO 1B NS PUMP CN-1563-01.00 I c ACT 2 12 CK SA OIC O/C N/A eve II SUCTION CHECK E-13 cvo II 1NS0128 NS SPRA¥ HOR 1B CONT CN-1563-01.00 I A ACT 2 8 GA MO c OIC FAI LT 2Y ISOL C-05 RPI 2Y FSC Q FSO Q

                                             -                                                       ST-C   Q ST-0   Q 1NS013     1 B NS SPRAY HEADER  CN-1563-01.00/   c   ACT   2       8    CK   SA   OIC   OIC    N/A   eve    II CHECK                     C-03 cvo    II
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Catawba 4,91erval Standa 'de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 63 of 222 Valve Summary Listing Page 63 of 222 VALVE ID FUNCTION DRAWING/COOR CAT .ACT/ CLASS . SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NS0158 NS SPRAY HOR 18 CONT CN-1563-01,00/ A ACT 2 8 GA MO c O/C FAI LT 2Y ISOL E-05 RPI 2Y FSC Q FSO Q ST-C Q ST-0 Q 1NS016 18 NS SPRAY HEADER CN-1563-01,00 I c ACT 2 8 CK SA O/C O/C N/A eve II CHECK E-03 cvo II 1NS018A NS PMP A SUCT FROM CN-1563-01.00 I 8 ACT 2 12 GA MO c OIC FAI RPI 2Y CONT SUMP K-13 FSC Q FSO Q ST-C Q ST-0 Q 1NS019 1A NS PUMP SUCTION CN-1563-01.00 I c ACT 2 0.75 RV SA c O/C N/A RV I RELIEF K-13 1NS020A NS PUMP 1A SUCT FROM CN-1563-01,00 /I- 8 ACT 2 12 GA MO 0 c FAI RPI 2Y FWST 13 FSC Q ST-C Q 1NS021 FWST TO 1A NS PUMP CN-1563-01.00 /I- c ACT 2 12 CK SA OIC OIC N/A eve II SUCTION CHECK 13 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 64 of 222 Valve Summary Listing Page 64 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NS029A NS SPRAY HOR 1A CONT CN-1563-01.00 /I- A ACT 2 8 GA MO c OIC FAI LT 2Y ISOL 05 RPI 2Y FSC Q FSO Q ST-C Q ST-0 Q 1NS030 1A NS SPRAY HEADER CN-1563-01.00 /I- c ACT 2 8 CK SA O/C OIC N/A eve II CHECK 03 cvo II 1NS032A NS SPRAY HOR 1A CONT CN-1563-01.00 I A ACT 2 8 GA MO c OIC FAI LT 2Y ISOL K-05 RPI 2Y FSC Q FSO Q ST-C Q ST-0 Q 1NS033 1A NS SPRAY HEADER CN-1563-01.00 I c ACT 2 8 CK SA OIC OIC N/A eve II CHECK K-03 cvo II 1NS038B 18 ND PUMP TO CN-1563-01.00 I F- A ACT 2 8 GA MO c c FAI LT 2Y CONTAINMENT SPRAY 05 HEADER RPI 2Y FSC cs CSJ-CN-NS-03 ST-C cs CSJ-CN-NS-03 1NS041 1B ND TO NS SPRAY CN-1563-01.00 IF- c ACT 2 8 CK SA O/C OIC N/A eve II HEADER CHECK 03 cvo II J.. ..-!..

Catawba terval Standa1 iode ISTC Catawba Noclear Plant Interval 4 IST 1.0.6 Page 65 of 222 Valve Summary Listing Page *65 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NS043A 1A ND PUMP TO CN-1563-01.00 I A ACT 2 8 GA MO c c FAI LT 2Y CONTAINMENT SPRAY H-05 HEADER RPI 2Y FSC cs CSJ-CN-NS-03 ST-C cs CSJ-CN-NS-03 1NS046 1A ND TO NS SPRAY CN-1563-01.00/ c ACT 2 8 CK SA O/C OIC N/A eve II HEADER CHECK H-03 cvo II 1NS098 1A NS PUMP DISCH CN-1563-01.00 I J- *c ACT 2 10 CK SA OIC OIC N/A eve II CHECK 09 CVO II 1NS099 18 NS PUMP DISCH CN-1563-01.00 I c ACT 2 10 CK SA OIC OIC N/A eve II CHECK D-09 cvo II 1NV001A NC LETDOWN TO REGEN CN-1554-01.00 I 8 ACT 1 3 GA AO 0 c c RPI 2Y HX ISOL H-01 FC cs CSJ-CN-NV-12 FSC cs CSJ-CN-NV-12 ST-C cs CSJ-CN-NV-12 1NV002A NC LETDOWN TO REGEN CN-1554-01.00 I 8 ACT 1 1 GA AO 0 c c RPI 2Y HX ISOL H-02 FC cs CSJ-CN-NV-12 FSC cs CSJ-CN-NV-12 ST-C cs CSJ-CN-NV-12

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 66 of 222 Valve Summary Listing Page 66 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NV010A LETDOWN ORIFICE 18 CN-1554-01.00/ A ACT 2 2 GA AO 0 c c LT 2Y OUTLET CONT ISOL H-09 RPI 2Y FC cs CSJ-CN-NV-11 FSC cs CSJ-CN-NV-11 ST-C cs CSJ-CN-NV-11 1NV011A LETDOWN ORIFICE 1C CN-1554-01.00 /I- A ACT 2 2 GA AO OIC c c LT 2Y OUTLET CONT ISOL 09 RPI 2Y FC cs CSJ-CN-NV-11 FSC cs CSJ-CN-NV-11 ST-C cs CSJ-CN-NV-

                                                       .                                                                                         11 1NV013A            LETDOWN ORIFICE 1A            CN-1554-01.00 I    A   ACT   2      2    GA  AO      0     c      c     LT   2Y OUTLET CONT ISOL                   G-09 RPI   2Y FC  cs                  CSJ-CN-NV-11 FSC  cs                  CSJ-CN-NV-11 ST-C  cs                  CSJ-CN-NV-11 1NV014            LETDN ORIF HOR RELIEF         CN-1554-01.00 I   A/C  ACT   2      3    RV   SA     c    O/C    N/A    RV    I G-10 LTJ    J
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Catawba 41 terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 67 of 222 Valve Summary Listing Page 67 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NV015B LETDN CONT ISOL CN-1554-01.00/ A ACT 2 3 GL MO 0 c FAI RPI 2Y H-12 FSC cs CSJ-CN-NV-01 ST-C cs CSJ-CN-NV-01 LTJ J 1NV022 CONT ISOL CHECK CN-1554-01.00 IF- c ACT 2 3 CK SA OIC OIC N/A eve II 04 cvo II 1NV033 NV CHARGING TO LOOP CN-1554-01.00/ c ACT 1 3 CK SA O/C OIC N/A eve II A CHECK K-11 cvo II 1NV034 NV CHARGING TO LOOP CN-1554-01.00/ c ACT 1 3 CK SA O/C O/C N/A eve II A CHECK K-11 cvo II 1NV036 NV CHARGING TO NC CN-1554-01.00 I J- c ACT 2 0.75 CK SA c 0 N/A BDC II LOOP D BYP CHECK 04 cvo II 1NV037A NV SUP TO PZR AUX CN-1554-01.00 IL- B PASS 1 2 GL MO c c FAI RPI 2Y SPRAY 08 1NV038 NV SUPPLY TO PZR AUX CN-1554-01.00 IL- c ACT 1 2 CK SA OIC c N/A BDO II SPRAY CHECK 11 eve II 1NV040 NV CHARGING TO LOOP CN-1554-01.00 I c ACT 1 3 CK SA OIC O/C N/A eve II D CHECK K-03 cvo II 1NV041 NV CHARGING TO LOOP CN-1554-01.00 I c ACT 1 3 CK SA OIC O/C N/A eve II D CHECK K-02 CVO II 1NV044A NC PMP A SEAL SUPPLY CN-1554-01.05 / J- B PASS 2 2 GL MO 0 0 FAI RPI 2Y CONT ISOL 04 1NV046 NC PUMP 1A SEAL CN-1554-01.05 / J- c ACT 2 2 CK SA OIC O/C N/A eve II SUPPLY CONT ISOL 05 CHECK cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 68 of 222 Valve Summary Listing Page 68 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NV049 1A NC PUMP SEAL CN-1554-01.05 / J- c ACT 1 2 CK SA OIC O/C N/A eve II SUPPLY INSIDE CHECK 07 cvo II 1NV055A NC PMP B SEAL SUPPLY CN-1554-01.05 / B PASS 2 2 GL MO 0 0 FAI RPI 2Y CONT ISOL H-04 1NV057 1 B NC PUMP SEAL CN-1554-01.05 / c ACT 2 2 CK SA O/C OIC N/A eve II SUPPLY INSIDE CHECK H-05 cvo II 1NV060 1 B NC PUMP SEAL CN-1554-01.05/ c ACT 1 2 CK SA OIC O/C N/A eve II SUPPLY INSIDE CHECK H-07 cvo II 1NV066A NC PMP C SEAL SUPPLY CN-1554-01.05 IF- B PASS 2 2 GL MO 0 0 FAI RPI 2Y

          *CONT ISOL                   04 1NV068    1 C NC PUMP SEAL     CN-1554-01.05 / F-  c   ACT   2      2      CK   SA  OIC   O/C     NIA  eve    II SUPPLY INSIDE CHECK         05 cvo    II 1NV071    1C NC PUMP SEAL      CN-1554-01.05 / F-  c   ACT   1      2      CK   SA  O/C   OIC     N/A  eve    II SUPPLY INSIDE CHECK         07 cvo    II 1NV077A    NC PMP D SEAL SUPPLY  CN-1554-01.05/     B  PASS   2      2      GL  MO    0     0      FAI   RPI  2Y CONT ISOL                  D-04 1NV079    NC PUMP 1D SEAL       CN-1554-01.05 /    c   ACT   2      2      CK   SA  O/C   OIC     N/A  eve    II SUPPLY INSIDE CHECK        D-05 cvo     II 1NV082    1D NC PUMP SEAL       CN-1554-01.05/     c   ACT   1      2      CK   SA  OIC   OIC     N/A  eve     II SUPPLY INSIDE CHECK        D-07 cvo     II 1NV087    NC PUMPS SEAL*        CN-1554-01.00 I    c   ACT   2      3      RV   SA   c    O/C     N/A   RV   I RETURN HOR INSIDE          C-08 RELIEF
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Catawba 41 terval Stand a 'Ode ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 69 of 222 Valve Summary Listing Page 69 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NV089A NC PUMPS SEAL CN-1554-01.00 I A ACT 2 4 GA MO 0 c FAI LT 2Y RETURN CONT ISOL B-10 RPI 2Y FSC cs CSJ-CN-NV-02 ST-C cs CSJ-CN-NV-02 1NV090 NC PUMPS SEAL CN-1554-01.00/ NC ACT 2 0.75 CK SA O/C OIC N/A eve II RETURN CONT ISOL D-10 RELIEVING CHECK cvo II LTJ J 1NV091B NC PMPS SEAL RET CN-1554-01.00/ A ACT 2 4 GA MO 0 c FAI LT 2Y CONT ISOL B-13 . RPI 2Y FSC cs CSJ-CN-NV-02 ST-C cs CSJ-CN-NV-02 1NV122B LOOP C TO EXS CN-1554-01.00 I B PASS 1 1 GL AO c c c RPI 2Y LETDOWN HX ISOL D-12 1NV123B LOOP C TO EXS CN-1554-01.00 I B PASS 1 1 GL AO c c c RPI 2Y LETDOWN HX ISOL D-10 1NV188A VCT OUTLET ISOL CN-1554-01.01 / B ACT 2 4 GA MO 0 c FAI RPI 2Y C-05 FSC cs CSJ-CN-NV-03 ST-C cs CSJ-CN-NV-03 1NV189B VCT OUTLET ISOL CN-1554-01.01 I B ACT 2 4 GA MO 0 c FAI RPI 2Y C-04 FSC cs CSJ-CN-NV-. 03 ST-C cs CSJ-CN-NV-03

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 70 of 222 Valve Summary Listing Page 70 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NV202B NV PMPS A & B RECIRC CN-1554-01.06 / B ACT 2 2 GL MO 0 O/C FAI RPI 2Y ISOL D-01 FSC cs CSJ-CN-NV-07 FSO cs CSJ-CN-NV-07 ST-C cs CSJ-CN-NV-07 ST-0 cs CSJ-CN-NV-07 1NV203A NV PUMPS A&B RECIRC CN-1554-01.06 / B ACT 2 2 GL MO 0 O/C FAI RPI 2Y ISOL D-02 FSC cs CSJ-CN-NV-07 FSO cs CSJ-CN-NV-07 ST-C cs CSJ-CN-NV-07 ST-0 cs CSJ-CN-NV-07 1NV220 SEAL WATER RETURN CN-1554-01.01 / c ACT 2 3 CK SA OIC c N/A BOO II TO VCT CHECK G-04 eve II 1NV223 VCT RELIEF TO RHT CN-1554-01.01 I c ACT 2 4 RV SA c OIC N/A RV I H-07 1NV236B BORIC ACID TO NV CN-1554-01.07 IF- B PASS 2 2 GL MO c c FAI RPI 2Y PUMPS SUCT 12 1NV252A NV PUMPS SUCT FROM CN-1554-01.07 / B ACT 2 8 GA MO c OIC FAI RPI 2Y FWST K-11 FSC cs CSJ-CN-NV-

                                                                                               .                                        10 FSO  cs                      CSJ-CN-NV-10 ST-C  cs                      CSJ-CN-NV-10 ST-0  cs                      CSJ-CN-NV-10
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Catawba 491erval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 71 of 222 Valve Summary Listing Page 71 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NV2538 NV PUMPS SUCT FROM CN-1554-01.07 I 8 ACT 2 8 GA MO c O/C FAI RPI 2Y FWST K-12 FSC cs CSJ-CN-NV-10 FSO cs CSJ-CN-NV-10 ST-C cs CSJ-CN-NV-10 ST-0 cs CSJ-CN-NV-10 1NV254 1A & 18 NV PUMPS CN-1554-01.07 I c ACT 2 8 CK SA c OIC N/A eve II SUPPLY CHECK K-12 cvo II 1NV268 1A NV PUMP MINI-FLOW CN-1554-01.07 /I- c ACT 2 2 CK SA O/C O/C N/A eve II CHECK 05 cvo II 1NV270 1A NV PUMP DISCH CN-1554-01.07 /I- c ACT 2 4 CK SA OIC OIC N/A eve II CHECK 05 cvo II 1NV273 1A & 18 NV PUMPS CN-1554-01.07 I E c ACT 2 1.5 RV SA c OIC N/A RV I SUCTION HEADER 12 RELIEF 1NV288 18 NV PUMP MINI- FLOW CN-1554-01.07 / c ACT 2 2 CK SA O/C OIC N/A eve II CHECK E-05 cvo II 1NV290 18 NV PUMP DISCH CN-1554-01.07 / c ACT 2 4 CK SA OIC OIC N/A eve II CHECK D-05 cvo II 1NV312A CHRG LINE CONT ISOL CN-1554-01.02 / 8 ACT 2 3 GA MO 0 c FAI RPI 2Y K-05 FSC cs CSJ-CN-NV-04 ST-C cs CSJ-CN-NV-04 1NV3148 CHRG LINE CONT ISOL CN-1554-01.02/ 8 ACT 2 3 GA MO 0 c FAI RPI 2Y K-06 FSC cs CSJ-CN-NV-04 ST-C cs CSJ-CN-NV-04

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 72 of 222 Valve Summary Listing Page 72 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NV492 1A NC PUMP SEAL CN"1554-01.05 / J- c ACT 1 2 CK SA OIC O/C N/A eve II SUPPLY INSIDE CHECK 07 cvo II 1NV493 1 B NC PUMP SEAL CN-1554-01.05/ c ACT 1 2 CK SA OIC OIC N/A eve II SUPPLY INSIDE CHECK H-07 cvo II 1NV494 1C NC PUMP SEAL CN-1554-01.05 / F- c ACT 1 2 CK SA O/C OIC N/A eve II SUPPLY INSIDE CHECK 07 cvo II 1NV495 1D NC PUMP SEAL CN-1554-01.05 / c ACT 1 2 CK SA OIC OIC N/A eve II SUPPLY INSIDE CHECK D-07 cvo II 1NV813 ND PUMP DISCH TO NI CN-1554-01.07 / c ACT 2 8 CK SA OIC OIC N/A eve II PUMP SUCTION CHECK C-12 cvo II 1NV861 ND TO PZR SPRAY CN-1554-01.00 IL- c ACT 2 2 CK SA c OIC N/A eve II CHECK 10 cvo II 1NV865A STANDBY M/U PUMP CN-1554-01.08 / B ACT 2 3 GL MO OIC c FAI RPI 2Y SUCTION FROM XFR H-01 TUBE FSC Q ST-C Q 1NV872A STDBY M/U PMP FIL T CN-1554-01.08 / F- A ACT 2 2 GL MO OIC c FAI RPI 2Y OTLT 08 LTJ J FSC Q ST-C Q 1NV874 STAND BY MAKEUP CONT CN-1554-01.08 / F- A/C ACT 2 2 CK SA OIC OIC NIA eve II HEADER CHECK 10 cvo II LTJ J

Catawba .terval __ de ISTC Catawba N~clear Plant Interval 4 IST 1.0.6 Page 73 of 222 Valve Summary Listing Page 73 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NV878 STDBY MAKEUP TO NC CN-1554-01.08 / c ACT 2 0.75 CK SA c OIC N/A eve II PMP 1A CHK G-12 cvo II 1NV879 STDBY MAKEUP TO NC CN-1554-01.08 / c ACT 2 0.75 CK SA c O/C NIA eve II PMP 1C CHK G-13 cvo II 1NV880 STDBY MAKEUP TO NC CN-1554-01.08/ c ACT 2 0.75 CK SA c OIC N/A eve II PMP 1B CHK E-12

                                                                                 -                   cvo   II 1NV881  STDBY MAKEUP TO NC     CN-1554-01.08 /  c   ACT   2     0.75  CK   SA     c    O/C     N/A  eve   II PMP 10 CHK                  E-13 cvo   II 1NW002  1A NW SURGE CHAMBER    CN-1569-01.00 I  B  PASS   2     0.5   sv  so      c     c       c   RPI  2Y NITROGEN                    H-11 1NW006  NW SURGE CHAMBER RN    CN-1569-01.00 I  c  ACT    2       1   CK   SA    OIC   OIC    N/A   eve   II SUPPLY CHECK                G-12 I

cvo II 1NW008A 1A NW SURGE CHAMBER CN-1569-01.00 I B ACT 2 2 sv so c 0 0 RPI 2Y RN SUPPLY G-13 FO Q FSO Q ST-0 Q 1NW011 1A NW SURGE CHAMBER CN-1569-01.00 IF- B PASS 2 1 sv so c c c RPI 2Y YM SUPPLY 13 1NW013A NW TO 1KC-425A CN-1569-01.00 I B ACT 2 1 sv so c 0 0 RPI 2Y E-09 FO Q FSO Q ST-0 Q 1NW017 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C OIC NIA eve II 1KC425A E-11 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 74 of 222 Valve Summary Listing Page 74 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW020A 1A NW SURGE CHAMBER CN-1569-01.02 I F- B ACT 2 1 sv so c 0 0 RPI 2Y OUTLET 09 FO Q FSO Q ST-0 Q 1NW021 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 1 CK SA OIC OIC N/A eve II 1WLA24 E-12 cvo II 1NW024 NW SUPPLY CHECK TO

CN-1569-01.00 I c ACT 2 1 CK SA OIC O/C N/A eve II 1KC333A E-13 cvo II 1NW027 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA OIC OIC N/A eve II 1KC320A E-14 cvo II 1NW035A CONT VLV INJ HOR 1A CN-1569-01.00 I B ACT 2 1 GL MO c OIC FAI RPI 2Y CONT ISOL G-09

                                                                                                         .                  FSC   Q FSO   Q ST-C   Q ST-0   Q 1NW037        1A NW CONTAINMENT      CN-1569-01.00 /I-   c   ACT   2       1        CK             SA  OIC   OIC    N/A   eve   II HEADER CHECK                  09 cvo    II 1NW040        NW SUPPLY CHECK TO     CN-1569-01.00 I J-  c   ACT   2      0.5       CK             SA  O/C   OIC    N/A   eve   II 1WL825A                       11 cvo    II
. 1NW043        NW SUPPLY CHECK TO     CN-1569-01.00 I J-  c   ACT   2    . 0.5       CK             SA  OIC   OIC    N/A   eve   II 1WL805A                       10 cvo    II
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Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 75 of 222 Vah(e Summary Listing Page 75 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE . ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW046A SW TO 1 RN-484A CN-1569-01.00/ B ACT 2 1 sv so c 0 0 RPI 2Y K-09 FO Q FSO Q ST-0 Q 1NW047 NW SUPPLY CHECK TO CN-1569-01.00/ L- c ACT 2 0.5 CK SA O/C O/C NIA eve II 1WL867A 10 cvo II 1NW050 NW SUPPLY CHECK TO CN-1569-01.00 IL- c ACT 2 0.5 CK SA OIC OIC N/A eve II 1RN484A 11 cvo II 1NW057 1B NW SURGE CHAMBER CN-1569-01.00 I B PASS 2 0.5 sv so c c c RPI 2Y NITROGEN H-4 1NW061B 1B NW SURGE CHAMBER CN-1569-01.00 I B ACT 2 2 sv so c 0 0 RPI 2Y RN SUPPLY G-02 FO Q FSO Q ST-0 Q 1NW063 1B NW SURGE CHAMBER CN-1569-01.00 I c ACT 2 1 CK SA O/C O/C NIA eve II RN CHECK G-04 cvo II 1NW064 1B NW SURGE CHAMBER CN-1569-01.00 IF- B PASS 2 1 sv so c c c RPI 2Y YM SUPPLY 2 1NW068B SEAL WATER TO CN-1569-01.00 I B ACT 2 1 sv so c 0 0 RPI 2Y 1RN487B AND 1RN437B E-05 FO Q FSO Q ST-0 Q

Catawba 4th Interval. Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 76 of 222 Valve Summary Listing Page 76 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW0698 1B NW SURGE CHAMBER CN-1569-01.00 I F- B ACT 2 1 sv so c 0 0 RPI 2Y OUTLET 06 FO Q FSO Q ST-0 Q 1NW070 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1NC568 E-05 cvo II 1NW074 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC O/C NIA eve II 1RN4378 E-05 cvo II 1NW077 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1RN4878 E-04 cvo II 1NW080 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 1WL8698 E-03 cvo II 1NW086 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC O/C NIA eve II 1WL8278 E-01 cvo II 1NW089 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 1RF3898 C-05 cvo II 1NW092 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 1RN4048 C-05 cvo II 1NW095 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1KC3388 C-04 cvo II 1NW098 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1WL8078 C-02

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Catawba 41 terval Standa delSTC Catawba Nuclear Plant Interval 4 'IST 1.0.6 Page 77 of 222 Valve Summary Listing Page 77 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW101 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA O/C O/C NIA eve II 1RF4478 C-01 cvo II 1NW1058 CONT VLV INJ HOR 18 CN-1569-01.00/ 8 ACT 2 1 GL MO c O/C FAI RPI 2Y CONT ISOL H-06 FSC Q FSO Q ST-C Q ST-0 Q 1NW107 18 NW CONTAINMENT CN-1569-01.00 /I- c ACT 2 1 CK SA OIC OIC N/A eve II HEADER CHECK 06 cvo II 1NW109 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA OIC O/C N/A eve II 1KC424B K-05 cvo II 1NW110B NW SUPPLY TO 1KC-4248 CN-1569-01.00 I B ACT 2 1 sv so c 0 0 RPI 2Y K-06 FO Q FSO Q ST-0 Q 1NW111 NW SUPPLY CHECK TO CN-1569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 1KC332B 05 cvo II 1NW114 NW SUPPLY CHECK TO CN-1569-01.00 IL- c ACT 2 0.5 CK SA OIC OIC N/A eve II 1KC424B 05 cvo II 1NW120 NW SUPPLY CHECK TO CN-1569~01.00 I J- c ACT 2 0.5 CK SA O/C OIC N/A eve II 1KC332B 05 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 78 of 222 Valve Summary Listing Page 78 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW121 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 1WL827B E-01 cvo II 1NW123 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C OIC NIA eve II 1WL869B E-03 cvo II 1NW124 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 1RN487B E-04 cvo II 1NW125 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA O/C O/C N/A eve II 1RN437B E-05 cvo II 1NW126 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA OIC O/C N/A eve II 1NC56B E-05 cvo II 1NW127 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA OIC O/C N/A eve II 1RF447B C-01 cvo II 1NW128 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1WL807B C-02 cvo II 1NW129 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 1KC338B C-04 cvo II 1NW130 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 1RN404B C-05 cvo II 1NW131 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 1RF389B C-05 cvo II 1NW132 NW SUPPLY CHECK TO . CN-1569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 1WL867A K-10 cvo II

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Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 79 of 222 Valve Summary Listing Page 79 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW133 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 1RN484A K-11 cvo II 1NW135 NW SUPPLY CHECK TO CN-1569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 1WL805A 10 cvo II 1NW136 NW SUPPLY CHECK TO CN-1569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 1WL825A 11 cvo II 1NW138 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 1KC425A E-11 cvo II 1NW139 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 1 CK SA OIC OIC N/A eve II 1WLA24 E-12 cvo II 1NW140 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 1 CK SA O/C OIC N/A eve II 1KC333A E-13 cvo II 1NW141. NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1KC320A E-14 cvo II 1NW1458 SEAL WATER TO 1KC- CN-1569-01.00 I 8 ACT 2 0.5 sv so c 0 0 RPI 2Y 3388 & 1RN-4048 C-05 FO Q FSO Q ST-0 Q 1NW147 NW SUPPLY CHECK TO CN-1569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 1WLA21 07 cvo II 1NW148 NW SUPPLY CHECK TO CN-1569-01.00 I J- c ACT 2 0.5 CK SA O/C O/C N/A eve II 1WLA21 07 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 80 of 222 Valve Summary Listing Page 80 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW159 NW SUP CHK TO 1NV-10A CN-1569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC NIA eve II 12 cvo II 1NW160 NW SUPPLY CHECK TO CN-1569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 1NV-10A 12 cvo II 1NW163 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1NV-11A K-12 cvo II 1NW164 NW SUP CHKTO 1NV-11A CN-1569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 12 cvo II 1NW168 NW SUP CHKTO 1NV-13A CN-1569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II K-13 cvo II 1NW169 NW SUPPLY CHECK TO CN-1569-01.00 I J- c ACT 2 0.5 CK SA O/C OIC N/A eve II 1NV-13A 13 cvo II 1NW171 NW SUP CHK TO 1NV-89A CN-1569-01.00 I J- c ACT 2 0.5 CK SA OIC O/C N/A eve II 13 cvo II 1NW172 NW SUP CHK TO 1NV-89A CN-1569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 13 cvo II 1NW175A NWTO 1Nl-173A CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y C-12 FO Q FSO Q ST-0 Q 1NW178 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA O/C OIC N/A eve II 1Nl-173A C-12 cvo

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Catawba terval (" de ISTC 1 Catawba N~clear Plant Interval 4 'IST 1.0.6 Page 81 of 222 Valve Summary Listing Page. 81 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/* CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW179 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1Nl-173A C-12 cvo II 1NW180A NW TO 1NS-43A CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y C-13 FO Q FSO Q ST-0 Q 1NW183 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 1NS-43A C-13 cvo II 1NW184 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 1NS-43A C-13 cvo II 1NW185A NWTO 1Nl-162A CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y C-13 FO Q FSO Q ST-0 Q 1NW188 NW SUP CHK TO 1NI- CN-1569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 162A C-13 cvo II 1NW189 NW SUP CHK TO 1NI- CN-1569-01.00/ c ACT 2 0.5 CK SA OIC O!C N/A eve II 162A C-13 cvo II 1NW195A NW TO 1NS-32A CN-1569-01.00 IF- B ACT 2 0.5 sv so c 0 0 RPI 2Y 08 FO Q FSO Q ST-0 Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 82 of 222 Valve Summary Listing Page 82 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW196 NW SUPPLY CHECK TO CN-1569-01.00 IF- c ACT 2 *o.5 CK SA O/C O/C N/A eve II 1NS-32A 08 cvo II 1NW197 NW SUPPLY CHECK TO CN-1569-01.00 IF- c ACT 2 0.5 CK SA OIC OIC N/A eve II 1NS-32A 08 cvo II 1NW200A NW TO 1NS-29A CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y E-08 FO Q FSO Q ST-0 Q 1NV\1201 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA OIC OIC N/A eve II 1NS-29A E-08 cvo II 1NV\1202 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1NS-29A D-08 cvo II 1NV\1205 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1KC-3058 E-07 cvo II 1NV\1206 NW SUPPLY CHECK TO CN-1569-01.00 IF- c ACT 2 0.5 CK SA OIC OIC N/A eve II 1KC-3058 07 cvo II 1NV\1209 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC NIA eve II 1KC-3158 E-07 cvo II 1NV\1210 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O!C OIC N/A eve II 1KC-3158 E-07 cvo II 1NV\1213 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1 NV-91 B C-07 cvo II

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Catawba 4' terval Stand a de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 83 of 222 Valve Summary Listing Page 83 of* 222 VALVE ID FUNCTION DRAWING/COOR CAT .ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW214 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC O/C NIA eve II 1NV-91B C-07 cvo II 1NW217B NWTO 1NS-12B CN-1569-01.00 I 8 ACT 2 0.5 sv . so c 0 0 RPI 2Y C-08 FO Q FSO Q ST-0 Q 1NW218 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1NS-128 C-08 cvo II 1NW219 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 1NS-128 C-08 cvo .11 1NW2228 NWTO 1NS-158 CN-1569-01.00 I 8 ACT 2 0.5 sv so c 0 0 RPI 2Y C-08 FO Q FSO Q ST-0 Q 1NW223 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA OIC OIC N/A eve II 1NS-158 C-08 cvo II 1NW224 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C O/C NIA eve II 1NS-158 C-08 cvo II 1NW2278 NW TO 1NS-388 CN-1569-01.00 I 8 ACT 2 0.5 sv so c 0 0 RPI 2Y C-09 FO Q FSO Q ST-0 Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 84 of 222 Valve Summary Listing Page 84 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1NW230 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA OIC OIC NIA eve II 1NS-38B C-09 cvo II 1NW231 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1NS-38B C-09 cvo II 1NW237B NWTO 1Nl-178B CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y C-11 FO Q FSO Q ST-0 Q 1NW240 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 1Nl-178B C-11 cvo II 1NW241 NW SUPPLY CHECK TO CN-1569-01.00/ c ACT 2 0.5 CK SA O/C O/C N/A eve II 1Nl-178B C-11 cvo II 1NW242B NWTO 1NI 1838 CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y C-11 FO Q FSO Q ST-0 Q 1NW245 NW SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK .SA OIC OIC N/A eve II 1Nl-183B C-11 cvo II 1NW246 NI SUPPLY CHECK TO CN-1569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 1Nl-183B C-11 cvo II 1NW247 RELIEF VLV CN-1569-01.00 I J- c ACT *2 1 RV SA c OIC N/A RV I 11 c c 1NW248

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Catawba 49terval Standa ode ISTC j Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 85 of 222 Valve Summary Listing Page 85 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS* REQ NORM SAFE FAIL 1NW249 NW RELIEF CN-1569-01.00 I c ACT 2 1 RV SA c O/C N/A RV I D-06 1RF3898 UNIT 1 RF CONTAINMENT CN-1599-02.02 / A ACT 2 4 GA MO c c FAI LT 2Y ISOL D-07 RPI 2Y FSC cs CSJ-CN-RF-02 ST-C cs CSJ-CN-RF-02 1RF392 HOSE RACK CHECK CN-1599-02.02 / F- A/C ACT 2 4 CK SA OIC OIC NIA eve II 07 cvo II LTJ J 1RF4478 RF CONT ISOL CN-1599-02.02 / A ACT 2 4 GA MO c c FAI LT 2Y C-03 RPI 2Y FSC cs CSJ-CN-RF-02 ST-C cs CSJ-CN-RF-02 1RF448 U-1 CONT ISOL CHECK CN-1599-02.02 / A/C ACT 2 4 CK SA OIC O/C N/A eve II E-03 cvo II LTJ J 1RF4578 ANNULUS SPRINKLER CN-1599-02.02 / B ACT NC 6 GA MO 0 c FAI RPI 2Y HEADER ISOL C-02 FSC Q ST-C Q 1RN001A RN P/H PIT A ISOL FROM CN-1574-01.00 I J- B ACT 3 48 BF MO 0 c FAI RPI 2Y LAKE 07 FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 86 of 222 Valve Summary Listing Page 86 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1RN002B RN PIH PIT A ISOL FROM CN-1574-01.00 I J- B ACT 3 48 BF MO 0 c FAI RPI 2Y LAKE 07 FSC Q ST-C Q 1RN003A RN P/H PIT A ISOL FROM CN-1574-01.02 / J- B ACT 3 48 BF MO c 0 FAI RPI 2Y SNSWP . 11 . FSO Q ST-0 Q 1RN004B RN PIH PIT B ISOL FROM CN-1574-01.02 / J- B ACT 3 48 BF MO c 0 FAI RPI 2Y SNSWP 05 FSO Q ST-0 Q 1RN005A RN PIH PIT B ISOL FROM CN-1574-01.00 I B ACT 3 48 BF MO 0 c FAI RPI 2Y LAKE K-05 FSC Q ST-C Q 1RN006B RN P/H PIT B ISOL FROM CN-1574-01.00/ B ACT 3 48 BF MO 0 c FAI RPI 2Y LAKE K-04 FSC Q ST-C Q 1RN009 1A RN PUMP DISCHARGE CN-1574-01.00 I c ACT 3 30 CK SA OIC OIC N/A eve II CHECK E-03 cvo II 1RN011A 1A RN PUMP MOTOR CN-1574-01.00 I B ACT 3 2 BL MO OIC 0 FAI RPI 2Y COOLER INLET ISOL E-06 FSO Q ST-0 Q 1RN018 1B RN PUMP DISCHARGE CN-1574-01.02 / F- c ACT 3 30 CK SA OIC OIC NIA eve II CHECK 02

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Catawba 4 'terval Standa9>de ISTC Catawba Nuclear Plant Interval 4 ~ - -~ IST 1.0.6 Page 87 of 222 Va,lve Summary Listing Page 87 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1RN020B 1 B RN PUMP MOTOR CN-1574-01.02/ B ACT 3 2 BL MO c 0 FAI RPI 2Y COOLER SUPPLY ISOL E-05 FSO Q ST-0 Q 1RN028A 1A RN PUMP DISCHARGE CN-1574-01.00/ B ACT 3 30 BF MO O/C 0 FAI RPI 2Y ISOL E-03 FSO Q ST-0 Q 1RN030A 1A RN STRAINER CN-1574-01.00/ B ACT 3 4 BL MO c 0 FAI RPI 2Y BACKFLUSH ISOL D-06

                                          '                                                            FSO    Q ST-0   Q 1RN038B  1B RN PUMP DISCHARGE CN-1574-01.02 / F-  B   ACT   3       30    BF  MO    O/C    0      FAI  RPI   2Y ISOL                          02 FSO    Q ST-0  Q 1RN040B 1B RN STRAINER          CN-1574-01.02 /  B   ACT   3        4    BL  MO     c     0      FAI   RPI  2Y BACKFLUSH ISOL               D-04 FSO    Q ST-0   Q 1RN047A RN SUPPLY X-OVER ISOL   CN-1574-01.01 /  B   ACT   3       30    BF   MO    0     c      FAI   RPI  2Y E-03 FSC    Q ST-C  Q 1RN048B  RN SUPPLY X-OVER ISOL  CN-1574-01.01 /  B   ACT   3       30    BF   MO    0     c      FAI   RPI  2Y E-08 FSC    Q ST-C  Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 88 of 222 Valve Summary Listing Page 88 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1RN049A NON-ESS SUPPLY HOR CN-1574-01.01 I B ACT 3 20 BF MO 0 c FAI RPI 2Y ISOL D-04 FSC Q ST-C Q 1RN050B NON-ESS SUPPLY HOR CN-1574-01.01 / B ACT 3 20 BF MO 0 c FAI RPI 2Y ISOL D-04 FSC Q ST-C Q 1RN051A NON-ESS RET HOR ISOL CN-1574-01.05/ B ACT 3 20 BF MO 0 c FAI RPI 2Y D-07 FSC Q ST-C Q 1RN052B NON-ESS RET HOR ISOL CN-1574-01.05 / B ACT 3 20 BF MO 0 c FAI RPI 2Y D-07 FSC Q ST-C Q 1RN053B STATION RN DISCHARGE CN-1574-01.05 / B ACT 3 42 BF MO 0 c FAI RPI 2Y HEADER X-OVER E-09 FSC Q ST-C Q 1RN054A STATION RN DISCH CN-1574-01.05/ B ACT 3 42 BF MO 0 c FAI RPI 2Y HEADER X-OVER E-08 FSC Q ST-C Q 1RN057A STATION RN DISCH TO CN-1574-01.05 / B ACT 3 42 BF MO 0 c FAI RPI 2Y RL SYSTEM E-05 FSC Q ST-C Q t**i~

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Catawba 41 terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 89 of 222 Valve Summary Listing Page .89 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1RN058B RN HEADER B RETURN CN-1574-01.05/ B ACT 3 42 BF MO c 0 FAI RPI 2Y TO SNSWP E-11 FSO Q ST-0 Q . 1RN063A RN HEADER A RETURN CN-1574-01.05/ B ACT 3 42 BF MO c 0 FAI RPI 2Y TO SNSWP G-08 FSO Q ST-0 Q 1RN067A 1A RN HEADER SUPPLY CN-1574-01.01 IF- B PASS 3 30 BF MO 0 0 FAI RPI 2Y ISOL 09 - 1RN069B 1B RN HEADER SUPPLY CN-1574-01.01 IF- B PASS 3 30 BF MO 0 0 FAI RPI 2Y ISOL 02 1RN144A 1A NS HX INLET ISOL CN-1574-02.00 I B ACT 3 18 BF MO c 0 FAI RPI 2Y B-08 FSO Q ST-0 Q 1RN147 1A NS HX RELIEF CN-1574-02.00 /I- c ACT 3 4 RV SA c OIC NIA RV I 13 1RN148A 1A NS HX OUTLET ISOL CN-1574-02.00 IL- B ACT 3 18 BF MO c 0 FAI RPI 2Y 02 FSO Q ST-0 Q 1RN225B 1B NS HX INLET ISOL CN-1574-02.04 / B ACT 3 12 BF MO c 0 FAI RPI 2Y B-08 FSO Q ST-0 Q 1RN228 1B NS HX RELIEF CN-1574-02.04 /I- c ACT 3 4 RV SA c O/C N/A RV I 13 1RN229B 1B NS HX OUTLET ISOL CN-1574-02.04 / L- B ACT 3 18 BF MO c 0 FAI RPI 2Y 2 FSO Q ST-0 Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 90 of 222 Valve Summary Listing Page 90 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1RN232A 1A D/G HX INLET ISOL CN-1574-02.01 / B ACT 3 10 BF MO c 0 FAI RPI 2Y D-03 FSO Q ST-0 Q 1RN235 1A D/G COOLING WATER CN-1574-02.01 / c ACT 3 0.75 RV SA c OIC NIA RV I HX RELIEF H-03 1RN250A 1A RN SUPPLY HEADER CN-1574-02.01 / B ACT 3 8 GA MO c 0 FAI RPI 2Y TO CA PUMPS SUCTION D-06 ISOL FSO Q ST-0 Q 1RN287A 1A KC HX INLET ISOL CN-1574-02.01 / B PASS 3 24 BF MO 0 0 FAI RPI 2Y D-13 1RN290 1A KC HX RELIEF CN-1574-02.01 I J- c ACT 3 0.75 RV SA c OIC N/A RV I 12 1RN291 1A KC HX OUTLET CN-1574-02.01 / L- B ACT .3 12 BL AO 0 0 0 RPI 2Y THROTTLE 13 FO Q FSO Q ST-0 Q 1RN292B 1B D/G HX INLET ISOL CN-1574-02.05 / B ACT 3 10 BF MO c 0 FAI RPI 2Y D-02 FSO Q ST-0 Q 1RN295 1B DIG COOLING WATER CN-1574-02.05 /I- c ACT 3 0.75 RV SA c OIC N/A RV I HX RELIEF 02 1RN310B 1B RN HEADER TO CA CN-1574-02.05 / B ACT 3 8 .GA MO c 0 FAI RPI 2Y PUMPS SUCTION ISOL D-07 FSO Q ST-0 Q 1RN347B

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                                                                       -rr-                                                     r Catawba Nuclear Plant Interval 4                                                                                                   , IST 1.0.6 Page 91 of 222 Valve Summary Listing Page 91 of 222 VALVE ID         FUNCTION       DRAWING/COOR *CAT 'ACT/ CLASS *SIZE   TYPE , ACT       POSITION      TEST  FREQ    PROCEDURE           NOTES PASS                                            REQ NORM SAFE     FAIL 1RN350  1B KC HX RELIEF        CN-1574-02.05 / J- c   ACT 3   . 0.75  RV     SA    c    OIC    N/A    RV    I 13 1RN351  1B KC HX OUTLET         CN-1574-02.05 /    B  ACT 3      12   BL     AO    0     0       0   RPI   2Y THROTTLE                     K-13 FO     Q FSO     Q ST-0  Q 1RN404B  UPPER CONT VENT UNIT    CN-1574-02.08 /    A  ACT 2       6   GA     MO    0     c      FAI   RPI   2Y SUPPLY                       G-05 LT   2Y FSC     Q ST-C  Q 1RN405 .UPPER CONT VENT UNIT   CN-1574-02.08 /   NC  ACT 2       6    CK    SA   OIC    c      N/A  BOO      II SUPPLY CHECK                G-03 eve      II LTJ     J 1RN437B  LOWER CONT VENT UNIT   CN-1574-02.08 /    A  ACT 2      12    GA    MO    0     c      FAI   RPI   2Y SUPPLY                      G-12 LT  2Y FSC   cs                      CSJ-CN-RN-02 ST-C  cs                      ,CSJ-CN-RN-02 1RN438  LOWER CONT VENT        CN-1574-02.08 /   NC  ACT 2       12    CK    SA  OIC     c     N/A  BOO       II UNITS SUPPLY CONT           D-13 ISOL INSIDE CHECK eve       II LTJ      J

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 92 of 222 Valve Summary Listing Page 92 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1RN484A LOWER CONT VENT UNIT CN-1574-02.02 / A ACT 2 12 GA MO 0 c FAI RPI 2Y RETURN G-08 LT 2Y FSC cs CSJ-CN-RN-03 ST-C cs CSJ-CN-RN-03 1RN485 LOWER CONT VENT CN-1574-02.02 / A/C ACT 2 0.75 CK SA OIC O/C N/A eve II UNITS RETURN INSIDE G-09 ISOL PRESS RELIEF CHECK cvo II LTJ J 1RN487B LOWER CONT VENT UNIT CN-1574-02.02 / F- A ACT 2 12 GA MO 0 c FAI RPI 2Y RETURN 08 LT 2Y FSC cs CSJ-CN-RN-03 ST-C cs CSJ-CN-RN-03 1RN807 1 B NC PUMP MOTOR AIR CN-1574-02.03 / J- c ACT NC 0.75 RV SA c O/C N/A RV I COOLER SAFETY RELIEF 07 1RN843B STATION RN DISCH TO CN-1574-01.05/ B ACT 3 42 BF MO 0 c FAI RPI 2Y RL SYSTEM E-05 FSC Q ST-C Q 1RN846A 1A D/G HX RETURN TO CN-1574-02.01 I J- B ACT 3 10 BF MO c 0 FAI RPI 2Y SNS WP 03 FSO Q ST-0 Q

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                                                                  'Page 93 of 222 VALVE ID        FUNCTION        DRAWING/COOR       CAT ACT/ CLASS* SIZE  TYPE  ACT       POSITION      TEST  FREQ      PROCEDURE        NOTES PASS                                             REQ NORM SAFE     FAIL 1RN847A  1A DIG HX RETURN TO    CN-1574-02.01 I J-  B   ACT    3     10   BF   MO     0     c      FAI  RPI   2Y LAKE                          02 FSC    Q ST-C   Q 1RN848B  1B D/G HX RETURN TO    CN-1574-02.05 / J-  B   ACT    3     10   BF   MO     c     0      FAI  RPI   2Y SNSWP                         02 FSO    Q ST-0   Q 1RN849B  1B D/G HX RETURN TO    CN-1574-02.05 / J-  B   ACT    3     10   BF   MO     0     c      FAI   RPI  2Y LAKE                          01 FSC    Q ST-C  Q 1RN854  RN PUMP 1A DISCH       CN-1574-01.00 IF-   c   ACT    3      4   VB    SA    c    OIC     NIA   RV      I VACUUM BREAKER                03 1RN855  RN PUMP 1B DISCH       CN-1574-01.02 / F-  c   ACT    3      4   VB    SA    c    O/C     N/A   RV      I VACUUM BREAKER                01 1RN861  UPPER CONT VENT        CN-1574-02.08 / J-  c   ACT   NC    0.75  RV    SA    c    O!C     N/A   RV      I UNITS SUPPLY HEADER           01 RELIEF 1RN863  LOWER CONT VENT         CN-1574-02.08 /    c   ACT   NC    0.75  RV    SA    c    OIC     N/A   RV       I UNITS SUPPLY HEADER          D-09 RELIEF 1RN882  1A CONTROL ROOM         CN-1574-02.01 /    c   ACT    3    0.75  RV    SA    c    OIC     N/A   RV    I AREA CHILLER                 H-10 CONDENSER OUTLET RELIEF 1RN883  1B CONTROL ROOM         CN-1574-02.05 /    c   ACT    3    0.75  RV    SA    c    O/C     N/A   RV    I AREA CHILLER                 H-09 CONDENSER OUTLET RELIEF 1RNC66  1A NS WET LAYUP         CN-1574-02.00 I    c   ACT    3      1   CK    SA   O/C    c      N/A  BOO      II RECIRC PUMP DISCH            D-09 CHECK                                                                                          eve      II 1RNC67  1A NS HX WET LAYUP      CN-1574-02.00  I   B   ACT    3      2   BL    MA    0     c      N/A   FS   2Y INLET ISOL                   K-03

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 94 of 222 Valve Summary Listing Page 94 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1RNC69 1B NS WET LAYUP CN-1574-02.04 / c ACT 3 1 CK SA OIC c N/A BOO II RECIRC PUMP DISCH 0-09 CHECK eve II 1RNC70 1B NS HX WET LAYUP CN-1574-02.04 / B ACT 3 2 BL MA 0 c N/A FS 2Y INLET ISOL K-03 1RNP47 1A1 DIG STARTING AIR CN-1574-02.01 /I- c ACT 3 1 CK SA OIC c N/A BOO II AFTERCOOLER OUTLET 05 CHECK eve II 1RNP48 1A2 DIG STARING AIR CN-1574-02.01 /I- c ACT 3 1 CK SA OIC c N/A BOO II AFTERCOOLER OUTLET 01 CHECK eve II 1RNP49 1B1 O/G STARTING AIR CN-1574-02.05 /I- c ACT 3 1 CK SA OIC c N/A BOO II AFTERCOOLER OUTLET 1 CHECK eve II 1RNP50 1B2 DIG STARTING AIR CN-1574-02.05 /I- c ACT 3 0.75 CK SA OIC c N/A BOO II AFTERCOOLER OUTLET 3 CHECK eve II 1SA001 1B S/G MAIN STEAM TO CN-1593-01.01 I B ACT 2 6 GA MA 0 OIC N/A FS 2Y CAPT MAINTENANCE G-04 ISOL 1SA002 1B S/G MAIN STEAM CN-1593-01.01 / B ACT 2 4 GA AO c 0 0 RPI 2Y SUPPLY TO CAPT G-04 FO Q FSO Q ST-0 Q

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Catawba 4 terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 95 of 222 Valve Summary Listing Page 95 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1SA003 18 SIG MAIN STEAM TO CN-1593-01.01 / c ACT 2 6 SCK SA OIC OIC N/A FS 2Y CAPT STOP CHECK G-05 eve II cvo II 1SA004 1 C S/G MAIN STEAM TO CN-1593-01.01 / B ACT 2 6 GA MA 0 OIC N/A FS 2Y CAPT MAINTENANCE H-04 ISOL 1SA005 1C S/G MAIN STEAM CN-1593-01.01 I B ACT 2 4 GA AO c 0 0 RPI 2Y SUPPLY TO CAPT H-04

                                                                      .                                 FO    Q FSO    Q ST-0  Q 1SA006  1C SIG MAIN STEAM TO     CN-1593-01.01 /  c   ACT   2       6   SCK  SA    OIC   OIC     N/A   FS   2Y CAPT STOP CHECK               H-05 eve     II cvo     II 1SM001  1D S/G MAIN STEAM ISOL   CN-1593-01.00/   B   ACT   2      34    GL  AO     0     c       c    RPI  2Y K-13 FC   cs                 CSJ-CN-SM-01 FSC   cs                 CSJ-CN-SM-01 ST-C  cs                 CSJ-CN-SM-01 1SM003   1C SIG MAIN STEAM ISOL  CN-1593-01.00 I  B   ACT   2      34    GL  AO     0     c       c    RPI   2Y H-13 FC   cs                 CSJ-CN-SM-01 FSC   cs                 CSJ-CN-SM-01 ST-C  cs                  CSJ-CN-SM-01

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 96 of 222 Valve Summary Listing Page 96 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1SM005 1B SIG MAIN STEAM ISOL CN-1593-01.00 IF- B ACT 2 34 GL AO 0 c c RPI 2Y 13 FC cs CSJ-CN-SM-01 FSC cs CSJ-CN-SM-01 ST-C cs CSJ-CN-SM-01 1SM007 1A SIG MAIN STEAM ISOL CN-1593-01.00 I 'B ACT 2 34 GL AO 0 c c RPI 2Y VALVE C-13 FC cs CSJ-CN-SM-01 FSC cs CSJ-CN-SM-01 ST-C cs CSJ-CN-SM-01 1SM009 1D S/G MAIN STEAM ISOL CN-1593-01.00 I J- B ACT 2 3 FC AO c c c RPI 2Y BYPASS 13 FC Q FSC Q ST-C Q 1SM010 1C S/G MAIN STEAM ISOL CN-1593-01.00 I B ACT 2 3 FC AO c c c RPI 2Y BYPASS G-13 FC Q FSC Q ST-C Q 1SM011 1B S/G MAIN STEAM ISOL CN-1593-01.00 I B ACT 2 3 FC AO c c c RPI 2Y BYPASS E-13 FC Q FSC Q ST-C Q

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Catawba 4 1 terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 97 of 222 Valve Summary Listing Page 97 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1SM012 1A SIG MAIN STEAM ISOL CN-1593-01.00 I B ACT 2 3 FC AO c c c RPI 2Y BYPASS B-13 FC Q FSC Q ST-C Q 1SM074B SIG 1D OTLT HDR BLOWN CN-1593-01.071 B PASS 2 2 GA MO 0 0 FAI RPI 2Y CN E-06 1SM075A SIG 1C OTLT HDR BLOWN CN-1593-01.071 B PASS 2 2 GA MO 0 0 FAI RPI 2Y CN E-13 1SM076B SIG 1B OTLT HDR BLOWN CN-1593-01.071 B PASS 2 2 GA MO 0 0 FAI RPI 2Y CN E-09 1SM077A SIG 1A OTL T HDR BLOWN CN-1593-01.07 I B PASS 2 2 GA MO 0 0 FAI RPI 2Y CN E-02 1SV001 10 SIG POWER CN-1593-01.00 IL- B ACT 2 6 PORV AO c OIC c FC 2Y OPERATED RELIEF 05 VALVE FSC 2Y FSO 2Y MS 2Y RPI 2Y STT 2Y ST-C Q 1SV002 1D SIG SAFETY NO 1 CN-1593-01.001 c ACT 2 6 RV SA c OIC NIA RV I K-06 1SV003 1D SIG SAFETY NO 2 CN-1593-01.001 c ACT 2 6 RV SA c OIC NIA RV I K-07 1SV004 1D SIG SAFETY NO 3 CN-1593-01.00 I c ACT 2 6 RV SA c OIC NIA RV I K-09 1SV005 1D SIG SAFETY NO 4 CN-1593-01.00 I c ACT 2 6 RV SA c OIC NIA RV I K-10 1SV006 1D SIG SAFETY NO 5 CN-1593-01.00 I c ACT 2 6 RV SA c OIC NIA RV I K-11

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 98 of 222 Valve Summary Listing Page 98 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1SV007 1C SIG POWER CN-1593-01.00 /I- B ACT 2 6 PORV AO c OIC c FC 2Y OPERATED RELIEF 9 VALVE FSC 2Y FSO 2Y MS 2Y RPI 2Y STT 2Y ST-C Q 1SV008 1C SIG SAFETY NO 1 CN-1593-01.0011- c ACT 2 6 RV SA c OIC NIA RV I 06 1SV009 1C SIG SAFETY NO 2 CN-1593-01.00 /I- c ACT 2 6 RV SA c OIC N/A RV I 07 1SV010 1C SIG SAFETY NO 3 CN-1593-01.00 /I- c ACT 2 6 RV SA c OIC NIA RV I 09 1SV011 1C SIG SAFETY NO 4 CN-1593-01.0011- c ACT 2 6 RV SA c OIC NIA RV I 10 1SV012 1C SIG SAFETY NO 5 CN-1593-01.0011- c ACT 2 6 RV SA c OIC NIA RV I 11 1SV013 18 SIG POWER CN-1593-01.00 IF- B ACT 2 6 PORV AO c OIC c FC 2Y OPERATED RELIEF 05 VALVE FSC 2Y FSO 2Y MS 2Y RPI 2Y STT 2Y ST-C Q 1SV014 1B SIG SAFETY NO 1 CN-1593-01.00 IF- c ACT 2 6 RV SA c OIC NIA RV I 06 1SV015 1B SIG SAFETY NO 2 CN-1593-01.00 IF- c ACT 2 6 RV SA c OIC NIA RV I 07 1SV016 1J~ SIG SAFETY NO 3 CN-1593-01.00 IF- c ACT 2 6 RV SA c OIC NIA RV I 1**.*-- 09 ....... . ...-l -.

Catawba terval Catawba Nuclear Plant Interval 4 Page 99 of 222 Valve Summary Listing Page 99 of 222 VALVE ID FUNCTION DRAWING/COOR CAT :ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1SV017 1B S/G SAFETY NO 4 CN-1593-01.00 I F- c ACT 2 6 RV SA c OIC N/A RV I 10 1SV018 1B SIG SAFETY NO 5 CN-1593-01.00 IF- c ACT . 2 6 RV SA c O/C N/A RV I 11 1SV019 1A SIG POWER CN-1593-01.00 I B ACT 2 6 PORV AO c OIC c FC 2Y OPERATED RELIEF D-05 VALVE FSC 2Y FSO 2Y MS 2Y RPI 2Y STT 2Y ST-C Q 1SV020 1A S/G SAFETY NO 1 CN-1593-01.00/ c ACT 2 6 RV SA c O/C N/A RV I C-06 1SV021 1A S/G SAFETY NO 2 CN-1593-01.00 I c ACT 2 6 RV SA c O/C N/A RV I C-07 1SV022 1A S/G SAFETY NO 3 CN-1593-01.00 I c ACT 2 6 RV SA c OIC N/A RV I C-09 1SV023 1A S/G SAFETY NO 4 CN-1593-01.00/ c ACT 2 6 RV SA c O/C N/A RV I C-10 1SV024 1A SIG SAFETY NO 5 CN-1593-01.00 I c ACT 2 6 RV SA c O/C NIA RV I C-11 1SV025B 1D SIG PORV ISOL CN-1593-01.00 I B ACT 2 6 GA MO 0 O/C FAI RPI 2Y K-05 FSC Q FSO Q ST-C Q ST-0 Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 100 of 222 Valve Summary Listing Page 100 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1SV026B 1C SIG PORV ISOL CN-1593-01.00 /I- B ACT 2 6 GA MO 0 OIC FAI RPI 2Y 05 FSC Q FSO Q ST-C Q ST-0 Q 1SV027A 1A SIG PORV ISOL CN-1593-01.00 I B ACT 2 6 GA MO 0 O/C FAI RPI 2Y C-05 FSC Q FSO Q ST-C Q ST-0 Q 1SV028A 1B S/G PORV ISOL CN-1593-01.00 IF- B ACT 2 6 GA MO 0 O/C FAI RPI 2Y 05 FSC Q FSO Q ST-C Q ST-0 Q 1VB083B VB CONT ISOL CN-1605-3.211-07 A ACT 2 2 DA MO c c FAI RPI 2Y LTJ J FSC Q ST-C Q 1VB085 UNIT 1 CONTAINMENT CN-1605-3.2 / H- AIC ACT 2 2 CK SA c c N/A BOO II HEADER SUPPLY CHECK 07 eve II LTJ J

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Catawba terval ode ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 101 of 222 Valve Summary Listing Page 101 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1VG005 1A D/G ENG STARTING CN-1609-04.00 /I- c ACT 3 1 CK SA OIC O/C N/A eve II AIR DRYER 1A1 DISCH 02 CHECK CVO II 1VG006 1A D/G ENG STARTING CN-1609-04.00 /I- c ACT 3 1 CK SA OIC O/C N/A eve II AIR DRYER 1A2 DISCH 13 CHECK - CVO II 1VG007 1A DIG ENG STARTING CN-1609-04.00 /I- c ACT 3 1 CK SA O/C OIC N/A eve II AIR DRYER 1A1 DISCH 02 CHECK CVO II 1VG008 1A D/G ENG STARTING CN-1609-04.00 I J- c ACT 3 1 CK SA OIC OIC N/A eve II AIR DRYER 1A2 DISCH 13 CHECK cvo II 1VG015 1A D/G ENG STARTING CN-1609-04.00 I c ACT 3 3 CK SA OIC O/C N/A eve II AIR TANK 1A1 OUTLET G-02 CHECK cvo II 1VG016 1A D/G ENG STARTING CN-1609-04.00 I c ACT 3 3 CK SA OIC O/C N/A eve II AIR TANK 1A2 OUTLET G-13 CHECK cvo II 1VG049 18 D/G ENG STARTING CN-1609-04.01 /I- c ACT 3 1 CK SA OIC OIC NIA eve II AIR DRYER 181 DISCH 02 CHECK cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 102 of 222 Valve Summary Listing Page 102 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1VG050 18 DIG ENG STARTING CN-1609-04.01 /I- c ACT 3 1 CK SA O/C O/C N/A eve II AIR DRYER 182 DISCH 13 CHECK cvo II 1VG051 18 D/G ENG STARTING CN-1609-04.01 /I- c ACT 3 1 CK SA OIC OIC N/A eve II AIR DRYER 181 DISCH 02 CHECK cvo II 1VG052 18 D/G ENG STARTING CN-1609-04.01 /I- c ACT 3 1 CK SA OIC OIC N/A eve II AIR DRYER 182 DISCH 13 CHECK cvo II 1VG059 18 D/G ENG STARTING CN-1609-04.01 / F- c ACT 3 3 CK SA OIC OIC N/A eve II AIR TANK 181 OUTLET 02 CHECK cvo II 1VG060 18 D/G ENG STARTING CN-1609-04.01 IF- c ACT 3 3 CK SA OIC OIC N/A eve II AIR TANK 182 OUTLET 13 CHECK cvo II 1VG133 18 D/G ENG STARTING CN-1609-04.01 I c ACT 3 0.5 CK SA OIC OIC N/A eve II AIR TANK 181 SUP TO H-02 ENG CONTROL PNL 18 C cvo II 1VG134 18 D/G ENG STARTING CN-1609-04.01 I c ACT 3 0.5 CK SA O/C O/C N/A eve II AIR TANK 182 SUP TO H-13 ENG CONTROL PNL 18 C cvo II

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Catawba Catawba Nuclear Plant Interval 4 Standa' ode ISTC 1 IST 1.0.6 Page 103 of 222 Valve Summary Listing Page 103 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1VG135 1A DIG ENG STARTING CN-1609-04.00 I c ACT 3 0.5 CK SA OIC OIC NIA eve II AIR TANK 1A1 SUP TO H-02 ENG CONTROL PNL 1A C cvo II 1VG136 1A DIG ENG STARTING CN-1609-04.00 I c ACT 3 0.5 CK SA OIC OIC N/A eve II AIR TANK 1A2 SUP TO H-13 ENG CONTROL PNL 1A C cvo II 1Vl077B VI CONT ISOL CN-1605-01.04/ A ACT 2 2 DA MO 0 c FAI RPI 2Y K-06 FSC cs CSJ-CN-VI-02 ST-C cs CSJ-CN-VI-02 LTJ J 1Vl079 VI CONTAINMENT CN-1605-01.04 / A/C ACT 2 2 CK SA 0 c N/A BOO II HEADER CHECK H-09 eve II LTJ J 1Vl312A VI TO VP CONT ISOL CN-1605-01.04 / A ACT 2 2 GL MO 0 c FAI RPI 2Y H-08 LTJ J FSC Q ST-C Q 1Vl367 NC PORV 1NC 34A AIR CN-1605-01.14/ c ACT 3 2 CK SA 0 c N/A BOO II SUP CHECK E-11 eve II 1Vl368 NC PORV 1 NC 32B AIR CN-1605-01.14 / c ACT 3 2 CK SA 0 c N/A BOO II SUP CHECK E-12 eve II 1Vl369 NC PORV 1NC 34A NI CN-1605-01.14 / F- c ACT 3 2 CK SA c OIC N/A eve II ACCUM SUP CHECK 10 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 104 of 222 Valve Summary Listing Page 104 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1Vl370 NC PORV 1NC 32B NI CN-1605-01.14 / F- c ACT 3 2 CK SA c OIC N/A eve II ACCUM SUP CHECK 13 cvo II 1Vl373 NI ACCUM 1A TO NC CN-1605-01.14 / c ACT 3 1.5 RV SA c OIC N/A RV I PORVRN G-10 1Vl374 1B CLA TO NC PORV CN-1605-01.14/ c ACT 3 1.5 RV SA c O/C N/A RV I RELIEF G-13 1VP001B UPPER CONT PURGE CN-1576-01.00 /I- A PASS 2 24 BF AO c c c LTJ J SUPPLY OUTSIDE ISOL 05 1VP002A UPPER CONT PURGE CN-1576-01.00 /I- A PASS 2 24 BF AO c c c LTJ J SUPPLY INSIDE ISOL 06 1VP003B UPPER CONT PURGE CN-1576-01.00/ A PASS 2 24 BF AO c c c LTJ J SUPPLY OUTSIDE ISOL H-05 1VP004A UPPER CONT PURGE CN-1576-01.00/ A PASS 2 24 BF AO c c c LTJ J SUPPLY INSIDE ISOL H-06 1VP006B LOWER CONT PURGE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J SUPPLY OUTSIDE ISOL G-05 1VP007A LOWER CONT PURGE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J SUPPLY INSIDE ISOL G-06 1VP008B LOWER CONT PURGE CN-1576-01.00 IF- A PASS 2 24 BF AO c c c LTJ J SUPPLY OUTSIDE ISOL 05 1VP009A LOWER CONT PURGE CN-1576-01.00 I F- A PASS 2 24 BF AO c c c LTJ J SUPPLY INSIDE ISOL 06 1VP010A UPPER CONT PURGE CN-1576-01.00 /I- A PASS 2 24 BF AO c c c LTJ J EXHAUST INSIDE !SOL 09 1VP011 B UPPER CONT PURGE CN-1576-01.00 /I- A PASS 2 24 BF AO c c c LTJ J EXHAUST OUTSIDE ISOL 10 1VP012A UPPER CONT PURGE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J EXHAUST INSIDE ISOL H-09 1VP013B UPPER CONT PURGE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J EXHAUST OUTSIDE ISOL H-10 1VP015A LOWER CONT PURGE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J EXHAUST INSIDE ISOL G-09 1VP016B LOWER CONT PURGE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J EXHAUST OUTSIDE ISOL G-10 1VP017A INCORE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J INSTRUMENTATION E-09

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Catawba 49terval ,- Standa1 odelSTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 105 of 222 Valve Summary Listing Page 105 of 222 VALVE ID FUNCTION ID RAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1VP018B INCORE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J INSTRUMENTATION E-10 ROOM PURGE SUPPLY OUTSIDE ISOL 1VP019A INCORE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J INSTRUMENTATION E-06 ROOM PURGE EXHAUST INSIDE ISOL . 1VP020B INCORE CN-1576-01.00 I A PASS 2 24 BF AO c c c LTJ J INSTRUMENTATION E-05 ROOM PURGE EXHAUST OUTSIDE ISOL . 1VQ002A VQ FAN SUCT FROM CN-1585-01.00 /I- A ACT 2 4 DA MO c c FAI RPI 2Y CONT ISOL 02 LTJ J FSC Q ST-C Q 1VQ003B VQ FAN SUCT FROM CN-1585-01.00/ A ACT 2 4 GA MO c c FAI RPI 2Y CONT ISOL G-02 LTJ . J FSC Q ST-C Q 1VQ015B CONT AIR ADD CONT CN-1585-01.00 /I- A ACT 2 4 GA MO c c FAI RPI 2Y ISOL 12 LTJ J FSC Q ST-C Q 1VQ016A CONT AIR ADD CONT CN-1585-01.00 I J- A ACT 2 4 DA MO c c FAI RPI. 2Y ISOL 12 LTJ J FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 106 of 222 Valve Summary Listing Page 106 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1VS054B VS CONT ISOL CN-1605-02.01 I A ACT 2 3 GA MO c c FAI RPI 2Y G-10 LTJ J FSC Q ST-C Q 1VS056 UNIT 1 CONTAINMENT CN-1605-02.01 I A/C ACT 2 CK SA c c N/A BOO II HEADER CHECK G-12 eve II LTJ J 1VX001A 1A HYDROGEN SKIMMER CN-1557-01.00 I B ACT 2 12 BF MO c 0 FAI RPI 2Y FAN INLET ISOL G-03 FSO Q ST-0 Q 1VX002B 1B HYDROGEN SKIMMER CN-1557-01.00/ B ACT 2 12 BF MO c 0 FAI RPI 2Y FANINLETISOL G-14 FSO Q ST-0 Q 1VY015B VY INLT BLWR DISCH CN-1559-01.00 I F- A PASS 2 4 GA MO c c FAI RPI 2Y ISOL

07 LTJ J 1VY016 CONTAINMENT H2 CN-1559-01.00 I A/C ACT 2 4 CK SA OIC c N/A BOO II PURGE INLET BLOWER D-07 DISCH CHECK eve II LTJ J 1VY017A CONTAINMENT H2 CN-1559-01.00/ A PASS 2 4 GA MO c c FAI RPI 2Y PURGE OUTLET D-04 CONTAINMENT ISOL LTJ J

Catawba 4.terval Standa_9>de ISTC Catawba Nuclear Plant Interval 4 . IST 1.0.6 Page 107 of 222 Valve Summary Listing Page 107 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1VY018B VY OTLT CONT ISOL CN-1559-01.00 IF- A PASS 2 4 GA MO c c FAI RPI 2Y 04 LTJ . J 1WE020 CONTAINMENT BUILDING CN-1568-01.00 I A PASS 2 1 GL MA c c N/A LTJ J SUPPLY OUTSIDE ISOL E-11 1WE022 CONTAINMENT BLDG CN-1568-01.00/ A PASS 2 1 GL MA c c N/A LTJ J SUPPLY INSIDE ISOL E-13 1WL022 1B ND & NS SUMP PUMP CN-1565-01.01 I c ACT 3 3 CK SA OIC OIC NIA eve II DISCH CHECK C-08 cvo II 1WL024 1A ND & NS SUMP PUMP CN-1565-01.01 / c ACT 3 3 CK SA OIC OIC N/A eve II DISCH CHECK C-08 cvo II 1WL026 2B ND & NS SUMP PUMP CN-1565-01.01 / c ACT 3 3 CK SA OIC O/C NIA eve II DISCH CHECK C-12 cvo II 1WL028 2A ND & NS SUMP PUMP CN-1565-01.01 / c ACT 3 3 CK SA O/C O/C N/A eve II DISCH CHECK D-13 cvo II 1WL321 INCORE INSTRUMENT CN-1565-02.04 / A/C ACT 2 0.75 CK SA O/C OIC N/A eve II SUMP PUMP DISCH TEST H-06 DRAIN CHECK cvo II LTJ J 1WL450A NCDT VENT CONT ISOL CN-1565-02.00 /I- A ACT 2 0.75 GL MO 0 c FAI RPI 2Y 04 LTJ J FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC . Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 108 of 222 Valve Summary Listing Page 108 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1WL451B NCDT VENT CONT ISOL CN-1565-02.00 I J- A ACT 2 0.75 GL MO 0 c FAI RPI 2Y 04 LTJ J FSC Q ST-C Q 1WL462 UNIT 1 NCDT RELIEF CN-1565-02.00 I c ACT NC 2 RV SA c OIC N/A RV I VALVE H-03 1WL805A NCDT PUMP DISCH CONT CN-1565-02.00 /I- A ACT 2 3 GA MO 0 c FAI RPI 2Y ISOL 08 LT 2Y FSC Q ST-C Q 1WL806 NCDT PUMP DISCH CONT CN-1565-02.00 /I- A/C ACT 2 0.5 CK SA OIC OIC NIA eve II ISOL BYPASS 08 cvo II LTJ J 1WL807B NCDT PUMPS DISCH CN-1565-02.00 I J- A ACT 2 3 GA MO 0 c FAI RPI 2Y CONT ISOL 08 LT 2Y FSC Q ST-C Q 1WL825A UNIT 1 CONTAINMENT CN-1565-02.04 / A ACT 2 4 GA MO 0 c FAI RPI 2Y SUMP PUMPS DISCH H-07 CONTAINMENT ISOL LT 2Y FSC Q ST-C Q (.'r.

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Catawba terval Standa1 ode ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 109 of 222 Valve Summary Listing Page 109 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1WL826 INCORE CN-1565-02.04 / c ACT NC 0.75 RV SA c OIC NIA RV I INSTRUMENT/CONTAl NM H-10 ENT AND EQUIP SUMP PUMPS DISCH REL 1WL827B CONT SMP PMPS DISCH CN-1565-02.04 / J- A ACT 2 4 GA MO 0 c FAI RPI 2Y CONT ISOL 07

                                                                 .                                       LT  2Y FSC   Q ST-C  Q 1WL830  CAPT#1 SUMP PUMP 1A     CN-1565-02.02 /    c   ACT    3      2   CK    SA   O/C   OIC     N/A  eve   II DISCH CHECK                  H-04 cvo   II 1WL832  CAPT# 1 SUMP PUMP 1B    CN-1565-02.02 /    c   ACT    3      2   CK    SA   O/C   OIC     N/A  eve   II DISCH CHECK                  H-05 cvo   II 1WL838  1A CA PUMP SUMP PUMP    CN-1565-02.02 /    c   ACT    3      2   CK    SA   OIC   OIC     N/A  eve   II DISCH CHECK                  D-08 cvo   II 1WL840  1B CA PUMP SUMP PUMP    CN-1565-02.02 /    c   ACT    3      2   CK    SA   OIC   OIC     N/A  eve   II DISCH CHECK                  D-11 cvo   II 1WL847  FLOOR DRAIN SUMP D      CN-1565-02.02 /    B   ACT    3      4   PL    AO    c     0       0    FO   Q DISCH TO ND & NS SUMP        K-07 FSO   Q 1WL848  FLOOR DRAIN SUMP D      CN-1565-02.02 /    B   ACT    3      4   PL    AO    0     c       c    FC   Q DISCH TO TURBINE BLDG        K-08 SUMP FSC   Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 110 of 222 Valve Summary Listing Page 110 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1WL850 CA PUMP ROOM SUMP CN-1565-02.02 / J- c ACT 3 4 CK SA OIC 0 NIA BDC II DISCHARGE HEADER 09 CHECK VALVE cvo II 1WL867A VUCDT CONTAINMENT CN-1565-02.01 /I- A ACT 2 4 GA MO 0 c FAI RPI 2Y ISOL 07 LT 2Y FSC Q ST-C Q 1WL868 VUCDT CONTAINMENT CN-1565-02.01 / I- A/C ACT 2 1 CK SA O/C c N/A BDO II ISOL BYPASS CHECK 06 eve II LTJ J 1WL869B VUCDT CONTAINMENT CN-1565-02.01 I A ACT 2 4 GA MO 0 c FAI RPI 2Y ISOL H-07 LT 2Y FSC Q ST-C Q 1WL894 FLOOR DRAIN SUMP D CN-1565-02.02 /I- c ACT 3 2 CK SA OIC c N/A BDO II PUMPS DISCH CHECK 08 eve II 1WLA21 SIG DRAIN PUMP DISCH CN-1565-02.06 / J- A PASS 2 3 GA MA c c N/A LT 2Y CONTAINMENT ISOL 10 1WLA22 S/G DRAIN PUMP DISCH CN-1565-02.06 / A/C ACT 2 0.75 CK SA O/C OIC N/A eve II CONTAINMENT ISOL K-10 BYPASS cvo II LTJ J 1WLA24 LJ.NIT 1 S/G DRAIN PUMP CN-1565-02.06 / J- A PASS 2 3 GA MA c c N/A LT 2Y CH CONTAINMENT 12 "

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Catawba 4-erval Stand a de ISTC Catawba Nuclear Plant Interval 4

IST 1.0.6 Page 111 of 222 Valve Summary Listing Page 111 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1WN004 1A DIG ENG SUMP PUMP CN-1609-07.00 I J- c ACT 3 3 CK SA O/C 0 N/A 8DC II 1A1 DISCH CHECK 6 cvo II 1WN006 1A D/G ENG SUMP PUMP CN-1609-07.00 I J- c ACT 3 3 CK SA OIC 0 N/A 8DC II 1A2 DISCH CHECK 9 cvo II 1WN012 18 D/G ENG SUMP PUMP CN-1609-07.00 I c ACT 3 3 CK SA OIC 0 N/A 8DC II 181 DISCH CHECK E-6 cvo II 1WN014 18 D/G ENG SUMP PUMP CN-1609-07.00 I c ACT 3 3 CK SA O/C 0 NIA 8DC II 182 DISCH CHECK E-9 cvo II 1YC068 YC COMPRESSION TANK CN-1578-02.00 I c ACT 3 1 RV SA 0 OIC N/A RV I A RELIEF 8-10 1YC077A YC LOOP-A M/U ISOL CN-1578-02.00 I 8 ACT 3 2 GA MO 0 c FAI RPI 2Y D-12 FSC Q ST-C Q 1YC112 YC COMPRESSION TANK CN-1578-02.02 / c ACT 3 1 RV SA 0 OIC N/A RV I 8 RELIEF 8-10 1YC1218 YC LOOP-8 MIU ISOL CN-1578-02.02 / 8 ACT 3 2 GA MO 0 c FAI RPI 2Y D-12 FSC Q ST-C Q 1YM1198 YM CONT ISOL CN-1601-03.01 I A ACT 2 GL MO 0 c FAI RPI 2Y E-06 LTJ J FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 112 of 222 Valve Summary Listing Page 112 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1YM121 UNIT-1 CONTAINMENT CN-1601-03.01 / AIC ACT 2 CK SA OIC c N/A BDO II . YM HEADER CHECK E-05 eve II LTJ J

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Catawba Catawba Nuclear Plant Interval 4 Standa1 odelSTC IST 1.0.6 Page 113 of 222 Valve Summary Listing Page 113 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2BB008A S/G 20 SLOWDOWN CN-2580-01.00 I J- B ACT 2 4 GA MO 0 c FAI RPI 2Y INSIDE CONT ISOL 05 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 2880108 S/G 20 BLOWN CONT CN-2580-01.00 I J- B ACT 2 4 GA MO 0 c FAI RPI 2Y ISOLOTSD 06 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 2BB019A SIG 28 SLOWDOWN CN-2580-01.00 I B ACT 2 4 GA MO 0 c FAI RPI 2Y INSIDE CONT ISOL D-05 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 2880218 SIG 28 BLDWN CONT CN-2580-01.00 I B ACT 2 4 GA MO 0 c FAI RPI 2Y ISOLOTSD D-06 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 288052 20 S/G SLOWDOWN CN-2580-01.00 I J- c ACT 2 0.75 CK SA O/C OIC N/A eve II CONT ISOL PRESS 05 RELIEF CHECK cvo II 288053 2A SIG SLOWDOWN CN-2580-01.00 I c ACT 2 0.75 CK SA OIC O/C N/A eve II CONT ISOL PRESS H-05 RELIEF CHECK cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 114 of 222 Valve Summary Listing Page 114 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 288054 2C SIG SLOWDOWN CN-2580-01.00 IF- c ACT 2 0.75 CK SA OIC OIC NIA eve II CONT ISOL PRESS 05 RELIEF CHECK cvo II 288055 28 SIG SLOWDOWN CN-2580-01.00 I c ACT 2 0.75 CK SA OIC OIC NIA eve II CONT ISOL PRESS D-05 RELIEF CHECK cvo II 2BB056A SIG 2A SLOWDOWN CN-2580-01.00 I B ACT 2 4 GA MO 0 c FAI RPI 2Y INSIDE CONT ISOL H-05 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 2880578 SIG 2A BLOWN CONT CN-2580-01.00 I B ACT 2 4 GA MO 0 c FAI RPI 2Y ISOLOTSD H-06 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 2BB060A SIG 2C SLOWDOWN CN-2580-01.00 IF- B ACT 2 4 GA MO 0 c FAI RPI 2Y INSIDE CONT ISOL 05 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-01 2880618 SIG 2C BLOWN CONT CN-2580-01.00 IF- B ACT 2 4 GA MO 0 c FAI RPI 2Y ISOL OTSD 06 FSC cs CSJ-CN-BB-01 ST-C cs CSJ-CN-BB-

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Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 115 of 222 Valve Summary Listing Page 115 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2BB147B S/G 20 BLOWN CONT CN-2580-01.00 I B ACT 2 4 GL MO c c FAI RPI 2Y ISOL BYP K-06 FSC Q ST-C Q

2BB148B SIG 2A BLOWN CONT CN-2580-01.00 / I- B ACT 2 4 GL MO c c FAI RPI 2Y ISOL BYP 06 FSC Q ST-C Q 2BB149B S/G 2C BLOWN CONT CN-2580-01.00 I B ACT 2 4 GL MO c c FAI RPI 2Y ISOL BYP G-06 FSC Q ST-C Q 2BB150B S/G 2B BLOWN CONT CN-2580-01.00 I B ACT 2 4 GL MO c c FAI RPI 2Y ISOL BYP E-06 FSC Q ST-C Q 2CA008 CAPT #2 SUCTION CN-2592-01.00 I c ACT 3 10 CK SA OIC OIC N/A eve II CHECK 0-09 cvo II 2CA010 2B CA PUMP SUCTION CN-2592-01.00 I c ACT 3 10 CK SA c OIC N/A eve II CHECK 0-05 cvo II 2CA012 2A CA PUMP SUCTION CN-2592-01.00 I c ACT 3 6 CK SA O/C O/C N/A eve II CHECK 0-01 cvo II 2CA015A CA PUMP 2A SUCT FRM CN-2592-01.00 I B ACT 3 6 GA MO c 0 FAI RPI 2Y RN ISOL 0-02 FSO Q ST-0 Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 116 of 222 Valve Summary Listing Page 116 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CA0188 CA PUMP 28 SUCT FRM CN-2592-01.00 I 8 ACT 3 6 GA MO c 0 FAI RPI 2Y RN ISOL D-06 FSO Q ST-0 Q 2CA020 CAPT #2 MINI FLOW CN-2592-01.00 /I- c ACT 3 6 CK SA OIC OIC N/A eve Q CONTROL 11 cvo Q 2CA023 CAPT #2 MINIFLOWTO CN-2592-01.00 I J- c ACT 3 2.5 CK SA OIC O/C N/A eve II UST DOME CHECK 10 cvo II 2CA027 2A CA PUMP MINI FLOW CN-2592-01.00 / I- c ACT 3 4 CK SA OIC OIC N/A eve Q CONTROL 04 cvo Q 2CA028 2A CA PUMP MINI FLOW CN-2592-01.00 I J- c ACT 3 2 CK SA O/C OIC NIA eve II TO UST DOME CHECK 03 cvo II 2CA032 28 CA PUMP MINI FLOW CN-2592-01.00 /I- c ACT 3 4 CK SA OIC OIC N/A eve Q CONTROL 07 cvo Q 2CA033 28 CA PUMP MINIFLOW CN-2592-01.00 I J- c ACT 3 2 CK SA O/C OIC N/A eve II TO UST DOME CHECK 07 cvo II 2CA036 CA PUMP #2 FLOW TO CN-2592-01.01 I 8 ACT 3 4 FC AO 0 0 0 RPI 2Y S/G2D C-12 FO Q FSO Q ST-0 Q 2CA037 CAPT #2 DISCH TO 2D CN-2592-01.01 I c ACT 2 4 CK SA O/C OIC N/A eve. II SIG CHECK G-12 cvo II

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Catawba 4' terval Stand a de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 117 of 222 Valve Summary Listing Page 117 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL -2CA038A CA PMP 2 DISCH TO SIG CN-2592-01.01 I 8 ACT 2 4 GA MO 0 O/C FAI RPI 2Y 2D ISOL H-12 FSC Q FSO Q ST-C Q ST-0 Q 2CA040 CA PUMP 28 FLOW TO CN-2592-01.01 I J- 8 ACT 3 4 FC AO 0 0 0 RPI 2Y S/G2D 12 FO Q FSO Q ST-0 Q 2CA041 28 CA PUMP DISCH TO CN-2592-01.01 / I- c ACT 2 4 CK SA O/C OIC N/A eve II 20 S/G CHECK 12 cvo II 2CA0428 CA PMP 8 DISCH TO SIG CN-2592-01.01 / I- 8 ACT 2 4 GA MO 0 OIC FAI RPI 2Y 2DISOL 12 FSC Q FSO Q ST-C Q ST-0 Q 2CA044 CA PUMP 28 FLOW TO CN-2592-01.01 I J- 8 ACT 3 4 FC AO 0 0 0 RPI 2Y S/G2C 09 FO Q FSO Q ST-0 Q 2CA045 28 CA PUMP DISCH TO CN-2592-01.01 /I- c ACT 2 4 CK SA OIC OIC N/A eve II 2C SIG CHECK 09 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 118 of 222 Valve Summary Listing Page 118 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CA046B CA PMP B DISCH TO S/G CN-2592-01.01 /I- B ACT 2 4 GA MO 0 O/C FAI RPI 2Y 2C ISOL 09 FSC Q FSO Q ST-C Q ST-0 Q 2CA048 CA PUMP #2 FLOW TO CN-2592-01.01 I B ACT 3 4 FC AO 0 0 0 RPI 2Y S/G2C C-09 FO Q FSO Q ST-0 Q 2CA049 CAPT #2 DISCH TO 2C CN-2592-01.01 I c ACT 2 4 CK SA OIC O/C NIA eve II S/G CHECK G-09 cvo II 2CA050A CA PMP 2 DISCH TO S/G CN-2592-01.01 I B ACT 2 4 GA MO 0 O/C FAI RPI 2Y 2CISOL H-09 FSC Q FSO Q ST-C Q ST-0 Q 2CA052 CA PUMP #2 FLOW TO CN-2592-01.01 I B ACT 3 4 FC AO 0 0 0 RPI 2Y S/G2B C-06 FO Q FSO Q ST-0 Q 2CA053 CAPT #2 DISCH TO 28 CN-2592-01.01 I c ACT 2 4 CK SA OIC OIC N/A eve II SIG CHECK G-06 cvo II

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Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 119 of 222 Valve Summary Listing Page 119 of 222 VALVE ID FUNCTION DRAWING/COOR CAT* ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CA0548 CA PMP 2 DISCH TO SIG CN-2592-01.01 I 8 ACT 2 4 GA MO 0 OIC FAI RPI 2Y 28 ISOL H-06 FSC Q FSO Q ST-C Q ST-0 Q 2CA056 CA PUMP 2A FLOW TO CN-2592-01.01 I J- 8 ACT 3 4 FC AO 0 0 0 RPI 2Y SIG28 06 FO Q FSO Q ST-0 Q 2CA057 2A CA PUMP DISCH TO CN-2592-01.01 11- c ACT 2 4 CK SA OIC OIC N/A eve II 28 SIG CHECK 06 cvo II 2CA058A CA PMP A DISCH TO SIG CN-2592-01.01 11- 8 ACT 2 4 GA MO 0 OIC FAI RPI 2Y 28 ISOL 06 FSC Q FSO Q ST-C Q ST-0 Q 2CA060 CA PUMP 2A FLOW TO CN-2592-01.01 I J- 8 ACT 3 4 FC AO 0 0 0 RPI 2Y SIG2A 03 FO Q FSO Q ST-0 Q 2CA061 2A CA PUMP DISCH TO CN-2592-01.01 /I- c ACT 2 4 CK SA OIC OIC N/A eve II 2A SIG CHECK 03 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 120 of 222 Valve Summary Listing Page 120 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CA062A CA PUMP A DISCH TO CN-2592-01.01 /I- B ACT 2 4 GA MO 0 OIC FAI RPI 2Y S/G2A ISOL 03 FSC Q FSO Q ST-C Q ST-0 Q 2CA064 CA PUMP #2 FLOW TO CN-2592-01.01 I B ACT 3 . 4 FC AO 0 0 0 RPI 2Y S/G2A C-03

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Catawba terval Standa1 ode ISTC Catawba Nuclear Plant Interval 4 J* IST 1.0.6 Page 121 of 222 Valve Summary Listing Page 121 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CA149 2A SIG CF BYPASS TO CA CN-2592-01,01 /I- B ACT 2 6 GA AO 0 c c RPI 2Y NOZZLE 01 FC cs CSJ-CN-CA-05 FSC cs CSJ-CN-CA-05 ST-C cs CSJ-CN-CA-05 2CA150 2B S/G CF BYPASS TO CA CN-2592-01.01 /I- B ACT 2 6 GA AO 0 c c RPI 2Y NOZZLE 05 FC cs CSJ-CN-CA-05 FSC cs CSJ-CN-GA-05 ST-C cs CSJ-CN-CA-05 2CA151 . 2G SIG CF BYPASS TO CA CN-2592-01.01 /I- B ACT 2 6 GA AO 0 c c RPI 2Y NOZZLE 08 FC cs CSJ-CN-CA-05 FSC cs CSJ-CN-CA-05 ST-C cs CSJ-CN-CA-05 2CA152 20 S/G CF BYPASS TO CA CN-2592-01.01 /I- B ACT 2 6 GA AO 0 c c RPI 2Y NOZZLE 11 FC cs CSJ-CN-CA-05 FSC cs CSJ-CN-CA-05 ST-C cs CSJ-CN-CA-05

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 122 of 222 Valve Summary Listing Page 122 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CA173 RC TO CA SUCTION CN-2592-01.00 I c ACT 3 8 CK SA O/C c N/A BOO II CHECK E-07 eve II 2CA174 RC TO CA SUCTION ISOL CN-2592-01.00 I B PASS 3 8 BF AO c c 0 RPI 2Y E-07 2CA185 2A S/G CA NOZZLE CN-2592-01.01 I B ACT 2 2 GA AO 0 c c RPI 2Y TEMPERING ISOL E-01 FC Q FSC Q ST-C Q 2CA186 2B SIG CA NOZZLE CN-2592-01.01 I B ACT 2 2 GA AO 0 c c RPI 2Y TEMPERING ISOL E-05 FC Q FSC Q ST-C Q 2CA187 2C S/G CA NOZZLE CN-2592-01.01 I B ACT 2 2 GA AO 0 c c RPI 2Y TEMPERING ISOL E-08 FC Q FSC Q ST-C Q 2CA188 20 S/G CA NOZZLE CN-2592-01.01 I B ACT 2 2 GA AO 0 c c RPI 2Y TEMPERING ISOL E-11 FC Q FSC Q ST-C Q 2CA255 2A CA PUMP SUCTION CN-2592-01.00 I F- c ACT 3 0.75 RV SA c OIC NIA RV I RELIEF 01 2CA256 2B CA PUMP SUCTION CN-2592-01.00 IF- c ACT 3 0.75 RV SA c O/C N/A RV I RELIEF 05 2CA257 CAPT #2 SUCTION CN-2592-01.00 IF- c ACT 3 0.75 RV SA c O/C N/A RV I _,* ~£'.F. 09 . *:.: '\ ~

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IST 1.0.6 Page 123 of 222 Valve Summary Listing Page 123 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CA291 RN TO CA X-OVER TRAIN CN-2592-01.00 I c ACT 3 6 CK SA OIC O/C N/A eve II 2A CHECK 0-8 cvo II 2CA292 RN TO CA X-OVER TRAIN CN-2592-01.00 I c ACT 3 6 CK SA OIC OIC N/A eve II 2B CHECK 0-7 cvo II 2CF028 2A S/G CF CONTROL CN-2591-01.01 I J- B ACT 3 16 FC AO 0 c c RPI 2Y 13 FC cs CSJ-CN-CF-04 FSC cs CSJ-CN-CF-04 ST-C cs CSJ-CN-CF-04 2CF030 2A S/G CF BYPASS CN-2591-01.01 I J- B ACT NC 6 FC AO 0 c c RPI 2Y CONTROL 11 FC cs CSJ-CN-CF-05 FSC cs CSJ-CN-CF-05 ST-C cs CSJ-CN-CF-05 2CF031 2A S/G FEEOWATER CN-2591-01.01 I c ACT 2 18 CK SA OIC c N/A BOO II CONTAINMENT ISOL G-13 INLET CHECK eve II 2CF033 2A SIG CF CONTAINMENT CN-2591-01.01 IF- B ACT 2 18 GA HO 0 c c RPI 2Y ISOL 13 FC cs CSJ-CN-CF-01 FSC cs CSJ-CN-CF-01 ST-C cs CSJ-CN-CF-01 2CF035 SIG 2A FEEOWATER CN-2591-01.01 I c ACT 2 16 CK SA OIC c N/A BOO II INLET CHECK 0-13 eve II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 124 of 222 Valve Summary Listing Page 124 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CF037 28 SIG CF CONTROL CN-2591-01.01 I J- B ACT 3 16 FC AO 0 c c RPI 2Y 09 FC cs CSJ-CN-CF-04 FSC cs CSJ-CN-CF-04 ST-C cs CSJ-CN-CF-04 2CF039 28 S/G CF BYPASS CN-2591-01.01 I J- B ACT NC 6 FC AO 0 c c RPI 2Y CONTROL 11 FC cs CSJ-CN-CF-05 FSC cs CSJ-CN-CF-05 ST-C cs CSJ-CN-CF-05 2CF040 28 SIG FEEDWATER CN-2591--01.01 I c ACT 2 18 CK SA OIC c NIA BDO II CONTAINMENT ISOL G-09 INLET CHECK eve II 2CF042 28 S/G CF CONTAINMENT CN-2591-01.01 IF- B ACT 2 18 GA HO 0 c c RPI 2Y ISOL 09 FC cs CSJ-CN-CF-01 FSC cs CSJ-CN-CF-01 ST-C cs CSJ-CN-CF-01 2CF044 28 SIG FEEDWATER CN-2591--01.01 I c ACT 2 16 CK SA OIC c N/A BDO II INLET CHECK D--09 eve II 2CF046 2C S/G CF CONTROL CN-2591-01.01 I J- B ACT 3 16 FC AO 0 c c RPI 2Y 06 FC cs CSJ-CN-CF-04 FSC cs CSJ-CN-CF-04 ST-C cs CSJ-CN-CF-04

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Catawba terval Standa' 'ode ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 125 of 222 Valve Summary Listing Page *125 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CF048 2C SIG CF BYPASS CN-2591-01.01 I J- B ACT NC 6 FC AO 0 c c RPI 2Y CONTROL 05 FC cs CSJ-CN-CF-05 FSC cs CSJ-CN-CF-05 ST-C cs CSJ-CN-CF-05 2CF049 2C SIG FEEOWATER CN-2591-01.01 I c ACT 2 18 CK SA OIC c N/A BOO II CONTAINMENT ISOL G-06 INLET CHECK eve II 2CF051 2C SIG CF CONTAINMENT CN-2591-01.01 IF- B ACT 2 18 GA HO 0 c c RPI 2Y ISOL 06 FC cs CSJ-CN-CF-01 FSC cs CSJ-CN-CF-01 ST-C cs CSJ-CN-CF-01 2CF053 2C SIG FEEOWATER CN-2591-01.01 I c ACT 2 16 CK SA OIC c N/A BOO II INLET CHECK 0-06 eve II 2CF055 20 SIG CF CONTROL CN-2591-01.01 I J- B ACT 3 16 FC AO 0 c c RPI 2Y 03 FC cs CSJ-CN-CF-04 FSC cs CSJ-CN-CF-04 ST-C cs CSJ-CN-CF-04 2CF057 20 SIG CF BYPASS CN-2591-01.01 I J- B ACT NC 6 FC AO 0 c c RPI 2Y CONTROL 04 FC cs CSJ-CN-CF-05 FSC cs CSJ-CN-CF-05 ST-C cs CSJ-CN-CF-05

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 126 of 222 Valve Summary Listing Page 126 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CF058 20 SIG FEEOWATER CN-2591-01.01 I c ACT 2 18 CK SA O/C c NIA BOO II CONTAINMENT ISOL G-03 INLET CHECK eve II 2CF060 20 S/G CF CONT ISOL CN-2591-01.01 I F- B ACT 2 18 GA HO 0 c c RPI 2Y 03 FC cs CSJ-CN-CF-01 FSC cs CSJ-CN-CF-01 ST-C cs CSJ-CN-CF-01 2CF062 2D SIG FEEOWATER CN-2591-01.01 I c ACT 2 16 CK SA OIC c NIA BOO II INLET CHECK 0-03 eve II 2CF087 2D SIG CF CONTAINMENT CN-2591-01.01 I F- B ACT 2 2 GA AO c c c RPI 2Y ISOL BYPASS 02 FC Q FSC Q ST-C Q 2CF088 2C SIG CF CONTAINMENT CN-2591-01.01 I F- B ACT 2 2 GA AO c c c RPI 2Y ISOL BYPASS 06 FC Q FSC Q ST-C Q 2CF089 2B SIG CF CONTAINMENT CN-2591-01.01 IF- B ACT 2 2 GA AO c c c RPI 2Y ISOLBYPASS 09 FC Q FSC Q ST-C Q i.,,

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Catawba 4'9terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 127 of 222 Valve Summary Listing Page 127 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CF090 2A S/G CF CONTAINMENT CN-2591-01.01 I F- B ACT 2 2 GA AO c c c RPI 2Y ISOL BYPASS 13 FC Q FSC Q ST-C Q 2CF166 2A SIG CF TO AUX CN-2591-01.01 I c ACT 2 6 CK SA OIC O/C NIA eve II FEEDWATER NOZZLE G-13 CHECK cvo II 2CF167 2B S/G CF TO AUX CN-2591-01.01 I c ACT 2 6 CK SA OIC OIC N/A eve II FEEDWATER NOZZLE G-09 CHECK cvo II 2CF168 2C SIG CF TO AUX CN-2591-01.01 I c ACT 2 6 CK SA O/C OIC N/A eve II FEEDWATER NOZZLE G-06 CHECK cvo II 2CF169 2D SIG CF TO AUX CN-2591-01.01 I c ACT 2 6 CK SA OIC OIC N/A eve II FEEDWATER NOZZLE G-02 CHECK cvo II 2FD022 2A DIG ENG FUEL OIL CN-2609-03.00 I B ACT 3 2 sv so c 0 c RPI 2Y DAY TANK2A FILL H-12 FC Q FSO Q ST-0 Q 2FD023 2A DIG ENG FUEL OIL CN-2609-03.00 I J- B ACT 3 2 PL MA c O/C NIA FS 2Y DAYTANK2A FILL VALVE 12 BYPASS 2FD062 2B DIG ENG FUEL OIL CN-2609-03.01 I B ACT 3 2 sv so c 0 c RPI 2Y DAY TANK 2B FILL H-12 FC Q FSO Q ST-0 Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 128 of 222 Valve Summary Listing Page 128 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2FD063 28 DIG ENG FUEL OIL CN-2609-03.01 I J- B ACT 3 2 PL MA c OIC N/A FS 2Y DAY TANK28 FILL VALVE 12 BYPASS 2FW001A FWLOOP ISOL CN-2571-01.00 I J- B ACT 2 8 GA MO c c FAI RPI 2Y 13 FSC Q ST-C Q 2FW004 FW PUMP RETURN TO CN-2571-01.00 IL- A PASS 2 6 GA MA c c N/A LTJ J REFUELING CAVITY 07 CONTAINMENT ISOL 2FW005 FW PUMP RETURN TO CN-2571-01.00/ L- A/C ACT 2 6 CK SA OIC OIC N/A eve II REFUELING CAVITY CHK 05 cvo II LTJ J 2FW011 REFUELING CAVITY TO CN-2571-01.00 I J- A PASS 2 4 PL MA c c N/A LTJ J FW PUMP CONT ISOL 04 2FW013 REFUELING CAVITY TO CN-2571-01.00 I J- A PASS 2 4 PL MA c c N/A LTJ J FW PUMP CONTAINMENT 05 ISOL 2FW027A NDPUMP2ASUCTFROM CN-2571-01.00 IF- B ACT 2 12 GA MO 0 O/C FAI RPI 2Y FWST 03 FSC Q FSO Q ST-C Q ST-0 Q 2FW028 2A ND PUMP SUCTION CN-2571-01.00 IF- c ACT 2 12 CK SA OIC OIC N/A eve II FROM FWST CHECK 02 cvo II 2FW032B FWLOOP ISOL CN-2571-01.00 I J- B ACT 2 8 GA MO c c FAI RPI 2Y 13 FSC Q

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IST 1.0.6 Page 129 of 222 Valve Summary Listing Page 129 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2FW033A FWST RECIRC LOOP CN-2571-01.00 I B ACT 2 2 GL MO 0 c FAI RPI 2Y ISOL 8-08 FSC Q ST-C Q 2FW049B FWST RECIRC LOOP CN-2571-01.00 I B ACT 2 2 GL MO 0 c FAI RPI 2Y ISOL B-08 FSC Q ST-C Q 2FW052 NS/NI TEST LINE TO CN-2571-01.00 I c ACT NC 4 CK SA O/C 0 N/A BOC II FWST CHECK E-10 cvo II 2FW055B NDPUMP2BSUCTFROM CN-2571-01.00 I B ACT 2 12 GA MO 0 O/C FAI RPI 2Y FWST H-03 FSC Q FSO Q ST-C Q ST-0 Q 2FW056 28 ND PUMP SUCTION CN-2571-01.00 I c ACT 2 12 CK SA OIC O/C N/A eve II FROM FWST CHECK H-02 cvo II 2FW096 2A ND PUMP SUCTION CN-2571-01.00 I c ACT 2 0.75 CK SA O/C O/C N/A eve II HOR PRESSURE E-02 CONTROL CHECK cvo II 2FW097 28 ND PUMP SUCTION CN-2571-01.00 I c ACT 2 0.75 CK SA O/C O/C N/A eve II HOR PRESSURE G-02 CONTROL CHECK cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 130 of 222 Valve Summary Listing Page 130 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 21ACK5340 UPPER PERSONNEL AIR CN-2499-1A.01-01 AIC ACT 2 0.5 CK SA OIC c N/A BOO II LOCK CONTROL I eve II LTJ J 21ACK5350 LOWER PERSONNEL AIR CN-2499-1A.01-01 A/C ACT 2 0.5 CK SA OIC c NIA BOO II LOCK CONTROL I eve II LTJ J 21ACK5360 UPPER PERSONNEL AIR CN-2499-1A.01-01 AIC ACT 2 0.5 CK SA OIC c NIA BOO II LOCK CONTROL I eve II LTJ J 21ACK5370 LOWER PERSONNEL AIR CN-2499-1A.01-01 AIC ACT 2 0.5 CK SA OIC c NIA BOO II LOCK CONTROL I eve II LTJ J 21ACK5380 UPPER PERSONNEL AIR CN-2499-1A.01-01 A/C ACT 2 0.5 CK SA OIC c NIA BOO II LOCK CONTROL I eve II LTJ J 21ACK5390 LOWER PERSONNEL AIR CN-2499-1 A.01-01 A/C ACT 2 0.5 CK SA OIC c NIA BOO II LOCK CONTROL I eve II LTJ J 21ASV5080 UPPER PERSONNEL AIR CN-2499-1A.01-01 A ACT 2 0.5 sv so 0 c c RPI 2Y LOCK CONTROL I LTJ J FC Q FSC Q

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Catawba 49terval Standa-Catawba Nuclear Plant Interval 4 Page 131 of 222 Valve Summary.Listing Page 131 of 222 VALVE ID FUNCTION DRAWING/COOR CAT *ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 21ASV5160 LOWER PERSONNEL AIR CN-2499-1A.01-01 A ACT 2 0.5 sv so 0 c c RPI 2Y LOCK CONTROL I LTJ J FC Q FSC Q ST-C Q 21ASV5400 UPPER PERSONNEL AIR CN-2499-1A.01-01 A ACT 2 0.5 sv so 0 c c RPI 2Y LOCK CONTROL I LTJ J FC Q FSC Q ST-C Q 21ASV5410 LOWER PERSONNEL CN-2499-1A.01-01 A ACT 2 0.5 sv so 0 c c RPI 2Y AIRLOCK CONTROL I LTJ J FC Q FSC Q ST-C Q 2KC001A AUX BLDG NON- CN-2573-01.00 I B ACT 3 20 BF MO 0 c FAI RPI 2Y ESSENTIAL RETURN C-06 HEADERISOL FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 132 of 222 Valve Summary Listing Page 132 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2KC002B AUX BLDG NON- CN-2573-01.00 I B ACT 3 20 BF MO 0 c FAI RPI 2Y ESSENTIAL RETURN C-09 HEADERISOL FSC Q ST-C Q 2KC003A RX BLDG NON- CN-2573-01.00 I B ACT 3 10 GA MO 0 c FAI RPI 2Y ESSENTIAL RETURN C-06 HEADERISOL FSC Q ST-C Q 2KC005 2A1 KC PUMP DISCH CN-2573-01.00 I c ACT 3 16 CK SA OIC OIC N/A eve II CHECK E-04 cvo II 2KC008 2A2 KC PUMP DISCH CN-2573-01.00 I c ACT 3 16 CK SA OIC OIC N/A eve II CHECK E-04 cvo II 2KC011 2B1 KC PUMP DISCH CN-2573-01.00 I c ACT 3 16 CK SA OIC OIC N/A eve II CHECK E-10 cvo II 2KC014 2B2 KC PUMP DISCH CN-2573-01.00 I c ACT 3 16 CK SA OIC O/C N/A eve II CHECK E-11 cvo II 2KC018B RX BLDG NON- CN-2573-01.00 I B ACT 3 10 GA MO 0 c FAI RPI 2Y ESSENTIAL RETURN C-09 HEADERISOL FSC Q ST-C Q t.i.,;

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Catawba 41 terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 133 of 222 Valve Summary Listing Page 1*33 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2KC047 RX BLDG DRAIN HEADER CN-2573-01.05 / A/C ACT 2 0.75 CK SA OIC O/C N/A eve II - PRESS EQUALIZATION H-04 CHECK cvo II LTJ J 2KC050A AUX BLDG NON- CN-2573-01.00 I J- B ACT 3 20 GA MO 0 c FAI RPI 2Y ESSENTIAL HEADER ISOL 12 FSC Q ST-C Q 2KC053B AUX BLDG NON- CN-2573-01.00 I B ACT 3 20 GA MO 0 c FAI RPI 2Y ESSENTIAL HEADER ISOL K-08 FSC Q ST-C Q 2KC056A KC TO ND HX 2A SUP CN-2573-02.00 I B ACT 3 16 BF MO c 0 FAI RPI 2Y ISOL E-03 FSO Q ST-0 Q 2KC057A 2A ND HX KC FLOW CN-2573-02.00 I J- B ACT 3 16 BL AO 0 0 0 RPI 2Y CONTROL 03

                                                                                                       . FO    Q FSO    Q ST-0  Q 2KC061  2A ND HX OUTLET       CN-2573-02.00 /I-   c   ACT   3       4   RV    SA    c    OIC     N/A   RV   I RELIEF                       04 2KC079  2A ND PUMP MECH SEAL  CN-2573-02.00 /I-   c   ACT   3     0.75  RV    SA    c    O/C     N/A   RV   I HX RELIEF                    07 2KC081B  KC TO ND HX 2B SUP     CN-2573-02.01 I    B   ACT   3      16   BF    MO    c     0      FAI   RPI  2Y ISOL                        E-03 FSO    Q ST-0  Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 134 of 222 Valve Summary Listing Page 134 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2KC082B 28 ND HX KC FLOW CN-2573-02.01 I J- B ACT 3 16 BL AO 0 0 0 RPI 2Y CONTROL 03 FO Q FSO Q ST-0 Q 2KC086 28 ND HX OUTLET CN-2573-02.01 I c ACT 3 0.75 RV SA c OIC N/A RV I RELIEF H-04 2KC104 28 ND PUMP MECH SEAL CN-2573-02.01 I c ACT 3 0.75 RV SA c OIC N/A RV I HX RELIEF H-04 2KC228B RX BLDG NON- CN-2573-01.00 I L- B ACT 3 8 GA MO 0 c FAI RPI 2Y ESSENTIAL HEADER ISOL 08 FSC Q ST-C Q 2KC230A RX BLDG NON- CN-2573-01.00 I L- B ACT 3 8 GA MO 0 c FAI. RPI 2Y ESSENTIAL HEADER ISOL 07 FSC Q ST-C Q 2KC279 NC PUMPS RETURN CN-2573-01.03 / A/C ACT 2 1 CK SA O/C OIC N/A eve II HEADER PRESS K-05 EQUALIZATION CHECK cvo II LTJ J 2KC280 NCDT HX COOLING CN-2573-01.03 / c ACT 2 1 CK SA O/C OIC N/A eve II WATER RETURN PRESS E-01 EQUALIZATION CHECK cvo II 2KC281 NC PUMPS SLOWDOWN CN-2573-01.03 / c ACT 2 3 RV SA c OIC NIA RV I HX'S RETURN HEADER K-03 RELIEF

Catawba 491erval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 135 of 222 Valve Summary Listing Page 135 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2KC305B EXS LETDN HX SUPPLY CN-2573-01.03 / A ACT 2 4 GA MO c c FAI RPI 2Y CONT ISOL D-13 LT 2Y FSC Q ST-C Q 2KC313 EXCESS LETDOWN HX CN-2573-01.03 /I- c ACT 3 0.75 RV SA c OIC N/A RV I OUTLET RELIEF TO KC 12 DRAIN SUMP 2KC315B EXS LETDN HX RET CN-2573-01.03 / L- A ACT 2 4 GA MO c c FAI RPI 2Y CONT ISOL 13 LT 2Y FSC Q ST-C Q 2KC320A NCDT HX COOL SUPPLY CN-2573-01.03 / A ACT 2 4 GA MO 0 c FAI RPI 2Y CONT ISOL B-10 LT 2Y FSC cs CSJ-CN-KC-01 ST-C cs CSJ-CN-KC-01 2KC322 NCDT HX SUPPLY CN-2573-01.03 / c ACT 2 4 CK SA OIC O/C N/A eve II HEADER CHECK B-08 cvo II 2KC330 NCDT HX OUTLET RELIEF CN-2573-01.03 / c ACT 3 0.75 RV SA c OIC N/A RV I TO KC DRAIN SUMP B-01 2KC332B NCDT HX COOLING CN-2573-01.03 / A ACT 2 4 GA MO 0 c FAI RPI 2Y RETURN CONT ISOL E-02 LT 2Y FSC cs CSJ-CN-KC-01 ST-C cs CSJ-CN-KC-01

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 136 of 222 Valve Summary Listing Page 136 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2KC333A NCDT HX COOL RET CN-2573-01.03 / A ACT 2 4 GA MO 0 c FAI RPI 2Y CONT ISOL G-02 LT 2Y FSC cs CSJ-CN-KC-01 ST-C cs CSJ-CN-KC-01 2KC338B NC PUMPS SUP HOR CN-2573-01.03 / A ACT 2 8 GA MO 0 c FAI RPI 2Y CONT ISOL D-12 LT 2Y FSC cs CSJ-CN-KC-02 ST-C cs CSJ-CN-KC-02 2KC340 NC PUMPS SUP HOR CN-2573-01.03 IF- AIC ACT 2 8 CK SA OIC OIC NIA eve II CHECK 12 cvo II LTJ J 2KC344 2C NC PUMP THERMAL CN-2573-01.07 I c ACT 2 2 CK SA O/C c N/A BOO II BARRIER HX INLET K-13 CHECK eve II 2KC355 2C NC PUMP MOTOR CN-2573-01.07 I c ACT 3 0.75 RV SA c O/C N/A RV I LOWER BRG COOLER K-10 RELIEF TO KC DRAIN SUMP 2KC361 2C NC PUMP MOTOR CN-2573-01.07 I c ACT 3 0.75 RV SA c OIC N/A RV I UPPER BRG COOLER H-08 RELIEF TO KC DRAIN SUMP 2KC363 2B NC PUMP THERMAL CN-2573-01.07 I c ACT 2 2 CK SA O/C c N/A BOO II BARRIER HX INLET K-06 CHECK eve II

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Catawba terval Stand ode ISTC i Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 137 of 222 Valve Summary Listing Page i137 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2KC374 NC PUMP 2B MOTOR CN-2573-01.07 I c ACT 3 0.75 RV SA c OIC N/A RV I LOWER BRG COOLER K-04 RELIEF TO KC DRAIN SUMP 2KC380 2B NC PUMP MOTOR CN-2573-01.07 I c ACT 3 0.75 RV SA c OIC N/A RV I UPPER BRG COOLER H-02 RELIEF TO KC DRAIN SUMP

. 2KC386   2A NC PUMP MOTOR      CN-2573-01.04 /    c   ACT   3     0.75  RV    SA    c    OIC    N/A    RV    I UPPER BRG COOLER           H-12

RELIEF TO KC DRAIN SUMP 2KC392 2A NC PUMP MOTOR CN-2573-01.04 / c ACT 3 0.75 RV SA c O/C N/A RV I LOWER BEARING K-10 COOLER RELIEF TO KC DRAIN SUM 2KC393 2A NC PUMP THERMAL CN-2573-01.04 / c ACT 2 2 CK SA O/C c N/A BOO II BARRIER HX INLET K-09 CHECK eve II 2KC404 20 NC PUMP MOTOR CN-2573-01.04 / c ACT 3 0.75 RV SA c O/C N/A RV I UPPER BRG COOLER H-06 RELIEF TO KC DRAIN SUMP 2KC410 2D NC PUMP MOTOR CN-2573-01.04 / J- c ACT 3 0.75 RV SA c OIC N/A RV I LOWER BRG COOLER 04 RELIEF TO KC DRAIN SUMP 2KC412 20 NC PUMP THERMAL CN-2573-01.04 I J- c ACT 2 2 CK SA OIC c N/A BOO II BARRIER INLET CHK 03 eve II 2KC424B NC PUMPS RETURN CN-2573-01.03 / L- A ACT 2 8 GA MO 0 c FAI RPI 2Y HEADER CONT ISOL 05 LT 2Y FSC cs CSJ-CN-KC-02 ST-C cs CSJ-CN-KC-02

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 138 of 222 Valve Summary Listing Page 138 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2KC425A NC PUMPS RET HDR CN-2573-01.03 / L- A ACT 2 8 GA MO 0 c FAI RPI 2Y CONT ISOL 07 LT 2Y FSC cs CSJ-CN-KC-02 ST-C cs CSJ-CN-KC-02 2KC429B RX BLDG DRAIN HEADER CN-2573-01.05 / A ACT 2 2 GL MO 0 c FAI RPI 2Y CONT ISOL H-03 LTJ J FSC Q ST-C Q 2KC430A RX BLDG DRN HOR CONT CN-2573-01.05 / J- A ACT 2 2 GL MO 0 c FAI RPI 2Y ISOL 03 LTJ J FSC Q ST-C Q *-----. ~- 2KC494 2A KC SURGE TANK CN-2573-01.01 I B ACT 3 4 BL MA c OIC N/A FS 2Y EMERGENCY RN M/U H-02 2KC495 2A KC SURGE TANK CN-2573-01.01 I c ACT 3 4 CK SA OIC OIC NIA eve II EMERGENCY RN MIU H-03 CHECK cvo II 2KC496 2A KC SURGE TANK CN-2573-01.01 I B ACT 3 4 PL MA c 0 N/A FS 2Y EMERGENCY RN MIU H-04 2KC497 2B KC SURGE TANK CN-2573-01.011 B ACT 3 4 BL MA c OIC N/A FS 2Y EMERGENCY RN MIU H-13 2KC498 2B KC SURGE TANK CN-2573-01.01 I c ACT 3 4 CK SA OIC OIC NIA eve II EMERGENCY RN MIU H-12 CHECK cvo II 2KC499 2B KC SURGE TANK CN-2573-01.01 I B ACT 3 4 .. PL MA c 0 NIA FS 2Y EMERGENCY RN H-12 MAKEUP 2KC814

         ~t DRAIN HEADER il*EF CN-2573-01.051 G-01 c   ACT   NC    0.75        SA    c    OIC     NIA   RV      I
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                                                                                                                                'IST 1.0.6 Page 139 of 222 Valve Summary Listing Page 139 of 222 VALVE ID         FUNCTION       DRAWING/COOR . CAT   ACT/ CLASS  SIZE    TYPE ACT      POSITION      TEST  FREQ  PROCEDURE          NOTES PASS                                             REQ NORM SAFE     FAIL 2KCC37A  UNIT 2 A TRAIN KC      CN-2573-01.00 I    B  ACT   3      6      GL  MO    c    O/C     FAI  RPI   2Y MINI FLOW ISOL               D-10 FSC    Q FSO    Q ST-C   Q ST-0   Q 2KCC40B  UNIT 2 B TRAIN KC      CN-2573-01.00  I   B  ACT   3      6      GL  MO    c    O/C     FAI   RPI  2Y MINI FLOW ISOL               C-12 FSC    Q FSO    Q ST-C  Q ST-0  Q 2KCC42   RADIATION MONITOR      CN-2573-01.00 I   c  ACT   3     0.75    CK   SA  OIC    c      NIA  BOO    II 2EMF-46A OUTLET             K-01 CHECK                                                                                       eve    II 2KCC43   RADIATION MONITOR      CN-2573-01.00 I   c  ACT   3     0.75    CK   SA  OIC    c      NIA  BOO    II 2EMF-46B OUTLET             K-14 CHECK                                                                                       eve     II 2KD006   2A DIG ENG DRIVEN     CN-2609-01.00 I J- c  ACT   3       8     CK   SA  OIC   OIC     NIA  eve     II JACKET WATER                 10 CIRCULATION PUMP DISCH CHECK                                                                                 cvo     II 2KD021   2B DIG ENG DRIVEN      CN-2609-01.00 I   c  ACT   3       8     CK   SA  OIC   OIC     NIA  eve     II JACKET WATER                E-10 CIRCULATION PUMP DISCH CHECK                                                                                 cvo     II 2KF097  2B KF ASSURED FUEL    CN-2570-01.00 11-  B  ACT    3      4      PL  MA   c    OIC     NIA    FS   2Y POOL MIU ISOL                11

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 140 of 222 Valve Summary Listing Page 140 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2KF101B FWST TO SPENT FUEL CN-2570-01.00 I B ACT 2 4 GA MO c c FAI RPI 2Y POOL H-12 FSC Q ST-C Q 2KF103A FWST TO SPENT FUEL CN-2570-01.00 I B ACT 2 4 GA MO c c FAI RPI 2Y POOL H-12 FSC Q ST-C Q 2KF104 2A KF ASSURED FUEL CN-2570-01.00 I B ACT 3 4 PL MA c OIC NIA FS 2Y POOL MIU ISOL H-12 2LD017 2A DIG ENG LUBE OIL CN-2609-02.00 I c ACT 3 6 CK SA OIC 0 NIA BOC II STRAINER 2A1 CHECK K-5 cvo II 2LD018 2A DIG ENG LUBE OIL CN-2609-02.00 I J- c ACT 3 6 CK SA OIC 0 NIA BOC II STRAINER 2A2 CHECK 6 cvo II 2LD047 2B DIG ENG LUBE OIL CN-2609-02.021 c ACT 3 6 CK SA OIC 0 NIA BOC II STRAINER 2B1 CHECK K-5 cvo II 2LD048 2B DIG ENG LUBE OIL CN-2609-02.02 I J- c ACT 3 6 CK SA OIC 0 NIA BOC II STRAINER 2B2 CHECK 6 cvo II 2MIMV6470 ILRT ISOL I A PASS 2 GA MA c c NIA LTJ J 2MIMV6471 ILRT ISO VALVE I A PASS 2 GA MA c c NIA LTJ J 2MIMV6480 ILRT ISOL I A PASS 2 GA MA c c NIA LTJ J 2MIMV6481 ILRT ISO VALVE I A PASS 2 GA MA c c NIA LTJ J 2MIMV6490 ILRT ISOL I A PASS 2 GA MA c c NIA LTJ J 2MIMV6491 ILRT ISO VALVE I A PASS 2 GA MA c c NIA LTJ J

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Catawba terval Standa1 odelSTC Catawba Nuclear Plant Interval 4 : IST 1.0.6 Page 141 of 222 Valve Summary Listing Page 141 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL . 2MISV0150 HYDROGEN MONITOR I A PASS NC sv so c c c LTJ J SAMPLE SELECTION TRAIN A 2MISV0160 HYDROGEN MONITOR I A PASS NC sv so c c c LTJ J SAMPLE SELECTION TRAIN B 2MISV0170 HYDROGEN MONITOR I A PASS NC sv so c c c LTJ J SAMPLE SELECTOR TRAIN A 2MISV0180 HYDROGEN MONITOR I A PASS NC sv so c C* c LTJ J SAMPLE SELECTOR TRAIN B 2MISV5230 CONT EMF SUP OTSD I A ACT 2 sv so 0 c c RPI 2Y CONT ISOL LTJ J FC Q FSC Q ST-C Q 2MISV5231 CONT EMF SUP INSD I A ACT 2 sv so 0 c c RPI 2Y CONT ISOL LTJ J FC Q FSC Q ST-C Q 2MISV5232 CONT EMF RET OTSD I A ACT 2 sv so 0 c c RPI 2Y CONT ISOL LTJ J FC Q FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 142 of 222 Valve Summary Listing Page 142 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2MISV5233 CONT EMF RET INSD I A ACT 2 sv so 0 c c RPI 2Y CONT ISOL LTJ J FC Q FSC Q ST-C Q 2NB260B RMWST CONT ISOL CN-2556-02.00 I A ACT 2 1 GL MO c c FAI RPI 2Y G-04 LTJ J FSC Q ST-C Q 2NB262 RMWST RX BLDG CN-2556-02.00 I AIC ACT 2 1 CK SA OIC OIC N/A eve II SUPPLY HEADER CHECK G-06 cvo II LTJ J 2NB331 RMWST RX BLDG CN-2556-02.00 I c ACT NC 1 RV SA c O/C N/A RV I SUPPLY HEADER RELIEF G-07 VALVE TO NCDT 2NC001 PZR SAFETY RELIEF CN-2553-01.01 I c ACT 1 6 RV SA c OIC N/A RV I K-03 2NC002 PZR SAFETY RELIEF CN-2553-01.01 I c ACT 1 6 RV SA c OIC N/A RV I K-04 2NC003 PZR SAFETY RELIEF CN-2553-01.01 I c ACT 1 6 RV SA c OIC N/A RV I K-06 2NC031B PRZ POWER OPERATED CN-2553-01.01 IF- B ACT 1 1 GA MO 0 OIC FAI RPI 2Y . RELIEF VALVE ISOL 04 FSC Q FSO Q

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Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 143 of 222 Valve Summary Listing Page 143 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NC0328 PRESSURIZER POWER CN-2553-01.01 I B ACT 1 4 PORV AO c OIC c STT 2Y OPERATED RELIEF G-04 CONTROL FC cs CSJ-CN-NC-02 FSC cs CSJ-CN-NC-02 FSO cs CSJ-CN-NC-02 ST-C cs CSJ-CN-NC-02 ST-0 cs CSJ-CN-NC-02 2NC033A PZR POWER OPERATED CN-2553-01.01 IF- B ACT 1 1 GA MO 0 OIC FAI RPI 2Y RELIEF VALVE ISOL 03 FSC Q FSO Q - ST-C Q ST-0 Q 2NC034A PZR POWER OPERATED CN-2553-01. 01 I B ACT 1 4 PORV AO c OIC c STT 2Y RELIEF VALVE G-03 FC cs CSJ-CN-NC-02 FSC cs CSJ-CN-NC-02 FSO cs CSJ-CN-NC-02 ST-C cs CSJ-CN-NC-02 ST-0 cs CSJ-CN-NC-02

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 144 of 222 Valve Summary Listing Page 144 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NC035B PZR POWER OPERATED CN-2553-01.01 IF- B ACT 1 1 GA MO 0 OIC FAI RPI 2Y RELIEF VALVE ISOL 02 FSC Q FSO Q ST-C Q ST-0 Q 2NC036B PZR POWER OPERATED CN-2553-01.01 I B ACT 1 4 PORV AO c OIC c STT 2Y RELIEF VALVE G-02 FC cs CSJ-CN-NC-02 FSC cs CSJ-CN-NC-02 FSO cs CSJ-CN-NC-02 ST-C cs CSJ-CN-NC-02 ST-0 cs CSJ-CN-NC-02 2NC053B N2 TO PRT CONT ISOL CN-2553-01.01 I A ACT 2 1 GL MO c c FAI RPI 2Y K-11 LTJ J FSC Q ST-C Q 2NC054A NITROGEN TO PZR CN-2553-01.01 I A ACT 2 1 GL MO c c FAI RPI 2Y RELIEF TANK K-09 CONTAINMENT ISOL LTJ J FSC Q ST-C Q 1-..

Catawba 4.terval Standa de ISTC Catawba Nuclear Plant Interval 4 . IST 1.0.6 Page 145 of 222 Valve Summary Listing Page 145 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NC056B RMW PUMP DISCH CONT CN-2553-01.01 / I- A ACT 2 3 GA MO c c FAI RPI 2Y ISOL 13 LT 2Y FSC Q ST-C Q 2NC057 PZR RELIEF TANK SPRAY CN-2553-01.01 / I- NC ACT 2 3 CK SA OIC OIC NIA eve II SUPPLY CHECK 12 cvo II LTJ J 2NC141 NC MOTOR OIL DRAIN CN-2553-01.03 I J- A PASS 2 2 GA MA c c N/A LTJ J PUMP INSIDE 08 CONTAINMENT ISOL 2NC142 NC PUMP MOTOR OIL CN-2553-01.03 / A PASS 2 2 GA MA c c NIA LTJ J DRAIN PUMP OUTSIDE K-08 CONTAINMENT ISOL 2NC1958 NC PUMP MTR OIL FILL CN-2553-01.03 / A ACT 2 2 GA MO c c FAI RPI 2Y ISOL E-07 LTJ J FSC Q ST-C Q 2NC196A 2NC PUMP MOTOR OIL CN-2553-01.03 / A ACT 2 2 GA MO c c FAI RPI 2Y FILL ISOL D-07 LTJ J FSC Q ST-C Q 2NC250A REACTOR HEAD VENT CN-2553-01.01 IL- B ACT 1 1 GL MO c OIC FAI RPI 2Y BLOCK. 07 FSC cs CSJ-CN-NC-03 FSO cs CSJ-CN-NC-03

                                  -                                                                     ST-C  cs                  CSJ-CN-NC-03 ST-0  cs                  CSJ-CN-NC-03

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 146 of 222 Valve Summary Listing Page 146 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NC251B REACTOR HEAD VENT CN-2553-01.01 IL- B ACT 1 1 GL MO c OIC FAI RPI 2Y 07 FSC cs CSJ-CN-NC-03 FSO cs CSJ-CN-NC-03 ST-C cs CSJ-CN-NC-03 ST-0 cs CSJ-CN-NC-03 2NC252B REACTOR VESSEL HEAD CN-2553-01.01 I B ACT 1 1 GL MO c OIC FAI RPI 2Y VENT BLOCK K-07 FSC cs CSJ-CN-NC-03 FSO cs CSJ-CN-NC-03 ST-C cs CSJ-CN-NC-03 ST-0 cs CSJ-CN-NC-03 2NC253A REACTOR VESSEL HEAD CN-2553-01.01 I B ACT 1 1 GL MO c OIC FAI RPI 2Y VENT K-07 FSC cs CSJ-CN-NC-03 FSO cs CSJ-CN-NC-03 ST-C cs CSJ-CN-NC-03 ST-0 cs CSJ-CN-NC-03 2ND001B ND PUMP 2A SUCT FRM CN-2561-01.00 I L- A ACT 1 12 GA MO c 0 FAI RPI 2Y LOOP B 13 LT 2Y FSO cs CSJ-CN-ND-01 ST-0 cs CSJ-CN-ND-01

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Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 147 of 222 Val~e Summary Listing Page 147 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS* REQ NORM SAFE FAIL 2ND002A ND PUMP 2A SUCT FRM CN-2561-01.00 I J- A ACT 1 12 GA MO c 0 FAI RPI 2Y LOOP B 13 LT 2Y FSO cs CSJ-CN-ND-01 ST-0 cs CSJ-CN-ND-01 2ND003 2A ND PUMP SUCT FROM CN-2561-01.00 11- c ACT 2 4 RV SA c OIC NIA RV I NC LOOP B HOR RELIEF 13 2ND010 2A ND PUMP DISCH CN-2561-01.00 I c ACT 2 8 CK SA OIC OIC NIA eve II CHECK G-10 cvo II 2ND024A 2A ND HX OUTLET TO CN-2561-01.00 I B PASS 2 2 GL MO c c FAI RPI 2Y LETDOWN HX G-05 2ND025A 2A ND PUMP MINIFLOW CN-2561-01.00 I B ACT 2 2 GL MO c OIC FAI RPI 2Y E-13 FSC Q FSO Q ST-C Q ST-0 Q 2ND026 2A ND HX OUTLET CN-2561-01.00 I B ACT 2 8 FC AO 0 0 0 RPI 2Y CONTROL G-04 FO Q FSO Q ST-0 Q 2ND027 2A ND HX BYPASS CN-2561-01.00 I J- B ACT 2 8 FC AO c c c RPI 2Y CONTROL 06 FC Q FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 148 of 222 Valve Summary Listing Page 148 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2ND028A ND SUPPLY TO NV & 2A CN-2561-01.00 /I- B ACT 2 8 GA MO c OIC FAI RPI 2Y NI PMPS 04 FSC cs CSJ-CN-ND-05 FSO cs CSJ-CN-ND-05 ST-C cs CSJ-CN-ND-05 ST-0 cs CSJ-CN-ND-05 2ND031 2A ND TRAIN COLD LEG CN-2561-01.00 I c ACT 2 4 RV SA c OIC N/A RV I INJECTION RETURN G-02 SAFETY RELIEF 2ND032A ND TRAIN 2A HOT LEG CN-2561-01.00 I B ACT 2 8 GA MO 0 OIC FAI RPI 2Y INJ ISOL E-03 FSC cs CSJ-CN-ND-04 FSO cs CSJ-CN-ND-04 ST-C cs CSJ-CN-ND-04 ST-0 cs CSJ-CN-ND-04 2ND035 ND HOT LEG INJECTION CN-2561-01.00 I c ACT 2 1 RV SA c OIC NIA RV I RETURN SAFETY RELIEF D-02 2ND036B ND PUMP 28 SUCT FRM CN-2561-01.01 IL- A ACT 1 12 GA MO c 0 FAI RPI 2Y LOOP C 13 LT 2Y FSO cs CSJ-CN-ND-02 ST-0 cs CSJ-CN-ND-02

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Catawba terval . de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 149 of 222 Valve Summary Listing Page 149 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES

                      .                                PASS                                             REQ NORM SAFE     FAIL 2ND037A  ND PUMP 28 SUCT FRM    CN-2561-01.01 I J-  A  ACT    1      12  GA   MO      c     0      FAI  RPI    2Y LOOP C                        13 LT   2Y FSO   cs                  CSJ-CN-ND-02 ST-0   cs                  CSJ-CN-ND-02 2ND038  2BNDPUMPSUCTFROM       CN-2561-01.01 /I-   c   ACT   2      4   RV    SA     c    O/C    N/A    RV    I NC LOOP C HEADER              13 RELIEF 2ND044  28 ND PUMP DISCH        CN-2561-01.01 I    c   ACT   2       8  CK    SA    OIC   O/C    N/A   eve     II CHECK                        G-10 cvo     II 2ND058B  28 ND HX OUTLET TO      CN-2561-01.01 /    B  PASS   2      2   GL   MO      c     c      FAI  RPI    2Y LETDOWN HX                   G-05 2ND059B  28 ND PUMP MINIFLOW     CN-2561-01.01 I    B   ACT   2      2   GL   MO      0    OIC     FAI   RPI   2Y E-13 FSC     Q FSO     Q
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Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 150 of 222 Valve Summary Listing Page 150 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2ND064 28 ND TRAIN COLD LEG CN-2561-01.01 I c ACT 2 4 RV SA c O/C N/A RV I INJECTION RETURN G-02 SAFETY RELIEF 2ND0658 ND TRAIN 28 HOT LEG CN-2561-01.01 IF- 8 ACT 2 8 GA MO 0 O/C FAI RPI 2Y INJ ISOL 03 FSC cs CSJ-CN-ND-04 FSO cs CSJ-CN-ND-04 ST-C cs CSJ-CN-ND-04 ST-0 cs CSJ-CN-ND-04 2ND090 2A ND TRAIN AUX PZR CN-2561-01.00 I 8 PASS 2 2 GL MO c c FAI RPI 2Y SPRAYISOL E-09 2ND091 28 ND TRAIN AUX PZR CN-2561-01.00 I 8 PASS 2 2 GL MO c c FAI RPI 2Y SPRAYISOL E-09 2ND116 OVER PRESS CHECK CN-2561-01.00 I c ACT 2 0.75 CK SA OIC OIC N/A eve II VALVE AROUND 2ND18 K-12 cvo II 2ND117 OVER PRESS CHECK CN-2561-01.01 / c ACT 2 0.75 CK SA O/C O/C N/A eve II VALVE AROUND 2ND368 K-12 cvo II 2NF22BA 2NF GLYCOL SUPPLY CN-2558-02.00 I A ACT 2 4 GA AO 0 c c RPI 2Y OUTSIDE CONTAINMENT H-14 ISOL LTJ J

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Catawba 49terval Standa delSTC Catawba Nuclear Plant Interval 4 **IST 1.0.6 Page 151 of 222 Valve Summary Listing Page 151 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NF229 NF AHU GLYCOL SUPPLY CN-2558-02.00 I F- NC ACT 2 4 CK SA OIC OIC NIA eve II HEADER CHECK 14 cvo II LTJ J 2NF233B GLYCOL RETURN CN-2558-02.00 IL- A ACT 2 4 GA MO 0 c FAI RPI 2Y CONTAINMENT ISOL 10 LTJ J FSC Q ST-C Q 2NF234A 2NF GLYCOL RETURN CN-2558-02.00 I L- A ACT 2 4 GA AO 0 c c RPI 2Y

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Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 152 of 222 Valve Summary Listing Page 152 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NI0108 NV PMP C/L INJ ISOL CN-2562-01.00 I B ACT 2 4 GA MO c OIC FAI RPI 2Y C-06 FSC cs CSJ-CN-NI-01 FSO cs CSJ-CN-NI-01 ST-C cs . CSJ-CN-NI-01 ST-0 cs CSJ-CN-NI-01 2NI012 NV PUMPS TO COLD LEG CN-2562-01 :OO I c ACT 2 3 CK SA OIC O/C N/A eve II CHECK E-08 cvo II 2NI015 NV PUMPS TO LOOP A CN-2562-01.00 /I- c ACT 1 1.5 CK SA OIC O/C N/A eve II COLD LEG CHECK 11 cvo II 2Nl017 NV PUMPS TO B C-LEG CN-2562-01.00 /I- c ACT 1 1.5 CK SA O/C O/C N/A eve II CHK 09 cvo II 2NI019 NV PUMPS TO LOOP C CN-2562-01.00 / I- c ACT 1 1.5 CK SA OIC O/C N/A eve II COLD LEG CHECK 07 cvo II 2NI021 NV PUMPS TO D C-LEG CN-2562-01.00 /I- c ACT 1 1.5 CK SA OIC O/C N/A eve II CHK 05 cvo II 2NI047A C-LEG ACCUM N2 SUP CN-2562-01.01 I L- A ACT 2 0.75 GL MO c c FAI RPI 2Y CONT ISOL 09 LTJ J FSC Q ST-C Q

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Catawba terval Standa.ode ISTC Catawba Nuclear Plant Interval 4 - IST 1.0.6 Page 153 of 222 Valve Summary Listing Page .153 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NI048 ACCUMULATOR CN-2562-01.01 IL- NC ACT 2 1 CK SA OIC c N/A BOO II NITROGEN SUPPLY 08 CONTAINMENT CHECK eve II LTJ J 2NI052 2A COLD LEG ACCUM CN-2562-01.01 /I- c ACT 2 1 RV SA c O/C NIA RV I RELIEF 03 2NI054A C-LEG ACCUM A DISCH CN-2562-01.01 I B ACT 1 10 GA MO 0 OIC FAI RPI 2Y ISOL G-02 FSC RO ROJ-CN-NI-25 FSO RO ROJ-CN-NI-25 ST-C RO ROJ-CN-NI-25 ST-0 RO ROJ-CN-NI-25 2Nl059 2A COLD LEG ACCUM CN-2562-01.01 I NC ACT 1 10 CK SA OIC O/C N/A LT 2Y DISCH CHECK D-02 eve II cvo II 2NI060 2A COLD LEG ACCUM CN-2562-01.01 I NC ACT 1 10 CK SA OIC OIC N/A LT 2Y DISCH CHECK C-02 eve II cvo II 2NI063 28 CLA RELIEF CN-2562-01.01 /I- c ACT 2 1 RV SA c OIC N/A RV I 05 2NI065B 28 CLA DISCH ISOL CN-2562-01.01 I B ACT 1 10 GA MO 0 OIC FAI RPI 2Y G-05 FSC RO ROJ-CN-NI-25 FSO RO ROJ-CN-NI-25 ST-C RO ROJ-CN-NI-25 ST-0 RO ROJ-CN-NI-25

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 154 of 222 Valve Summary Listing Page 154 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NI070 28 CLA DISCH CHECK CN-2562-01.01 I A/C ACT 1 10 CK SA OIC OIC NIA LT 2Y D-05 eve II cvo II 2Nl071 28 CLA DISCH CHECK CN-2562-01.01 I A/C ACT 1 10 CK SA OIC OIC NIA LT 2Y C-05 eve II cvo II 2NI074 2C CLA RELIEF CN-2562-01.01 11- c ACT 2 1 RV SA c OIC NIA RV I 08 2Nl076A C-LEG ACCUM C DISCH CN-2562-01.01 I 8 ACT 1 10 GA MO 0 OIC FAI RPI 2Y ISOL G-07 FSC RO ROJ-CN-NI-25 FSO RO ROJ-CN-NI-25 ST-C RO ROJ-CN-NI-25 ST-0 RO ROJ-CN-NI-25 2NI081 ACCUM 2C DISCH CHK CN-2562-01.01 I AIC ACT 1 10 CK SA OIC OIC NIA LT 2Y D-07 eve II cvo II 2NI082 ACCUM 2C DISCH CHK CN-2562-01.01 I AIC ACT 1 10 CK SA OIC OIC NIA LT 2Y C-07 eve II cvo II 2NI086 2D CLA RELIEF CN-2562-01.01 11- c ACT 2 1 RV SA c OIC NIA RV I 11

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Catawba 4Wterval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 155 of 222 Valve Summary Listing Page 155 of 222 VALVE ID FUNCTION. DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NI088B C-LEG ACCUM D DISCH CN-2562--01.01 I B ACT 1 10 GA MO 0 OIC FAI RPI 2Y ISOL G-10 FSC RO ROJ-CN-NI-25 FSO RO ROJ-CN-NI-25 ST-C RO ROJ-CN-NI-25 ST-0 RO ROJ-CN-NI-25 2NI093 ACCUM 2D DISCH CHK CN-2562--01.01 I NC ACT 1 10 CK SA OIC O/C NIA LT 2Y D-10 eve II cvo II 2Nl094 ACCUM 2D DISCH CHK CN-2562--01.01 I NC ACT 1 10 CK SA O/C O/C NIA LT 2Y C-10 eve II cvo II 2NI095A COLD LEG ACCUM CN-2562-01.01 I F- A ACT 2 0.75 GA MO c c FAI RPI 2Y CHECK VALVE TEST ISOL 13 LTJ J FSC Q ST-C Q 2NI096B C-LEG ACCUM CHK VLV CN-2562--01.01 I A ACT 2 0.75 GL MO c c FAI RPI 2Y TSTISOL H-13 LTJ J FSC Q ST-C Q 2Nl100B NI PMPS SUCT FROM CN-2562--01.02 / B ACT 2 8 GA MO 0 O/C FAI RPI 2Y FWST G-13 FSC cs CSJ-CN-NI-08

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Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 156 of 222 Valve Summary Listing Page 156 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl101 FWST TO SUCTION CN-2562-01.02 / c ACT 2 8 CK SA OIC OIC NIA eve II HEADER OF NI PUMPS G-13 CHECK cvo II 2Nl102 NI PUMPS SUCTION CN-2562-01.02 IF- c ACT 2 1.5 RV SA c OIC NIA RV I HEADER RELIEF 13 2Nl103A 2A NI PUMP SUCTION CN-2562-01.02 /I- B ACT 2 6 GA MO 0 OIC FAI RPI 2Y 13 FSC cs CSJ-CN-NI-24 FSO cs CSJ-CN-NI-24 ST-C cs CSJ-CN-NI-24 ST-0 cs CSJ-CN-NI-24 2Nl114 2A NI PUMP RECIRC LINE CN-2562-01.02 / I- c ACT 2 3 CK SA OIC OIC NIA eve II CHECK 08 cvo II 2N1115A NI PUMP 2A MINIFLOW CN-2562-01.02 / B ACT 2 2 GL MO 0 OIC FAI RPI 2Y ISOL H-08 FSC Q FSO Q ST-C Q ST-0 Q 2Nl116 2A NI PUMP DISCH CN-2562-01.02 I J- c ACT 2 4 CK SA OIC OIC NIA eve II CHECK 08 cvo II 2Nl118A NI PUMP 2A C-LEG INJ CN-2562-01.02 I B ACT 2 4 GA MO 0 OIC FAI RPI 2Y ISOL H-06 FSC Q FSO Q ST-C Q

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Catawba 4.terval de ISTC f Catawba Nuclear Plant Interval 4 . IST 1.0.6 Page 157 of 222 Valve Summary Listing Page 157 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl119- 2A NI PUMP DISCH CN-2562-01.02 / c ACT 2 1.5 RV SA c OIC N/A RV I HEADER RELIEF K-06 2Nl1208 NI PMPS TO C-LEG CN-2562-01.02 /I- A ACT 2 0.75 GL MO c c FAI RPI 2Y ACCUM FILL 05 LTJ J FSC

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Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 158 of 222 Valve Summary Listing Page 158 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl126 INLET TO HOT LEG C CN-2562-01.02 /I- A/C ACT 1 6 CK SA OIC OIC N/A LT 2Y CHECK 01 eve II cvo II 2Nl128 NI PUMPS TO HOT LEG 8 CN-2562-01.02 I NC ACT 1 2 CK SA O/C O/C N/A LT 2Y CHECK K-04 eve II cvo II 2Nl129 ND TO HOT LEG 8 CHECK CN-2562-01.02 I J- A/C ACT 1 8 CK SA OIC OIC N/A LT 2Y 03 eve II cvo II 2Nl134 28 HOT LEG INJECTION CN-2562-01.02 / NC ACT 1 6 CK SA O/C O/C N/A LT 2Y CHECK K-01 eve II cvo II 2Nl1358 28 NI PUMP SUCTION CN-2562-01.02 / 8 ACT 2 6 GA MO 0 OIC FAI RPI 2Y E-13 FSC Q

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Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 159 of 222 Valve Summary Listing Page 159 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl143 28 NI PUMP RECIRC LINE CN-2562-01.02 I c ACT 2 3 CK SA OIC O/C N/A eve II CHECK E-08 cvo II 2Nl144A NI PUMP 28 MINIFLOW CN-2562-01.02 IF- 8 ACT 2 2 GL MO 0 OIC FAI RPI 2Y ISOL 08 FSC cs CSJ-CN-NI-22 FSO cs CSJ-CN-NI-22 ST-C cs CSJ-CN-NI-22 ST-0 cs CSJ-CN-NI-22 2Nl1478 NI MINI FLOW HDR TO CN-2562-01.02 I 8 ACT 2 2 GL MO 0 O/C FAI RPI 2Y FWST ISOL G-10 FSC cs CSJ-CN-NI-09 FSO cs CSJ-CN-NI-09 ST-C cs CSJ-CN-NI-09 2Nl148 28 NI PUMP DISCH CN-2562-01.02 / c ACT 2 4 CK SA OIC OIC N/A eve II CHECK D-08 cvo II 2Nl1508 NI PUMP 28 C-LEG INJ CN-2562-01.02 I F- 8 ACT 2 4 GA MO 0 OIC FAI RPI 2Y ISOL 06 FSC Q FSO Q ST-C Q ST-0 Q 2Nl151 28 NI PUMP DISCH CN-2562-01.02 / c ACT 2 1.5 RV SA c OIC N/A RV I HEADER RELIEF E-06

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 160 of 222 Valve Summary Listing Page 160 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl1528 NI PUMP 28 TO H-LEGS CN-2562-01.02 I B ACT 2 4 GA MO c OIC FAI RPI 2Y A&D D-05 FSC cs CSJ-CN-NI-21 FSO cs CSJ-CN-NI-21 ST-C cs CSJ-CN-NI-21 ST-0 cs CSJ-CN-NI-21 2Nl153A HOT LEG INJECTION CN-2562-01.02 / B ACT 2 0.75 GL MO c c FAI RPI 2Y CHECK VALVE TEST ISOL D-04 FSC Q ST-C Q 2Nl1548 ND TO HOT LEGS CHECK CN-2562-01.02 I B ACT 2 12 GL MO c c FAI RPI 2Y VALVE TEST ISOL H-03 FSC Q ST-C Q 2Nl156 28 NI PUMP HOT LEG CN-2562-01.02 / AIC ACT 1 1.5 CK SA OIC OIC N/A LT 2Y INJECTION TO HOT LEG E-03 A CHECK eve II cvo II 2N1157 HOT LEG INJECTION A CN-2562-01.02 I AIC ACT 1 6 CK SA OIC OIC N/A LT 2Y CHECK E-01 eve II cvo II 2Nl159 28 NI PUMP HOT LEG INJ CN-2562-01.02 / A/C ACT 1 2 CK SA OIC OIC N/A LT 2Y TO HOT LEG D CHECK C-03 eve II cvo II

Catawba terval StandaWode ISTC Catawba Nuclear Plant Interval 4 . IST 1.0.6 Page 161 of 222 Valve Summary Listing Page '161 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl160 HOT LEG INJECTION D CN-2562-01.02 / AIC ACT 1 6 CK SA OIC OIC N/A LT 2Y CHECK C-01 eve II cvo II 2Nl161 NI PUMPS DISCH TO CN-2562-01.03 / c ACT 2 1.5 RV SA c OIC N/A RV I COLD LEG HEADER K-07 RELIEF 2Nl162A NI TO C-LEGS INJ HOR CN-2562-01.03 / A ACT 2 4 GA MO 0 OIC FAI RPI 2Y ISOL K-07 LT 2Y FSC cs CSJ-CN-NI-12 FSO cs CSJ-CN-NI-12 ST-C cs CSJ-CN-NI-12 2Nl165 NI PUMPS DISCH CN-2562-01.03 / AIC ACT 1 2 CK SA O/C OIC N/A LT 2Y HEADER TO COLD LEG A G-03 CHECK eve II cvo II 2Nl167 NI PUMPS DISCH CN-2562-01.03 / AIC ACT 1 2 CK SA OIC OIC N/A LT 2Y HEADER TO COLD LEG B G-06 CHECK eve II cvq II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 162 of 222 Valve Summary Listing Page 162 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl169 NI PUMPS DISCH CN-2562-01.03 / A/C ACT 1 2 CK SA OIC OIC N/A LT 2Y HEADER TO COLD LEG D G-09 CHECK eve II cvo II 2Nl171 NI PUMPS DISCH CN-2562-01.03 / AIC ACT 1 2 CK SA OIC OIC N/A LT 2Y HEADER TO COLD LEG C G-12 CHECK eve II cvo II 2Nl173A ND HOR 2A TO COLD CN-2562-01.03 / A ACT 2 8 GA MO 0 OIC FAI RPI 2Y LEGS C&D E-10 LT 2Y FSC cs CSJ-CN-NI-15 FSO cs CSJ-CN-NI-

      .                                                                                                                         15 ST-C  cs                 CSJ-CN-NI-15 ST-0  cs                 CSJ-CN-NI-15 2Nl175  2A ND HEADER TO C . CN-2562-01.03 / F- AIC  ACT   1      6    CK   SA    OIC   OIC     N/A   LT  2Y COLD LEG CHECK               11 eve   II cvo   II 2Nl176  2A ND HEADER TOD      CN-2562-01.03 IF-  AIC  ACT   1      6    CK   SA    OIC   O/C     NIA   LT  2Y COLD LEG CHECK               09 eve   II cvo   II

Catawba 49-terval Standa de ISTC Catawba Nuclear Plant Interval 4 'IST 1.0.6 Page 163 of 222 Valve Summary Listing Page 163 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl1788 ND HOR 28 TO COLD CN-2562-01.03 / A ACT 2 8 GA MO 0 OIC FAI RPI 2Y LEGS A&8 E-04 LT 2Y FSC cs CSJ-CN-NI-15 FSO cs CSJ-CN-NI-15 ST-C cs CSJ-CN-NI-15 ST-0 cs CSJ-CN-NI-15 2Nl180 28 ND HEADER TO 8 CN-2562-01.03 / F- AIC ACT 1 6 CK SA OIC OIC NIA LT 2Y COLD LEG CHECK 05 eve II cvo II 2Nl181 28 ND HEADER TO A CN-2562-01.03 IF- AIC ACT 1 6 CK SA OIC OIC N/A LT 2Y COLD LEG CHECK 04 eve II cvo II 2Nl1838 ND HOR A&8 HOT LEG CN-2562-01.02 / A ACT 2 12 GA MO c OIC FAI RPI 2Y INJ ISOL G-04 LT 2Y FSC cs CSJ-CN-NI-16 FSO cs CSJ-CN-NI-16 ST-C cs CSJ-CN-NI-16 ST-0 cs CSJ-CN-NI-16

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 164 of 222 Valve Summary Listing Page 164 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl184B ND PUMP 28 CONT SUMP CN-2562-01.03 / B ACT 2 18 GA MO c OIC FAI RPI 2Y SUCT C-10 FSC cs CSJ-CN-NI-17 FSO cs CSJ-CN-NI-17 ST-C cs CSJ-CN-NI-17 ST-0 cs CSJ-CN-NI-17 2Nl185A NDPUMP2ACONTSUMP CN-2562-01 :o3 / B ACT 2 18 GA MO c OIC FAI RPI 2Y SUCT C-05 FSC cs CSJ-CN-NI-17 FSO cs CSJ-CN-NI-17 _ST-C cs CSJ-CN-NI-17 ST-0 cs CSJ-CN-NI-17 2Nl332A NI PUMP SUCT X-OVER CN-2562-01.02 / L- B ACT 2 6 GA MO c OIC FAI RPI 2Y FROM ND 12 FSC cs CSJ-CN-NI-18 FSO cs CSJ-CN-NI-18 ST-C cs CSJ-CN-NI-18 ST-0 cs CSJ-CN-NI-18

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Catawba 41 terval de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 165 of 222 Valve Summary Listing Page 165 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl333B NI PUMP SUCT FROM ND CN-2562-01.02 I B ACT 2 6 GA MO c O/C FAI RPI 2Y K-12 FSC cs CSJ-CN-NI-18 FSO cs CSJ-CN-NI-18 ST-C cs CSJ-CN-NI-18 ST-0 cs CSJ-CN-NI-18 2Nl334B NI PUMP suer X-OVER CN-2562-01.02 / B ACT 2 6 GA MO 0 OIC FAI RPI 2Y FROM ND K-11 FSC cs CSJ-CN-NI-23 FSO cs CSJ-CN-NI-23 ST-C cs CSJ-CN-NI-23 ST-0 cs CSJ-CN-NI-23 2N1342 ND TO SUCTION OF 28 NI CN-2562-01.02 I c ACT 2 8 CK SA OIC OIC N/A eve II PUMP CHECK D-13 CVO II 2Nl351 NV PUMPS TO NC LOOP CN-2562-01.00 /I- c ACT 1 1.5 CK SA OIC OIC N/A eve II A CHECK 11 cvo II 2N1352 CCP TO NC LOOP B CN-2562-01.00 /I- c ACT 1 1.5 CK SA O/C O/C N/A eve II CHECK 09 cvo II 2Nl353 CCP TO NC LOOP C CN-2562-01.00 /I- c ACT 1 1.5 CK SA O/C O/C N/A eve II CHECK 07 cvo II 2N1354 NV PUMPS TO NC LOOP CN-2562-01.00 / I- c ACT 1 1.5 CK SA O/C O/C N/A eve II D CHECK 05 CVO II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 166 of 222 Valve Summary Listing Page 166 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl391 2A COLD LEG INJECTION CN-2562-01.01 I A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL C-03 2Nl392 28 COLD LEG INJECTION CN-2562-01.01 I A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL C-03 2Nl393 2C COLD LEG INJECTION CN-2562-01.01 I A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL C-08 2Nl394 2D COLD LEG INJECTION CN-2562-01.01 I A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL C-11 2Nl395 2A HOT LEG INJECTION CN-2562-01.02 I A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL E-02 2Nl396 28 HOT LEG INJECTION CN-2562-01.02 I A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL K-02 2Nl397 2C HOT LEG INJECTION CN-2562-01.02 / I- A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL 02 2Nl398 2D HOT LEG INJECTION CN-2562-01.02 / A PASS 2 0.75 GL AO c c c LT 2Y CHECK VALVE TEST ISOL C-02 2Nl438A N2 TO 2NC-34A FROM CN-2562-01.01 I 8 ACT 2 1 GL MO c OIC FAI RPI 2Y ACCUM 2A K-01 FSC Q FSO Q ST-C Q ST-0 Q 2Nl4398 N2 TO 2NC-328 FROM CN-2562-01.01 I 8 ACT 2 1 GL MO c OIC FAI RPI 2Y ACCUM 28 K-05 FSC Q FSO Q ST-C Q

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Catawba 4'9terval -! Standa de ISTC Catawba Nuclear Plant Interval 4 'IST 1.0.6 Page 167 of 222 Val~e Summary Listing Page 167 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2N1471 BYPASS CHECK VALVE CN-2562-01.01 IF- AIC ACT 2 0.75 CK SA OIC OIC N/A eve II FOR2Nl95A. 13 cvo II LTJ J 2Nl481 NI TEST HEADER RELIEF CN-2562-01.01 I c ACT NC 0.75 RV SA c OIC NIA RV I E-12 2N1485 NI LEAKOFF HEADER CN-2562-01.03 / A/C ACT 2 1 CK SA O/C O/C N/A eve II CHECK H-07 cvo II LTJ J 2N1495 28 ND HEADER PRESS CN-2562-01.03 / AIC ACT 2 0.5 CK SA OIC O/C N/A eve II RELIEF LINE CHECK E-06 cvo II LTJ J 2Nl501 2A ND HEADER PRESS CN-2562-01.03 / A/C ACT 2 0.5 CK SA OIC OIC N/A eve II RELIEF LINE CHECK G-10 cvo II LTJ J 2Nl515 2A ECCS SUMP PIPING CN-2562-01.03 / A PASS 2 1 GL MA c c N/A LTJ J DRAIN 1ST ISOL B-05 2Nl516 2A ECCS SUMP PIPING CN-2562-01.03 / A PASS 2 GL MA c c N/A LTJ J DRAIN 2ND ISOL B-05 2Nl517 2A ECCS SUMP PIPING CN-2562-01.03 / A PASS 2 1 GL MA c c N/A LTJ J VENT 1ST ISOL B-06 2Nl518 . 2A ECCS SUMP PIPING CN-2562-01.03 / A PASS 2 - GL MA c c N/A LTJ J VENT 2ND ISOL B-06 2Nl519 2Nl185A RESERVOIR CN-2562-01.03 / A PASS 2 GL MA c c NIA LTJ J DRAIN 1ST ISOL B-06 2Nl520 2Nl185A RESERVOIR CN-2562-01.03 / A PASS 2 GL MA c c N/A LTJ J DRAIN 2ND ISOL B-06 2Nl521 2Nl185A RESERVOIR CN-2562-01.03 / A PASS 2 GL MA c c N/A LTJ J VENT 1ST ISOL B-06 2Nl522 2Nl185A RESERVOIR CN-2562-01.03 / A PASS 2 GL MA c c N/A LTJ J VENT 2ND ISOL B-06

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 168 of 222 Valve Summary Listing Page 168 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Nl523 28 ECCS SUMP PIPING CN-2562-01.03 / A PASS 2 1 GL MA c c N/A LTJ J DRAIN 1ST ISOL C-10 2Nl524 28 ECCS SUMP PIPING CN-2562-01.03 / A PASS 2 GL MA c c N/A LTJ J DRAIN 2ND ISOL 8-10 2Nl525 28 ECCS SUMP PIPING CN-2562-01.03 / A PASS 2 1 GL MA c c N/A LTJ J VENT 1ST ISOL C-09 2Nl526 28 ECCS SUMP PIPING CN-2562-01.03 / A PASS 2 GL MA c c N/A LTJ J VENT 2ND ISOL 8-09 2Nl527 2Nl1848 RESERVOIR CN-2562-01.03 / A PASS 2 GL MA c c N/A LTJ J DRAIN 1ST ISOL 8-12 2Nl528 2Nl1848 RESERVOIR CN-2562-01.03 / A PASS 2 GL MA c c N/A LTJ J DRAIN 2ND ISOL 8-12 2Nl529 2Nl1848 RESERVOIR CN-2562-01.031 A PASS 2 GL MA c c NIA LTJ J VENT 1ST ISOL 8-10 2Nl530 2Nl1848 RESERVOIR CN-2562-01.031 A PASS 2 GL MA c c NIA LTJ J VENT 2ND ISOL 8-10 2N1532 2D CLA CHECK VALVE CN-2562-01.031 NC ACT 2 0.5 CK SA OIC OIC NIA eve II VENT LINE CHECK G-09 cvo II LTJ J 2N1537 2A CLA CHECK VALVE CN-2562-01.031 NC ACT 2 0.5 CK SA O/C OIC NIA eve II VENT LINE CHECK G-03 cvo II LTJ . J 2NM003A PZR LIQUID SAMPLE LINE CN-2572-01.00 I A ACT 2 0.5 GL MO c c FAI RPI 2Y CONTAINMENT ISOL K-03 LTJ J FSC Q ST-C Q 2NM006A PZR STEAM SAMPLE CN-2572-01.00 I J- A ACT 2 0.5 GL MO c c FAI RPI 2Y LINE CONT ISOL 03 LTJ J FSC Q

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Catawba terval Standa.ode ISTC Catawba Nuclear Plant Interval 4 ' IST 1.0.6 Page 169 of 222 Valve Summary Listing Page .169 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NM007B PZR SMPL HDR CONT CN-2572-01.00 I A ACT 2 0.5 GL MO c c FAI RPI 2Y ISOL K-06 LTJ J FSC Q ST-C Q 2NM022A HOT LEG A SMPL CONT CN-2572-01.00 I A ACT 2 0.5 GL MO 0 c FAI RPI 2Y ISOL K-11 LTJ J FSC Q ST-C Q 2NM025A 2C HOT LEG SAMPLE CN-2572-01.00 I A ACT 2 0.5 GL MO c c FAI RPI 2Y CONTAINMENT ISOL K-12 LTJ J FSC Q ST-C Q 2NM026B HOT LEG SMPL HDR CN-2572-01.00 I A ACT 2 0.5 GL MO 0 c FAI RPI 2Y CONT ISOL K-08 LTJ J FSC Q ST-C Q 2NM069 NI ACCUMULATOR CN-2572-01.01 I NC ACT 2 0.5 RV SA c OIC N/A RV I SAMPLE LINE RELIEF G-10 LTJ J

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 170 of 222 Valve Summary Listing Page 170 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NM072B 2A ACCUMULATOR CN-2572-01.01 /I- A ACT 2 0.5 GL MO c c FAI RPI 2Y SAMPLE LINE 06 CONTAINMENT ISOL. LTJ J FSC Q ST-C Q 2NM075B 28 ACCUMULATOR CN-2572-01.01 /I- A ACT 2 0.5 GL MO c c FAI RPI 2Y SAMPLE LINE 08 CONTAINMENT ISOL LTJ J FSC Q ST-C Q 2NM078B 2C ACCUMULATOR CN-2572-01.01 /I- A ACT 2 0.5 GL MO c c FAI RPI 2Y SAMPLE LINE 10 CONTAINMENT ISOL LTJ J

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Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 172 of 222 Valve Summary Listing Page 172 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NM201A S/G 2S SMPL HOR CONT CN-2572-01.04 /I- S ACT 2 0.5 GL MO 0 c FAI RPI 2Y ISOL 06 FSC Q ST-C Q 2NM207A 2C SIG UPPER SHELL CN-2572-01.04 / S ACT 2 0.5 GL MO c c FAI RPI 2Y SAMPLE CONTAINMENT K-08 ISOL FSC Q ST-C Q 2NM210A 2C S/G SLOWDOWN CN-2572-01.04 / S ACT 2 0.5 GL MO 0 c FAI RPI 2Y SAMPLE CONTAINMENT K-09 ISOL FSC Q ST-C Q 2NM211S S/G 2C SMPL HOR CONT CN-2572-01.04 /I- S ACT 2 0.5 GL MO 0 c FAI RPI 2Y ISOL 09 FSC Q ST-C Q 2NM217S 20 SG UPPER SHELL CN-2572-01.04 / S ACT 2 0.5 GL MO c c FAI RPI 2Y SAMPLE CONTAINMENT K-11 ISOL FSC Q ST-C Q 2NM220S 20 S/G SLOWDOWN CN-2572-01.04 / S ACT 2 0.5 GL MO 0 c FAI RPI 2Y SAMPLE CONTAINMENT K-12 ISOL FSC Q ST-C Q

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Catawba Catawba Nuclear Plant Interval 4 Standa1 de ISTC IST 1.0.6 Page 173 of 222 Valve Summary Listing Page 173 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NM221A S/G 2D SMPL HOR CONT CN-2572-01.04 / B ACT 2 0.5 GL MO 0 c FAI RPI 2Y ISOL H-12 FSC Q ST-C Q 2NM424 PZR SMPL LINE BYP CK CN-2572-01.00 I J- AIC ACT 2 0.5 CK SA OIC OIC N/A eve II 03 cvo II LTJ J 2NM425 2C HOT LEG SAMPLE CN-2572-01.00 I AIC ACT 2 0.5 CK SA OIC OIC N/A eve II CONTAINMENT ISOL K-12 BYPASS CHECK cvo II LTJ J 2NM426 2A SIG SLOWDOWN CN-2572-01.04 / c ACT 2 0.5 CK SA OIC OIC N/A eve II SAMPLE CONTAINMENT K-02 ISOL BYPASS cvo II 2NM427 28 SIG SLOWDOWN CN-2572-01.04 / c ACT 2 0.5 CK SA O/C O/C NIA eve II SAMPLE CONTAINMENT K-05 ISOL BYPASS cvo II 2NM428 2C S/G UPPER SHELL CN-2572-01.04 / c ACT 2 0.5 CK SA OIC OIC NIA eve II SAMPLE CONTAINMENT K-09 ISOL BYPASS cvo II 2NM429 20 SIG UPPER SHELL CN-2572-01.04 / c ACT 2 0.5 CK SA O/C OIC N/A eve II SAMPLE CONTAINMENT K-12 ISOL BYPASS cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 174 of 222 Valve Summary Listing Page 174 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NS0018 NS PMP 8 SUCT FROM CN-2563-01.00 I 8 ACT 2 12 GA MO c OIC FAI RPI 2Y CONT SUMP C-13 FSC Q FSO Q ST-C Q ST-0 Q 2NS002 28 NS PUMP SUCTION CN-2563-01.00 I c ACT 2 0.75 RV SA c O/C NIA RV I RELIEF 8-13 2NS0038 NS PUMP 28 SUCT FROM CN-2563-01.00 I 8 ACT 2 12 GA MO 0 c FAI RPI 2Y FWST E-13 FSC Q ST-C Q 2NS004 FWST TO 28 NS PUMP CN-2563-01.00 I c ACT 2 12 CK SA OIC OIC N/A eve II SUCTION CHECK D-13 cvo II 2NS0128 NS SPRAY HOR 28 CONT CN-2563-01.00 I A ACT 2 8 GA MO c OIC FAI LT 2Y ISOL C-05 RPI 2Y FSC Q FSO Q ST-C Q ST-0 Q 2NS013 28 NS SPRAY HEADER CN-2563-01.00 I c ACT 2 8 CK SA OIC OIC N/A eve II CHECK C-03 cvo II

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Catawba 4.erval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 175 of 222 Valve Summary Listing Page 175 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NS0158 NS SPRAY HOR 28 CONT CN-2563-01.00 I A ACT 2 8 GA MO c OIC FAI LT 2Y ISOL E-05 RPI 2Y FSC Q FSO Q ST-C Q ST-0 Q 2NS016 NS SPRAY HOR 28 CN-2563-01.00 I c ACT 2 8 CK SA OIC O/C N/A eve II CHECKVLV E-02 cvo II 2NS018A NS PMP A SUCT FROM CN-2563-01.00 I J- 8 ACT 2 12 GA MO c O/C FAI RPI 2Y CONT SUMP 13 FSC Q FSO Q ST-C Q ST-0 Q 2NS019 2A NS PUMP SUCTION CN-2563-01.00 I c ACT 2 0.75 RV SA c OIC N/A RV I RELIEF K-13 2NS020A NSPUMP2ASUCTFROM CN-2563-01.00 I J- 8 ACT 2 12 GA. MO 0 c FAI RPI 2Y FWST 13 FSC Q ST-C Q 2NS021 FWST TO 2A NS PUMP CN-2563-01.00 /I- c ACT 2 12 CK SA O/C OIC N/A eve II SUCTION CHECK 13 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 176 of 222 Valve Summary Listing Page 176 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NS029A NS SPRAY HOR 2A CONT CN-2563-01.00 /I- A ACT 2 8 GA MO c OIC FAI LT 2Y ISOL 05 RPI 2Y FSC Q FSO Q ST-C Q ST-0 Q 2NS030 2A NS SPRAY HEADER CN-2563-01.00 /I- c ACT 2 8 CK SA OIC OIC NIA eve II CHECK 03 cvo II 2NS032A NS SPRAY HOR 2A CONT CN-2563-01.00 I A ACT 2 8 GA MO c O/C FAI LT 2Y ISOL K-05 RPI 2Y FSC Q FSO Q ST-C Q ST-0 Q 2NS033 2A NS SPRAY HEADER CN-2563-01.00 I c ACT 2 8 CK SA OIC OIC NIA eve II CHECK K-03 cvo II 2NS0388 28 ND PUMP TO CN-2563-01.00 IF- A ACT 2 8 GA MO c c FAI LT 2Y CONTAINMENT SPRAY 05 HEADER RPI 2Y FSC cs CSJ-CN-NS-03 ST-C cs CSJ-CN-NS-03 2NS041 ND 28/NS SPRAY CN-2563-01.00 I F- c ACT 2 8 CK SA OIC OIC N/A eve II HEADER CHECK 03

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                                                                                                                                   'ode ISTC Catawba Nuclear Plant Interval 4                                                                                                  . IST 1.0.6 Page 177 of 222 Valve Summary Listing Page 177 of 222 VALVE ID           FUNCTION     DRAWING/COOR       CAT ACT/ CLASS  SIZE TYPE  ACT        POSITION      TEST  FREQ  PROCEDURE           NOTES PASS                                             REQ NORM SAFE     FAIL 2NS043A     2A ND PUMP TO        CN-2563-01.00 I    A  ACT    2      8   GA   MO      c     c      FAI   LT    2Y CONTAINMENT SPRAY         H-05 HEADER                                                                                      RPI    2Y FSC   cs                    CSJ-CN-NS-03 ST-C   cs                    CSJ-CN-NS-03 2NS046     ND 2A/NS SPRAY       CN-2563-01.00 I    c   ACT   2      8   CK    SA    OIC   O/C    N/A   eve     II HEADER CHECK              G-03 cvo     II 2NS098     2A NS PUMP DISCH    CN-2563-01.00 I J-  c   ACT   2      10  CK    SA    OIC   OIC     N/A  eve     II CHECK                      09 cvo     II 2NS099     28 NS PUMP DISCH     CN-2563-01.00 I    c   ACT   2      10  CK    SA    OIC   O/C     N/A  eve     II CHECK                     D-09 cvo     II 2NV001A     NC LETDOWN TO REGEN  CN-2554-01.00 I    B   ACT   1      3   GA    AO     0     c       c   RPI    2Y HX ISOL                   H-02 FC   cs                    CSJ-CN-NV-12 FSC   cs                    CSJ-CN-NV-12 ST-C  cs                    CSJ-CN-NV-12 2NV002A     NC LETDOWN TO REGEN  CN-2554-01.00 I    B   ACT   1       1  GA    AO     0     c       c    RPI   2Y HX ISOL                   H-02 FC   cs                    CSJ-CN-NV-12 FSC   cs                    CSJ-CN-NV-12 ST-C  cs                    CSJ-CN-NV-12

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 178 of 222 Valve Summary Listing Page 178 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NV010A LETDOWN ORIFICE 28 CN-2554-01.00 I A ACT 2 2 GA AO 0 c c LT 2Y OUTLET CONTAINMENT H-08 ISOL RPI 2Y FC cs CSJ-CN-NV-11 FSC cs CSJ-CN-NV-11 ST-C cs CSJ-CN-NV-11 2NV011A LETDN ORIF 2C OTLT CN-2554-01.00 / I- A ACT 2 2 GA AO OIC c c LT 2Y CONT ISOL 09 RPI 2Y FC cs CSJ-CN-NV-11 FSC cs CSJ-CN-NV-11 ST-C cs CSJ-CN-NV-11 2NV013A LETDN ORIF 2A OTLT CN-2554-01.00 I A ACT 2 2 GA AO 0 c c LT 2Y CONT ISOL G-08 RPI 2Y FC cs CSJ-CN-NV-11 FSC cs CSJ-CN-NV-11 ST-C cs CSJ-CN-NV-11 2NV014 LETDOWN ORIFICE CN-2554-01.00 I NC ACT 2 .*' . ;3, RV SA c OIC N/A RV I HEADER RELIEF G-09 ' LTJ J

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Catawba 4~erval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 179 of 222 Valve Summary Listing Page 179 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NV015B LETON CONT ISOL CN-2554-01.00 I A ACT 2 3 GL MO 0 c FAI RPI 2Y H-12 FSC cs CSJ-CN-NV-01 ST-C cs CSJ-CN-NV-01 LTJ J 2NV022 CONTAINMENT ISOL CN-2554-01.00 I F- c ACT 2 3 CK SA OIC OIC N/A eve II CHECK 03 cvo II 2NV033 NV CHARGING TO LOOP CN-2554-01.00 I c ACT 1 3 CK SA O/C O/C N/A eve II A CHECK K-10 cvo II 2NV034 NV CHARGING TO LOOP CN-2554-01.00 I c ACT 1 3 CK SA OIC O/C N/A eve II A CHECK K-10 cvo II 2NV036 NV CHARGING TO NC CN-2554-01.00 I c ACT 2 0.75 CK SA c 0 N/A BOC II LOOP 0 BYPASS CHECK K-06 cvo II 2NV037A NV SUPPLY TO PZR AUX CN-2554-01.00 IL- B PASS 1 2 GL MO c c FAI RPI 2Y SPRAY 07 2NV038 NV SUPPLY TO PZR AUX CN-2554-01.00 IL- c ACT 2 3 CK SA O/C c NIA BOO II SPRAY CHECK 11 eve II 2NV040 NV CHARGING TO LOOP CN-2554-01.00 I c ACT 1 3 CK SA OIC O/C N/A eve II 0 CHECK K-03 cvo II 2NV041 NV CHARGING TO LOOP CN-2554-01.00 I c ACT 1 3 CK SA O/C O/C N/A eve II 0 CHECK K-02 cvo II 2NV044A NC PMP A SEAL SUPPLY CN-2554-01.05 / J- B PASS 2 2 GL MO 0 0 FAI RPI 2Y CONT ISOL 04 2NV046 2A NC PUMP SEAL CN-2554-01.05 I J- c ACT 2 2 CK SA OIC OIC N/A eve II SUPPLY CONT ISOL 05 CHECK cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 180 of 222 Valve Summary Listing Page 180 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NV049 2A NC PUMP SEAL CN-2554-01.05 / J- c ACT 1 2 CK SA OIC OIC NIA eve II SUPPLY INSIDE CHECK 07 cvo II 2NV055A NC PMP 8 SEAL SUPPLY CN-2554-01.05 / 8 PASS 2 2 GL MO 0 0 FAI RPI 2Y CONT ISOL H-04 2NV057 28 NC PUMP SEAL CN-2554-01.05 / c ACT 2 2 CK SA OIC OIC N/A eve II SUPPLY INSIDE CHECK H-05 cvo II 2NV060 28 NC PUMP SEAL CN-2554-01.05 / c ACT 1 2 CK SA O/C O/C N/A eve II SUPPLY INSIDE CHECK H-07 cvo II . 2NV066A NC PMP C SEAL SUPPLY CN-2554-01.05 IF- 8 PASS 2 2 GL MO 0 0 FAI RPI 2Y CONT ISOL 04 2NV068 2C NC PUMP SEAL CN-2554-01.05 / F- c ACT 2 2 CK SA OIC OIC N/A eve II SUPPLY INSIDE CHECK 05 cvo II 2NV071 2C NC PUMP SEAL CN-2554-01.05 / F- c ACT 1 2 CK SA OIC OIC N/A eve II SUPPLY INSIDE CHECK 07 cvo II 2NV077A NC PMP D SEAL SUPPLY CN-2554-01.05 / 8 PASS 2 2 GL MO 0 0 FAI RPI 2Y CONT ISOL D-04 2NV079 2D NC PUMP SEAL CN-2554-01.05 / c ACT 2 2 CK SA OIC OIC N/A eve II SUPPLY INSIDE CHECK D-05 cvo II 2NV082 2D NC PUMP SEAL CN-2554-01.05 / c ACT 1 2 CK SA OIC OIC N/A eve II SUPPLY INSIDE CHECK D-07 cvo II 2NV087 NC PUMPS SEAL CN-2554-01.00 I c ACT 2 3 RV SA c OIC N/A RV I RETURN HEADER INSIDE C-07 RELIEF

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Catawba terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 181 of 222 Valve Summary Listing Page 181 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NV089A NC PUMPS SEAL CN-2554-01.00 I A ACT 2 4 GA MO 0 c FAI LT 2Y RETURN CONT ISOL B-09 RPI 2Y FSC cs CSJ-CN-NV-02 ST-C cs CSJ-CN-NV-02 2NV090 NC PUMPS SEAL CN-2554-01.00 I AIC ACT 2 0.75 CK SA OIC OIC N/A eve II RETURN CONT ISOL D-10 RELIEVING CHECK cvo II LTJ J 2NV091B NC PMPS SEAL RET CN-2554-01.00 I A ACT 2 4 GA MO 0 c FAI LT 2Y CONT ISOL 8-11 RPI 2Y FSC cs CSJ-CN-NV-02 ST-C cs CSJ-CN-NV-02 2NV1228 LOOP C TO EXCESS CN-2554-01.00 I B PASS 1 1 GL AO c c c RPI 2Y LETDOWN HX ISOL D-12 2NV1238 LOOP C TO EXCESS CN-2554-01.00 I B PASS 1 1 GL AO c c c RPI 2Y LETDOWN HX ISOL D-10 2NV188A VCT OUTLET ISOL CN-2554-01.01 I B ACT 2 4 GA MO 0 c FAI RPI 2Y C-05 FSC cs CSJ-CN-NV-03 ST-C cs CSJ-CN-NV-03 2NV1898 VCT OUTLET ISOL CN-2554-01.01 I B ACT 2 4 GA MO 0 c FAI RPI 2Y C-04 FSC cs CSJ-CN-NV-03 ST-C cs CSJ-CN-NV-03

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 182 of 222 Valve Summary Listing Page 182 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NV202B NV PMPS A&B RECIRC CN-2554-01.06 / B ACT 2 2 GL MO 0 OIC FAI RPI 2Y ISOL D-02 FSC cs CSJ-CN-NV-07 FSO cs CSJ-CN-NV-07 ST-C cs CSJ-CN-NV-07 ST-0 cs CSJ-CN-NV-07 2NV203A NV PUMPS A&B RECIRC CN-2554--01 .06 I B ACT 2 2 GL MO 0 OIC FAI RPI 2Y ISOL D--02 FSC cs CSJ-CN-NV-07 FSO cs CSJ-CN-NV-07 ST-C cs CSJ-CN-NV-07 ST-0 cs CSJ-CN-NV-07 2NV206 SEAL WATER HX INLET CN-2554-01.06 / B PASS 2 4 PL AO 0 0 0 NTR NR C--03 2NV218 SEAL WATER HX OUTLET CN-2554--01.06 / B PASS 2 4 PL AO 0 0 0 NTR NR C--06 2NV220 SEAL WATER RETURN CN-2554--01.01 I c ACT 2 3 CK SA OIC c NIA BDO II TO VCT CHECK G-04 eve II 2NV223 VCT RELIEF TO RHT CN-2554--01.01 I c ACT 2 4 RV SA c O/C NIA RV I H--07 2NV236B BORIC ACID TO NV CN-2554-01.07 IF- B PASS 2 2 GL MO c c FAI RPI 2Y PUMPS SUCT 12 2NV252A NV PUMPS SUCT FROM CN-2554-01.07 I B ACT 2 8 GA MO c O/C FAI RPI 2Y FWST K-11 FSC cs CSJ-CN-NV-10 FSO cs CSJ-CN-NV-10 ST-C cs CSJ-CN-NV-10 ST-0 cs CSJ-CN-NV-10

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Catawba 4\9lerval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 183 of 222 Valve. Summary Listing Page 183 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NV2538 NV PUMPS SUCT FROM CN-2554-01.07 I 8 ACT 2 8 GA MO c O/C FAI RPI 2Y FWST K-12 FSC cs CSJ-CN-NV-10 FSO cs CSJ-CN-NV-10 ST-C cs CSJ-CN-NV-10 ST-0 cs CSJ-CN-NV-10 2NV254 2A & 28 NV PUMPS CN-2554-01.07 I c ACT 2 8 CK SA O/C O/C N/A eve II SUPPLY CHECK K-12 cvo II 2NV268 2A NV PUMP MINI-FLOW CN-2554-01.07 /I- c ACT 2 2 CK SA O/C O/C NIA eve II CHECK 05 cvo II 2NV270 2A NV PUMP DISCH CN-2554-01.07 /I- c ACT 2 4 CK SA OIC OIC N/A eve II

         .CHECK                        05 cvo     II 2NV273  2A & 28 NV PUMPS       CN-2554-01.07 I   c   ACT   2     1.5  RV    SA     c    OIC     N/A    RV    I SUCTION HEADER              D-11 RELIEF 2NV288  28 NV PUMP MINI FLOW   CN-2554-01.07 I   c   ACT   2      2   CK    SA    O/C   O/C     N/A   eve      II CHECK                       E-05 cvo      II 2NV290  28 NV PUMP DISCH       CN-2554-01.07  I  c   ACT   2      4   CK    SA    OIC   OIC     N/A   eve      II CHECK                       D-05 cvo      II 2NV312A  CHRG LINE CONT ISOL    CN-2554-01.02 /   8   ACT   2       3  GA    MO     0      c     FAI    RPI   2Y K-05 FSC  cs                    CSJ-CN-NV-04
                   .                                                                                    ST-C  cs                    CSJ-CN-NV-04 2NV3148  CHRG LINE CONT ISOL    CN-2554-01.02  I   8  ACT    2      3  GA    MO     0      c      FAI   RPI   2Y K-06 FSC  cs                    CSJ-CN-NV-04 ST-C  cs                    CSJ-CN-NV-04

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 184 of 222 Valve Summary Listing Page 184 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NV492 2A NC PUMP SEAL CN-2554-01.05 / J- c ACT 1 2 CK SA OIC O/C N/A eve II SUPPLY INSIDE CHECK 07 cvo II 2NV493 2B NC PUMP SEAL CN-2554-01.05 / c ACT 1 2 CK SA OIC O/C NIA eve II SUPPLY INSIDE CHECK H-07 cvo II 2NV494 2C NC PUMP SEAL CN-2554-01.05 / F- c ACT 1 2 CK SA OIC OIC N/A eve II SUPPLY INSIDE CHECK 07 CVO II 2NV495 2D NC PUMP SEAL CN-2554-01.05 / c ACT 1 2 CK SA O!C OIC

N/A eve II SUPPLY INSIDE CHECK D-07 cvo II 2NV813 ND PUMP DISCH TO NI CN-2554-01.07 I c ACT 2 8 CK SA OIC O/C N/A eve II PUMP SUCTION CHECK C-12 cvo II 2NV861 ND TO PZR SPRAY CN-2554-01.00 IL- c ACT 2 2 CK SA c OIC N/A eve II CHECK 09 cvo II 2NV865A STANDBY M/U PUMP CN-2554-01.08 / B ACT 2 3 GL MO OIC c FAI RPI 2Y SUCTION FROM H-01 TRANSFER TUBE FSC Q ST-C Q 2NV872A STDBY M/U PMP FILT CN-2554-01.08 IF- A ACT 2 2 GL MO OIC c FAI RPI 2Y OTLT 08 LTJ J FSC Q

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Catawba 41 terval Standa delSTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page. 185 of 222 Valve Summary Listing Page ~85 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NV874 STANDBY M/U CN-2554-01.08 / F- A/C ACT 2 2 CK SA OIC OIC N/A eve II CONTAINMENT HEADER 10 CHECK cvo II LTJ J 2NV878 STAND BY M/U TO NC CN-2554-01.08 / c ACT 2 0.75 CK SA O/C OIC N/A eve II PUMP 2A CHECK G-12 cvo II 2NV879 STANDBY M/U TO NC CN-2554-01.08 / c ACT 2 0.75 CK SA O/C O/C N/A eve II PUMP 2C CHECK G-13 cvo II 2NV880 STANDBY M/U TO NC CN-2554-01.08 / c ACT 2 0.75 CK SA OIC OIC N/A eve II PUMP 2B CHECK E-12 cvo II 2NV881 STANDBY MIU TO NC CN-2554-01.08 / c ACT 2 0.75 CK SA OIC OIC N/A eve II PUMP 2D CHECK E-13 cvo II 2NW002 2A NW SURGE CHAMBER CN-2569-01.00 I B PASS 2 0.5 sv so c c c RPI 2Y NITRO.GEN H-11 2NW006 2A NW SURGE CHAMBER CN-2569-01.00 I c ACT 2 1 CK SA OIC O/C NIA eve II RN SUPPLY CHECK G-12 cvo II 2NW008A 2A NW SURGE CHAMBER CN-1569-01.00 I B ACT 2 2 sv so c 0 0 RPI 2Y RN SUPPLY G-13 FO Q FSO Q ST-0 Q 2NW011 2A NW SURGE CHAMBER CN-2569-01.00 IF- B PASS 2 1 sv so c c c RPI 2Y YM SUPPLY ISOL 13

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 186 of 222 Valve Summary Listing Page 186 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW013A NW TO 2KC-425A CN-1569-01.00 I B ACT 2 1 sv so c 0 0 RPI 2Y E-09 FO Q FSO Q ST-0 Q 2NW017 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2KC425A E-11 cvo II 2NW020A 2A NW SURGE CHAMBER CN-2569-01.02 I F- B ACT 2 1 sv so c 0 0 RPI 2Y OUTLET 09 FO Q J FSO Q ST-0 Q 2NW021 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 1 CK SA OIC OIC N/A eve II 2WLA24 E-13 cvo II 2NW024 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 1 CK SA OIC OIC NIA eve II 2KC333A E-13 cvo II 2NW027 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 2KC320A E-14 cvo II 2NW035A CONT VLV INJ HDR 2A CN-2569-01.00 I B ACT 2 1 GL MO c OIC FAI RPI 2Y CONT ISOL H-09 FSC Q FSO Q ST-C Q ST-0 Q 2NW037 2A NW CONT HEADER CN-2569-01.00 /I- c ACT 2 1 CK SA O/C O/C N/A eve II

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Catawba 4.erval Standa de ISTC 1 Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 187 of 222 Valve Summary Listing Page 187 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW040 NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 2WL825A 11 cvo II 2NW043 NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT 2 0.5 CK SA O!C O/C N/A eve II 2WL805A 10 cvo II 2NW046A NW TO 2RN-484A CN-1569-01.00 I B ACT 2 1 sv so c 0 0 RPI 2Y K-09 FO Q FSO Q ST-0 Q 2NW047 NW SUPPLY CHECK TO CN-2569-01.00 IL- c ACT 2 0.5 CK SA OIC OIC N/A eve II 2WL867A 10 cvo II 2NW050 NW SUPPLY CHECK TO CN-2569-01.00 IL- c ACT 2 0.5 CK SA OIC O/C N/A eve II 2RN484A 11 cvo II 2NW057 2B NW SURGE CHAMBER CN-2569-01.00 I B PASS 2 0.5 sv so c c c RPI 2Y NITROGEN H-4 2NW061B 2B NW SURGE CHAMBER CN-1569-01.00 I B ACT 2 2 sv so c 0 0 RPI 2Y RN SUPPLY G-02 FO Q FSO Q ST-0 Q 2NW063 2B NW SURGE CHAMBER CN-2569-01.00 I c ACT 2 1 CK SA OIC OIC N/A eve II RN SUPPLY CHECK G-04 cvo II 2NW064 2B NW SURGE CHAMBER CN-2569-01.00 IF- B PASS 2 1 sv so c c c RPI 2Y YM SUPPLY 2

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant interval 4 IST 1.0.6 Page 188 of 222 Valve Summary Listing Page 188 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW068B NW TO 2RN-4878 & 2RN- CN-1569-01.00 I B ACT 2 1 sv so c 0 0 RPI 2Y 4378 E-05 FO Q FSO Q ST-0 Q 2NW069B 28 NW SURGE CHAMBER CN-1569-01.00 IF- B ACT 2 1 sv so c 0 0 RPI 2Y OUTLET 06 FO Q FSO Q ST-0 Q 2NW070 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 2NC56B E-05 cvo II 2NW074 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 2RN4378 . E-05 cvo II 2NW077 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2RN4878 E-04 cvo II 2NW080 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2WL869B E-03 cvo II 2NW086 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 2WL827B E-01 cvo II 2NW089 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 2RF389B C-05 cvo II 2NW092 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2RN4048 C-05 L cvo II

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ISTC Catawba Nuclear Plant Interval 4 : IST 1.0.6 Page 189 of 222 Valve Summary Listing Page , 189 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW095 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2KC338B C-04 cvo II 2NW098 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 2WL807B C-02 cvo II 2NW101 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 2RF4478 C-01 cvo II 2NW1058 CONT VLV INJ HOR 28 CN-2569-01.00 I 8 ACT 2 1 GL MO c OIC FAI RPI 2Y CONT ISOL H-06 FSC Q FSO Q ST-C Q ST-0 Q 2NW107 28 NW CONT HEADER CN-2569-01.00 11- c ACT 2 1 CK SA OIC OIC NIA eve II CHECK 06 cvo II 2NW109 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC NIA eve II 2KC4248 K-05 cvo II 2NW1108 NW SUPPLY TO 2KC4248 CN-1569-01.00 I 8 ACT 2 1 sv so c 0 0 RPI 2Y K-06 FO Q FSO Q ST-0 Q 2NW111 NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC NIA eve II 2KC3328 05 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 190 of 222 Valve Summary Listing Page 190 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW114 NW SUPPLY CHECK TO CN-2569-01.00 IL- c ACT 2 0.5 CK SA O/C OIC N/A eve II 2KC424B 05 cvo II 2NW120 NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 2KC332B 05 cvo II 2NW121 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 2WL827B E-01 cvo II 2NW123 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2WL869B E-03 cvo II 2NW124 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2RN487B E-04 cvo II 2NW125 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC NIA eve II 2RN437B E-05 cvo II 2NW126 NW SUPPLY CHECK TO CN-2569-01 :00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 2NC56B E-05 cvo II 2NW127 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O!C OIC N/A eve II 2RF447B C-01 cvo II 2NW128 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT. 2 0.5 CK SA OIC O/C NIA eve II 2WL807B C-02 cvo II 2NW129 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2KC338B C-04

                                                                        **                                        cvo   II 2NW130     NW SUPPLY CHECK TO    CN-2569-01.00  I   c   ACT   2     0.5    CK             SA  OIC   OIC    N/A   eve   II 2RN404B                    C-05 T

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Catawba 4~erval *1 Standa de ISTC l Catawba Nuclear Plant Interval 4 'IST 1.0.6 Page 191 of 222 Valve Summary Listing Page 191 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW131 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 2RF3898 C-05 cvo II 2NW132 NW SUPPLY CHECK TO CN-2569-01.00 I L- c ACT 2 0.5 CK SA O/C O/C NIA eve II 2WL867A 10 cvo II 2NW133 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC O/C NIA eve II 2RN484A K-11 cvo II 2NW135 NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC NIA eve II 2WL805A 10 cvo II 2NW136 NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC NIA eve II 2WL825A 11 cvo II 2NW138 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC NIA eve II 2KC425A E-11 cvo II 2NW139 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 1 CK SA OIC OIC NIA eve II 2WLA24 E-13 cvo II 2NW140 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 1 CK SA OIC OIC NIA eve II 2KC333A E-13 cvo II 2NW141 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC NIA eve II 2KC320A E-14 cvo II 2NW1458 NW TO KC-3388 & RN- CN-1569-01.00 I 8 ACT 2 0.5 sv so c 0 0 RPI 2Y 4048 C-05 FO Q FSO Q ST-0 Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 192 of 222 Valve Summary Listing Page 192 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW147

NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 2WLA21 07 -

cvo II 2NW148 NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT

2 0.5 CK SA OIC O/C N/A eve II 2WLA21 07 cvo II 2NW159 NW SUPPLY CHECK TO CN-2569-01.00 /I- c ACT 2 0.5 CK SA OIC OIC N/A eve II NV-10A 12 cvo II 2NW160 NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT 2 0.5 CK SA OIC OIC N/A eve II 2NV-10A 12 cvo II .

2NW163 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 2NV-11A K-12 cvo II 2NW164 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2NV-11A K-12 cvo II 2NW168 . NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2NV-13A K-13 cvo II 2NW169 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 2NV-13A K-13 cvo II 2NW171 NW SUPPLY CHECK TO CN-2569-01.00 I J- c ACT 2 0.5 CK SA OIC O/C N/A eve II 2NV-89A 13 cvo II 2NW172 NW SUPPLY CHECK TO CN-2569-01.00 /I- c ACT 2 0.5 CK SA O/C OIC N/A eve II 2NV-89A 13

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Catawba 4 1 terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 193 of 222 Valve Summary Listing Page 193 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW175A NWTO 2Nl-173A CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y C-12 FO Q FSO Q ST-0 Q 2NW178 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 2Nl-173A C-12 cvo II 2NW179 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2Nl-173A C-12 cvo II 2NW180A NW TO 2NS-43A CN-1569-01.00/ B ACT 2 0.5 sv so c 0 0 RPI 2Y C-13 FO Q FSO Q ST-0 Q 2NW183 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 2NS-43A C-13 cvo II 2NW184 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2NS-43A C-13 cvo II 2NW185A NWTO 2Nl-162A CN-1569-01.00/ B ACT 2 0.5 sv so c 0 0 RPI 2Y C-13 FO Q FSO Q ST-0 Q 2NW188 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2Nl-162A C-13 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 194 of 222 Valve Summary Listing Page 194 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW189 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC O/C N/A eve II 2Nl-162A C-13 cvo II 2NW195A NW TO 2NS-32A CN-1569-01.00 IF- B ACT 2 0.5 sv so c 0 0 RPI 2Y 08 FO Q FSO Q ST-0 Q 2NW196 NW SUPPLY CHECK TO CN-2569-01.00 IF- c ACT 2 0.5 CK SA O/C O/C NIA eve II 2NS-32A 08 cvo II 2NW197 NW SUPPLY CHECK TO CN-2569-01.00 IF- c ACT 2 0.5 CK SA OIC OIC N/A eve II 2NS-32A 08 cvo II 2NW200A NW TO 2NS-29A CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y E-08 FO Q FSO Q ST-0 Q . 2NW201 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 2NS-29A E-08 cvo II 2NW202 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC NIA eve II 2NS-29A D-08 cvo II 2NW205 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2KC-305B E-07 cvo II 2NW206 NW SUPPLY CHECK TO CN-2569-01.00 I F- c ACT 2 0.5 CK SA O/C O/C N/A eve II 2KC-305B 07 cvo II t.--..

Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 195 of 222 Valve Summary Listing Page 195 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW209 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 2KC-315B E-07 cvo II 2NW210 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 2KC-315B E-07 cvo II 2NW213 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2NV-91B C-07 cvo II ' 2NW214 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC NIA eve II 2NV-91 B C-07 cvo II 2NW217B NWTO 2NS-12B CN-1569-01.001 B ACT 2 0.5 sv so c 0 0 RPI 2Y C-08 FO Q

                                                                   .                                  FSO    Q ST-0  Q 2NW218  NW SUPPLY CHECK TO      CN-2569-01.00 I  c   ACT   2     0.5   CK   SA    OIC   OIC     NIA  eve     II 2NS-12B                      C-08 cvo     II 2NW219  NW SUPPLY CHECK TO      CN-2569-01.00 I  c   ACT   2     0.5   CK   SA    OIC   OIC     N/A  eve     II 2NS-12B                      C-08 cvo     II 2NW222B  NWTO 2NS-15B            CN-1569-01.00 I  B   ACT   2      0.5  sv   so     c      0      0    RPI  2Y C-08 FO    Q FSO     Q ST-0  Q 2NW223   NW SUPPLY CHECK TO     CN-2569-01.00 I  c   ACT    2     0.5  CK   SA    OIC   OIC     NIA  eve     II 2NS-15B                      C-09 cvo     II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 196 of 222 Valve Summary Listing Page 196 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NVV224 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2NS-15B C-09 cvo II 2NW227B NW TO 2NS-38B CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y C-09 FO Q FSO Q ST-0 Q 2NW230 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC O/C NIA eve II 2NS-38B C-09 cvo II 2NVV231 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 2ND-38B C-09 CVO II 2NW237B NWTO 2Nl-178B CN-1569-01.00/ B ACT 2 0.5 sv so c 0 0 RPI 2Y C-11 FO Q FSO Q ST-0 Q 2NVV240 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C OIC N/A eve II 2Nl-178B C-11 CVO II 2NVV241 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2Nl-178B C-11 CVO II 2NW242B NWT02Nl-183B CN-1569-01.00 I B ACT 2 0.5 sv so c 0 0 RPI 2Y C-11 FO Q FSO Q ST-0 Q

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Catawba 4 terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 197 of 222 Valve Summary Listing Page 197 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2NW245 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA OIC OIC N/A eve II 2Nl-183B C-11 cvo II 2NW246 NW SUPPLY CHECK TO CN-2569-01.00 I c ACT 2 0.5 CK SA O/C O/C N/A eve II 2Nl-183B C-11 cvo II 2NW247 2A NW INSIDE CONT CN-2569-01.00 I J- c ACT 2 1 RV SA c OIC N/A RV I RELIEF 11 2NW248 NW RELIEF CN-2569-01.00 I c ACT 2 1 RV SA c OIC N/A RV I D-11 2NW249 NW RELIEF CN-2569-01.00 I c ACT 2 1 RV SA c O/C N/A RV I D-06 2RF389B UNIT 2 RF CONTAINMENT CN-1599-02.01 / A ACT 2 4 GA MO c c FAI LT 2Y ISOL E-01 RPI 2Y FSC cs CSJ-CN-RF-02 ST-C cs CSJ-CN-RF-02 2RF392 CONT BLDG HOSE RACK CN-1599-02.01 / NC ACT 2 4 CK SA OIC OIC N/A eve II SUPPLY HEADER CHECK E-04 cvo II LTJ J 2RF447B RF CONT ISOL CN-1599-02.01 / A ACT 2 4 GA MO c c FAI LT 2Y G-04 RPI 2Y FSC cs CSJ-CN-RF-02 ST-C cs CSJ-CN-RF-02 2RF448 CONT BLDG SPRINKLER CN-1599-02.01 I NC ACT 2 4 CK SA OIC OIC N/A eve II SUPPLY HEADER CHECK H-07 cvo II LTJ J

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 198 of 222 Valve Summary Listing Page 198 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2RF457B ANNULUS SPRINKLER CN-1599-02.01 / B ACT NC 6 GA MO 0 c FAI RPI 2Y SYSTEM HEADER ISOL G-03 FSC Q ST-C Q 2RN009 2A RN PUMP DISCH CN-1574-01.00 I c ACT 3 30 CK SA O/C O/C N/A eve II CHECK E-11 cvo II 2RN011A 2A RN PUMP MOTOR CN-1574-01.00 I B ACT 3 2 BL MO 0 0 FAI RPI 2Y COOLER INLET ISOL E-09 FSO Q ST-0 Q 2RN018 2B RN PUMP DISCH CN-1574-01.02 / F- c ACT 3 30 CK SA OIC OIC N/A eve II CHECK VALVE 13 CVO II 2RN020B 2B RN PUMP MOTOR CN-1574-01.02 / B ACT 3 2 BL MO c 0 FAI RPI 2Y COOLER SUPPLY ISOL E-11 FSO Q ST-0 Q 2RN028A 2A RN PUMP DISCH ISOL CN-1574-01.00 I B ACT 3 30 BF MO OIC 0 FAI RPI 2Y E-11 FSO Q ST-0 Q 2RN030A 2A RN STRAINER CN-1574-01.00/ B ACT 3 4 BL MO c 0 FAI RPI 2Y BACKFLUSH ISOL D-08 FSO Q ST-0 Q 2RN038B 2B RN PUMP DISCH ISOL CN-1574-01.02 / F- B ACT 3 30 BF MO OIC 0 FAI RPI 2Y 13 FSO Q Q

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Catawba 4~erval Standa de ISTC Catawba Nuclear Plant Interval 4 'IST 1.0.6 Page 199 of 222 Valve Summary Listing Page 199 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2RN040B 2B RN STRAINER CN-1574-01.02/ B ACT 3 4 BL MO c 0 FAI RPI 2Y BACKFLUSH ISOL 0-09 FSO Q ST-0 Q 2RN047A RN SUPPLY X-OVER ISOL CN-1574-01.01 / B ACT 3 30 BF MO 0 c FAI RPI 2Y E-06

         '                                                                                             FSC    Q ST-C  Q 2RN048B  RN SUPPLY X-OVER ISOL   CN-1574-01.01 /    B   ACT   3     30   BF    MO    0    c      FAI    RPI  2Y E-12 FSC    Q ST-C  Q 2RN049A   NON-ESS SUPPLY HOR     CN-1574-01.01 /    B   ACT   3     20   BF    MO    0    c      FAI    RPI  2Y                  '

ISOL D-11 FSC Q ST-C Q 2RN050B NON-ESS SUPPPLY HOR CN-1574-01.01 / B ACT 3 20 BF MO 0 c FAI RPI 2Y ISOL 0-11 FSC Q ST-C Q 2RN051A NON-ESS RET HOR ISOL CN-1574-01.05 / F- B ACT 3 20 BF MO 0 c FAI RPI 2Y 07 FSC Q ST-C Q 2RN052B NON-ESS RET HOR ISOL CN-1574-01.05 / F- B ACT 3 20 BF MO 0 c FAI RPI 2Y 07 FSC Q ST-C Q 2RN067A 2A RN HEADER SUPPLY CN-1574-01.01 IF- B PASS 3 30 BF MO 0 0 FAI RPI 2Y ISOL 13

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 200 of 222 Valve Summary Listing Page 200 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2RN069B 2B RN HEADER SUPPLY CN-1574-01.01 IF- B PASS 3 30 BF MO 0 0 FAI RPI 2Y ISOL 06 2RN144A 2A NS HX INLET ISOL CN-2574-02.00 I B ACT 3 18 BF MO c 0 FAI RPI 2Y C-05 FSO Q ST-0 Q 2RN147 2A NS HX RELIEF CN-2574-02.00 I c ACT 3 4 RV SA c OIC NIA RV I G-14 . - 2RN148A 2A NS HX OUTLET ISOL CN-2574-02.00 IL- B ACT 3 18 BF MO c 0 FAI RPI 2Y 01 FSO Q ST-0 Q 2RN225B 2B NS HX INLET ISOL CN-2574-02.041 B ACT 3 18 BF MO c 0 FAI RPI 2Y C-06 FSO Q ST-0 Q 2RN228 2B NS HX RELIEF CN-2574-02.041 c ACT 3 4 RV SA c OIC NIA RV I H-13 2RN229B 2B NS HX OUTLET ISOL CN-2574-02.041 L- B ACT 3 18 BF MO c 0 FAI RPI 2Y 07 FSO Q ST-0 Q 2RN232A 2A DIG HX INLET ISOL CN-2574-02.01 I B ACT 3 10 BF MO c 0 FAI RPI 2Y D-02 FSO Q ST-0 Q 2RN235 2A DIG COOLING WATER CN-2574-02.011 c ACT 3 0.75 RV SA c OIC NIA RV I HX RELIEF H-03 2RN250A 2A RN HEADER TO CA CN-2574-02.011. B ACT 3 ... 8 GA MO c 0 FAI RPI 2Y PUMPS SUCTION ISOL D-07 FSO Q ST-0 Q

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Catawba 41 terval Standa de ISTC Catawba Nuclear Plant Interval 4 *1sT 1.0.6 Page 201 of 222 Valve Summary Listing Page 201 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2RN287A 2A KC HX INLET ISOL CN-2574-02.01 / B PASS 3 20 BF MO 0 0 *FAI RPI 2Y D-13 2RN290 2A KC HX RELIEF CN-2574-02.01 /I- c ACT 3 0.75 RV SA c OIC N/A RV I 12 2RN291 2A KC HX OUTLET CN-2574-02.01 I J- B ACT 3 12 BL AO 0 0 0 RPI 2Y THROTTLE VALVE 13 FO Q FSO Q ST-0 Q 2RN292B 2B DIG HX INLET ISOL CN-2574-02.05 / B ACT 3 10 BF MO c 0 FAI RPI 2Y E-02 FSO Q ST-0 Q 2RN295 2B D/G COOLING WATER CN-2574-02.05 /I- c ACT 3 0.75 RV SA c O/C N/A RV I HX RELIEF 02 2RN310B 2B RN HEADER TO CA CN-2574-02.05 / B ACT 3 8 GA MO c 0 FAI RPI 2Y PUMPS SUCTION ISOL G-06 FSO Q ST-0 Q 2RN347B 2B KC HX INLET ISOL CN-2574-02.05 / F- B PASS 3 20 BF MO 0 0 FAI RPI 2Y 13 2RN350 2B KC HX RELIEF CN-2574-02.05 /I- . c ACT 3 0.75 RV SA c OIC N/A RV I 14 2RN351 2B KC HX OUTLET CN-2574-02.05 /I- B ACT 3 12 BL AO 0 0 0 RPI 2Y THROTTLE 13 FO Q FSO Q ST-0 Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 202 of 222 Valve Summary Listing Page 202 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2RN404B UPPER CONT VENT UNIT CN-2574-02.07 I A ACT 2 6 GA MO 0 c FAI RPI 2Y SUP D-04 LT 2Y FSC Q ST-C Q 2RN405 UPPER CONT VENT UNIT CN-2574-02.07 I AIC ACT 2 6 CK SA OIC c N/A BOO II SUPPLY CHECK E-03 eve II LTJ J 2RN437B LOWER CONT VENT UNIT CN-2574-02.02 / L- A ACT 2 12 GA MO 0 c FAI RPI 2Y SUP 06 LT 2Y FSC cs CSJ-CN-RN-02 ST-C cs CSJ-CN-RN-02 2RN438 LOWER CONT VENT CN-2574-02.02 / L- A/C ACT 2 12 CK SA OIC c N/A BOO II UNITS SUPPLY 2 CONT 08 ISOL INSIDE CHECK eve II LTJ J 2RN484A LOWER CONT VENT UNIT CN-2574-02.02 / A ACT 2 12 GA MO 0 c FAI RPI 2Y RETURN C-08 LT 2Y FSC cs CSJ-CN-RN-03 ST-C cs CSJ-CN-RN-

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Catawba 49terval Standa de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 203 of 222 Valve Summary Listing Page 203 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2RN485 LOWER CONT VENT CN-2574-02.02 / AJC ACT 2 0.75 CK SA OIC OIC N/A eve II UNITS RETURN INSIDE B-08 ISOL PRESS RELIEF CHK VL cvo II LTJ J 2RN487B LOWER CONT VENT UNIT CN-2574-02.02 / A ACT 2 12 GA MO 0 c FAI RPI 2Y RET C-07 LT 2Y FSC cs .CSJ-CN-RN-03 ST-C cs CSJ-CN-RN-03 2RN807 2B NC PUMP MOTOR AIR CN-2574C02.03 / J- c ACT NC 0.75 RV SA c OIC N/A RV I COOLER SAFETY RELIEF 07 2RN846A 2A DIG HX RETURN TO CN-2574-02.01 I J- B ACT 3 10 BF MO c 0 FAI RPI 2Y SNSWP 02 FSO Q ST-0 Q 2RN847A 2A DIG HX RETURN TO CN-2574-02.01 I J- B ACT 3 10 BF MO 0 c FAI RPI 2Y LAKE 01 FSC Q ST-C Q 2RN848B 2B DIG HX RETURN TO CN-2574-02.05 / J- B ACT 3 10 BF MO c 0 FAI RPI 2Y SNSWP 02 FSO Q ST-0 Q 2RN849B 2B DIG HX RETURN TO CN-2574-02.05 / J- B ACT 3 10 BF MO 0 c FAI RPI 2Y LAKE 02 FSC Q ST-C Q 2RN854 2A RN PUMP DISCH CN-1574-01.00 IF- c ACT 3 4 VB SA c OIC N/A RV I VACUUM BREAKER 12

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 204 of 222 Valve Summary Listing Page 204 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2RN855 2B RN PUMP DISCH CN-1574-01.02 / F- c ACT 3 4 VB SA c OIC NIA RV I VACUUM BREAKER 14 2RN861 UPPER CONT VENT CN-2574-02.07 I c ACT NC 0.75 RV SA c OIC NIA RV I UNITS SUPPLY HEADER E-03 RELIEF 2RN863 LOWER CONT VENT CN-2574-02.021 c ACT NC 0.75 RV SA c OIC NIA RV I UNITS SUPPLY HEADER K-09 RELIEF 2RNC66 2A NS HX WET LAYUP CN-2574-02.00 I c ACT 3 2 CK SA OIC c NIA BOO II RECIRC PUMP OUTLET D-07 CHECK eve II 2RNC67 . 2A NS HX WET LAYUP CN-2574-02.00 I B ACT 3 BL MA NIA c NIA FS 2Y INLET ISOL K-09 2RNC69 2B NS HX WET LAYUP CN-2574-02.041 c ACT 3 1 CK SA OIC c NIA BOO II RECIRC PUMP OUTLET C-07 CHECK eve II 2RNC70 2B NS HX WET LAYUP CN-2574-02.041 B ACT 3 BL MA 0 c NIA FS 2Y INLET ISOL K-09 2RNP47 2A1 DIG STARTING AIR CN-2574-02.01 11- c ACT 3 1 CK SA OIC c NIA BOO II AFTERCOOLER OUTLET 03 CHECK eve II 2RNP48 2A2 DIG STARTING AIR CN-2574-02.01 11- c ACT 3 1 CK SA OIC c NIA BOO II AFTERCOOLER OUTLET 01 CHECK eve II 2RNP49 2B1 DIG STARTING AIR CN-2574-02.0511- c ACT 3 1. CK SA OIC c NIA BOO II AFTERCOOLER OUTLET 01 CHECK eve II

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Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 205 of 222 Valve Summary Listing Page 205 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2RNP50 282 DIG STARTING AIR CN-2574-02.05 /I- c ACT 3 1 CK SA O/C c N/A BOO II AFTERCOOLER OUTLET 03 CHECK eve II 2SA001 28 SIG MAIN STEAM TO CN-2593-01.01 I B ACT 2 6 GA MA 0 O/C N/A FS 2Y

           #2 CAPT MAINTENANCE         G-04 ISOL 2SA002    28 SIG MAIN STEAM TO   CN-2593-01.01 I   B   ACT   2      4   GA    AO    c     0       0   RPI   2Y
           #2 CAPT                     G-04 FO    Q FSO    Q ST-0  Q 2SA003    28 SIG MAIN STEAM TO   CN-2593-01.01 I   c   ACT   2      6   SCK   SA   OIC   OIC     NIA   FS   2Y UNIT 2 CAPT STOP           G-05 CHECK eve    II cvo    II 2SA004     2C S/G MAIN STEAM TO  CN-2593-01.01 I   B   ACT   2      6   GA    MA    0    OIC     N/A   FS   2Y
           #2 CAPT MAINTENANCE         H-04 ISOL 2SA005     2C SIG MAIN STEAM TO  CN-2593-01.01 I   B   ACT   2      4    GA   AO    c     0       0    RPI  2Y
           #2 CAPT                     H-04 FO    Q FSO    Q ST-0  Q 2SA006    2C S/G MAIN STEAM TO  CN-2593-01.01 I   c   ACT   2      6   SCK   SA   O/C   O/C     N/A   FS   2Y UNIT 2 CAPT STOP           H-05 CHECK eve     II cvo     II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 206 of 222 Valve Summary Listing Page 206 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2SM001 20 S/G MAIN STEAM ISOL CN-2593-01.00 I B ACT 2 34 GL AO 0 c c RPI 2Y K-13 FC cs CSJ-CN-SM-01 FSC cs CSJ-CN-SM-01 ST-C cs CSJ-CN-SM-01 2SM003 2C S/G MAIN STEAM ISOL CN-2593-01.00 I B ACT 2 34 GL AO 0 c c RPI 2Y H-13 FC cs CSJ-CN-SM-01 FSC cs CSJ-CN-SM-01 ST-C cs CSJ-CN-SM-01 2SM005 28 S/G MAIN STEAM ISOL CN-2593-01.00 IF- B ACT 2 34 GL AO 0 c c RPI 2Y 13 FC cs CSJ-CN-SM-01 FSC cs CSJ-CN-SM-01 ST-C cs CSJ-CN-SM-01 2SM007 2A SIG MAIN STEAM ISOL CN-2593-01.00 I B ACT 2 34 GL AO 0 c c RPI 2Y C-13 FC cs CSJ-CN-SM-01 FSC cs CSJ-CN-SM-01 ST-C cs CSJ-CN-SM-01 2SM009 20 SIG MAIN STEAM ISOL CN-2593-01.00 I J- B ACT 2 3 FC AO c c c RPI 2Y BYPASS 13 FC Q FSC Q ST-C Q

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Catawba 4Wterval Stand a de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 207 of 222 Valve Summary Listing Pa-ge 207 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2SM010 2C SIG MAIN STEAM ISOL CN-2593-01.00 I B ACT 2 3 FC AO c c c RPI 2Y BYPASS G-13 FC Q FSC Q ST-C Q 2SM011 2B SIG MAIN STEAM ISOL CN-2593-01.00 I B ACT 2 3 FC AO c c c RPI 2Y BYPASS E-13 FC Q FSC Q ST-C Q 2SM012 2A SIG MAIN STEAM ISOL CN-2593-01.00 I B ACT 2 3 FC AO c c c RPI 2Y BYPASS B-13 FC Q FSC Q ST-C Q 2SM074B SIG 20 OTLT HDR BLOWN CN-2593-01.07 I B PASS 2 2 GA MO 0 0 FAI RPI 2Y CN E-06 2SM075A SIG 2C OTLT HDR BLOWN CN-2593-01.07 I B PASS 2 2 GA MO 0 0 FAI RPI 2Y CN E-13 2SM076B SIG 2B OTL T HDR BLOWN CN-2593-01.07 I B PASS 2 2 GA MO 0 0 FAI RPI 2Y CN E-09 2SM077A SIG 2A OTLT HDR BLOWN CN-2593-01.07 I B PASS 2 2 GA MO 0 0 FAI RPI 2Y CN E-02 2SV001 2D SIG POWER CN-2593-01.00 IL- B ACT 2 6 PORV AO 0 OIC c FC 2Y OPERATED RELIEF 12 VALVE FSC 2Y FSO 2Y MS 2Y RPI 2Y STT 2Y ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 208 of 222 Valve Summary Listing Page 208 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2SV002 2D S/G SAFETY NO 1 CN-2593-01.00 I c ACT 2 6 RV SA c O/C NIA RV I K-04 2SV003 2D SIG SAFETY NO 2 CN-2593-01.00 I c ACT 2 6 RV SA c OIC NIA RV I K-06 2SV004 20 SIG SAFETY NO 3 CN-2593-01.00 I c ACT 2 6 RV SA c OIC NIA RV I K-07 2SV005 20 SIG SAFETY NO 4 CN-2593-01.00 I c ACT 2 6 RV SA c OIC NIA RV I K-08 2SV006 20 SIG SAFETY NO 5 CN-2593-01.00 I c ACT 2 6 RV SA c OIC NIA RV I K-10 2SV007 2C SIG POWER CN-2593-01.00 11- B ACT 2 6 PORV AO 0 OIC c FC 2Y OPERATED RELIEF 12 VALVE FSC 2Y FSO 2Y MS 2Y RPI 2Y STT 2Y ST-C Q 2SV008 2C SIG SAFETY NO 1 CN-2593-01.00 11- c ACT 2 6 RV SA c OIC NIA RV I 04 2SV009 2C SIG SAFETY NO 2 CN-2593-01.00 11- c ACT 2 6 RV SA c OIC NIA RV I 06 2SV010 2C SIG SAFETY NO 3 CN-2593-01.00 11- c ACT 2 6 RV SA* c OIC NIA RV I 07 2SV011 2C SIG SAFETY NO 4 CN-2593-01.0011- c ACT 2 6 RV SA c OIC NIA RV I 08 2SV012 2C SIG SAFETY NO 5 CN-2593-01.00 11- c ACT 2 6 RV SA c OIC NIA RV I 10

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Catawba 4' 'terval Standa delSTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 209 of 222 Valve Summary Listing Page 209 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2SV013 28 SIG POWER CN-2593-01.00 IF- 8 ACT 2 6 PORV AO 0 OIC c FC 2Y OPERATED RELIEF 12 VALVE FSC 2Y FSO 2Y MS 2Y RPI 2Y STT 2Y ST-C Q 2SV014 28 S/G SAFETY NO 1 CN-2593-01.00 IF- c ACT 2 6 RV SA c OIC N/A RV I 04 2SV015 28 SIG SAFETY NO 2 CN-2593-01.00 IF- c ACT 2 6 RV SA c OIC N/A RV I 06 2SV016 28 SIG SAFETY NO 3 CN-2593-01,00 IF- c ACT 2 6 RV SA c OIC N/A RV I 07 2SV017 28 S/G SAFETY NO 4 CN-2593-01.00 I F- c ACT 2 6 RV SA c OIC N/A RV I 08 2SV018 28 SIG SAFETY NO 5 CN-2593-01.00 IF- c ACT 2 6 RV SA c OIC N/A RV I 10 2SV019 2AS/G POWER CN-2593-01.00 I 8 ACT 2 6 PORV AO 0 O/C c FC 2Y OPERATED RELIEF D-12 VALVE FSC 2Y FSO 2Y MS 2Y RPI 2Y STT 2Y ST-C Q 2SV020 2A S/G SAFETY NO 1 CN-2593-01.00 I c ACT 2 6 RV SA c OIC N/A RV I C-04 2SV021 2A S/G SAFETY NO 2 CN-2593-01.00 I c ACT 2 6 RV SA c OIC NIA RV I C-06 2SV022 2A S/G SAFETY NO 3 CN-2593-01.00 I c ACT 2 6 RV SA c OIC N/A RV I C-07

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 210 of 222 Valve Summary Listing Page 21 O of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2SV023 2A S/G SAFETY NO 4 CN-2593-01.00 I c ACT 2 6 RV SA c O/C N/A RV I C-08 2SV024 2A SIG SAFETY NO 5 CN-2593-01.00 I c ACT 2 6 RV SA c O/C N/A RV I C-10 2SV025B 2D SIG PORV ISOL CN-2593-01.00 I B ACT 2 6 GA MO 0 OIC FAI RPI 2Y K-11 FSC Q FSO Q ST-C Q ST-0 Q 2SV026B 2C S/G PORV ISOL CN-2593-01.00 / I- B ACT 2 6 GA MO 0 *01c FAI RPI 2Y 11 FSC Q FSO Q ST-C Q ST-0 Q 2SV027A 2A SIG PORV ISOL CN-2593-01.00 I B ACT 2 6 GA MO 0 OIC FAI RPI 2Y C-11 FSC Q FSO Q ST-C Q ST-0 Q 2SV028A 28 S/G PORV ISOL CN-2593-01.00 IF- B ACT 2 6 GA MO 0 OIC FAI RPI 2Y 11 FSC Q FSO Q

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Catawba 49terval Stand a de ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 211 of 222 Valve Summary Listing Page 211 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2VB083B VB CONT ISOL CN-2605-3.211-07 A ACT 2 2 DA MO c c FAI RPI 2Y LTJ J FSC Q ST-C Q 2VB085 UNIT 2 CONTAINMENT CN-2605-3.2 I H- NC ACT 2 2 CK SA c c N/A BOO II HEADER SUPPLY CHECK 07 eve II LTJ J 2VG005 2A DIG ENG STARTING CN-2609-04.00 /I- c ACT 3 1 CK SA O/C O/C N/A eve II AIR DRYER 2A1 DISCH 02 CHECK cvo II 2VG006 2A DIG ENG STARTING CN-2609-04.00 I c ACT 3 1 CK SA O/C OIC N/A eve II AIR DRYER 2A2 DISCH H-13 CHECK cvo II 2VG007 2A DIG ENG STARTING CN-2609-04.00 /I- c ACT 3 1 CK SA O/C O/C N/A eve II AIR DRYER 2A1 DISCH 02 CHECK cvo II 2VG008 2A DIG ENG STARTING CN-2609-04.00 / I- c ACT 3 1 CK SA OIC OIC N/A eve II AIR DRYER 2A2 DISCH 13 CHECK cvo II 2VG015 2A DIG ENG STARTING CN-2609-04.00 I c ACT 3 3 CK SA OIC OIC N/A eve II AIR TANK2A1 OUTLET G-02 CHECK cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 212 of 222 Valve Summary Listing Page 212 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2VG016 2A DIG ENG STARTING CN-2609-04.00 I c ACT 3 3 CK SA OIC O/C N/A eve II AIR TANK2A2 OUTLET G-13 CHECK cvo II 2VG049 DIG STARTING AIR CN-2609-04.01 /I- c ACT 3 1 CK SA OIC OIC NIA eve II DRYER 281 DISCH 02 CHECK cvo II 2VG050 28 D/G ENG STARTING CN-2609-04.01 I c ACT 3 1 CK SA O/C O/C N/A eve II AIR DRYER 282 DISCH H-13 CHECK cvo II 2VG051 28 DIG ENG STARTING CN-2609-04.01 I J- c ACT 3 1 CK SA OIC OIC N/A eve II AIR DRYER 281 DISCH 02 CHECK cvo II 2VG052 28 D/G ENG STARTING CN-2609-04.01 I J- c ACT 3 1 CK SA O/C O/C N/A eve II AIR DRYER 282 DISCH 13 CHECK cvo II 2VG059 28 D/G ENG STARTING CN-2609-04.01 I c ACT 3 3 CK SA OIC OIC N/A eve II AIR TANK 281 OUTLET G-02 CHECK cvo II 2VG060 28 DIG ENG STARTING CN-2609-04.01 I c ACT 3 3 CK SA O!C OIC N/A eve II Al R TANK 282 OUTLET G-13 CHECK cvo II 2VG133 28 D/G ENG STARTING CN-2609-04.01 /I- c ACT 3 0.q CK SA O/C O/C N/A eve II AIR TANK281 SUP TO 02 ENG CONTROL PNL 28 C

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Catawba terval Standa1 ode ISTC 1 Catawba Nuclear Plant Interval 4 'IST 1.0.6 Page 213 of 222 Valve Summary Listing Page ~13 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2VG134 2B DIG ENG STARTING CN-2609-04.01 I c ACT 3 0.5 CK SA O/C OIC N/A eve II AIR TANK 282 SUP TO H-13 ENG CONTROL PNL 2B C cvo II 2VG135 2A DIG ENG STARTING CN-2609-04.00 I c ACT 3 0.5 CK SA O/C OIC N/A eve II AIRTANK2A1 SUP TO H-02 ENG CONTROL PNL 2A C cvo II 2VG136 2A DIG ENG STARTING CN-2609-04.00 I c ACT 3 0.5 CK SA OIC OIC N/A eve II AIR TANK 2A2 SUP TO H-13 ENG CONTROL PNL 2A C cvo II 2VI077B VI CONT ISOL CN-2605-01.05 /I- A ACT 2 2 DA MO 0 c FAI RPI 2Y 05 FSC cs CSJ-CN-VI-02 ST-C cs CSJ-CN-VI-02 LTJ J 2VI079 VI CONTAINMENT CN-2605-01.05 /I- AIC ACT 2 2 CK SA 0 c N/A BOO II HEADER CHECK 08 eve II LTJ J 2Vl312A VI TO VP CONT ISOL CN-2605-01.05 /I- A ACT 2 2 GL MO 0 c- FAI RPI 2Y 06 LTJ J FSC Q ST-C Q 2Vl367 PORV 2NC 34A VI CN-2605-01.05 / c ACT 3 2 CK SA 0 c N/A BOO II SUPPLY CHECK E-09 eve II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 214 of 222 Valve Summary Listing Page 214 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2Vl368 PORV 2NC 32B VI CN-2605-01.05 / F- c ACT 3 2 CK SA 0 c N/A BOO II SUPPLY CHECK 09 eve II 2Vl369 NITROGEN FROM 2A CN-2605-01.05 / c ACT 3 2 CK SA c* OIC N/A eve II COLD LEG E-08 ACCUMULATOR SUPPLY CHECK cvo II 2Vl370 NITROGEN FROM 28 CN-2605-01.05 I F- c ACT 3 2 CK SA c OIC N/A eve II COLD LEG 08 ACCUMULATOR SUPPLY CHECK cvo II 2Vl373 NITROGEN FROM 2A CN-2605-01.05 / c ACT 3 1.5 RV SA c OIC N/A RV I COLD LEG E-08 ACCUMULATOR SUPPLY HEADER RELIEF 2Vl374 NITROGEN FROM 2B CN-2605-01.05 / c ACT 3 1.5 RV SA c OIC N/A RV I COLD LEG G-08 ACCUMULATOR SUPPLY HEADER RELIEF 2VP001B UPPER CONT PURGE CN-2576-01.00 /I- A PASS 2 24 BF AO c c c LTJ J SUPPLY OUTSIDE ISOL 5 2VP002A UPPER CONT PURGE CN-2576-01.00 /I- A PASS 2 24 BF AO c c c LTJ J SUPPLY INSIDE ISOL 6 2VP003B UPPER CONT PURGE CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J SUPPLY OUTSIDE ISOL H-5 2VP004A UPPER CONT PURGE CN-2576-01.00 /I- A PASS 2 24 BF AO c c c LTJ J SUPPLY INSIDE ISOL 6 2VP006B LOWER CONT PURGE CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J SUPPLY OUTSIDE ISOL G-5 2VP007A LOWER CONT PURGE CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J SUPPLY INSIDE ISOL G-6 2VP008B LOWER CONT PURGE CN-2576-01.00 IF- A PASS 2 24 BF AO c c c LTJ J SUPPLY OUTSIDE ISOL 5 ; 2VP009A LOWER CONT PURGE CN-2576-01.00 IF- A PASS *2 24 *BF AO c C* c LTJ J SUPPLY INSIDE ISOL 6 2VP010A

UPPER CONT PURGE CN-2576-01.00 / I- A PASS 2 24 BF AO c c c LTJ J

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Catawba 4Wterval Standa delSTC Catawba. Nu.dear Plant Interval 4 ;IST 1.0.6 Page 215 of 222 Valve Summary Listing Page 215 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2VP011B UPPER CONT PURGE CN-2576-01.00 /I- A PASS 2 24 BF AO c c c LTJ J EXHAUST OUTSIDE ISOL 10 2VP012A UPPER CONT PURGE CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J EXHAUST INSIDE ISOL H-9 2VP013B UPPER CONT PURGE CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J EXHAUST OUTSIDE ISOL H-10 2VP015A LOWER CONT PURGE CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J EXHAUST INSIDE ISOL G-9 2VP016B LOWER CONT PURGE CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J EXHAUST OUTSIDE ISOL ' G-10 2VP017A INCORE INST ROOM CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J PURGE SUPPLY INSIDE E-9 ISOL 2VP018B INCORE INST ROOM CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J PURGE SUPPLY OUTSIDE E-10 ISOL 2VP019A INCORE INST ROOM CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J PURGE EXHAUST INSIDE E-5 ISOL 2VP020B INCORE INST ROOM CN-2576-01.00 I A PASS 2 24 BF AO c c c LTJ J PURGE EXHAUST E-6 OUTSIDE ISOL 2VQ002A VQ FAN SUCT FROM CN-1585-01.00 /I- A ACT 2 4 DA MO c c FAI RPI 2Y CONT ISOL 02 LTJ J FSC Q ST-C Q 2VQ003B VQ FAN SUCT FROM CN-1585-01.00 I A ACT 2 4 GA MO c c FAI RPI 2Y CONT ISOL G-02 LTJ J FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 216 of 222 Valve Summary Listing Page 216 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2VQ015B CONT AIR ADD CONT CN-1585-01.00 /I- A ACT 2 4 GA MO c c FAI RPI 2Y ISOL 12 LTJ J FSC Q ST-C Q 2VQ016A CONT AIR ADDITION CN-1585-01.00/ A ACT 2 4 DA MO c c FAI RPI 2Y CONT ISOL K-12 LTJ J FSC Q ST-C Q 2VS054B VS CONT ISOL CN-1605-02.01 I A ACT 2 GA MO c c FAI RPI 2Y G-05 LTJ J FSC Q ST-C Q 2VS056 UNIT 2 CONT HEADER CN-1605-02.01 I AIC ACT 2 CK SA c c NIA BOO II CHECK G-03 eve II LTJ J 2VX001A 2A HYDROGEN SKIMMER CN-2557-01.00 I B ACT 2 12 BF MO c 0 FAI RPI 2Y FANINLETISOL G-03 FSO Q ST-0 Q 2VX002B 2B HYDROGEN SKIMMER CN-2557-01.00 I B ACT 2 12 BF . MO c 0 FAI RPI 2Y FAN INLET ISOL G-14 FSO Q ST-0 Q 2VY015B VY INLET BLOWER DISCH CN-2559-01.00 IF- A PASS 2 4 GA MO c c FAI RPI 2Y ISOL 07 LTJ J

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Catawba 4 1 terval Standa .ude ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 217 of 222 Valve Summary Listing Page 217 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2VY016 CONTAINMENT H2 CN-2559-01.00 I AIC ACT 2 4 CK SA OIC c N/A BOO II PURGE INLET BLOWER D-07 DISCH CHECK eve II LTJ J 2VY017A VY OUTLET CN-2559-01.00 I A PASS 2 4 GA MO c c FAI RPI 2Y CONTAINMENT ISOL D-04 LTJ J 2VY018B VY OUTLET CONT ISOL CN-2559-01.00 IF- A PASS 2 4 GA MO c c FAI RPI 2Y 04 LTJ J 2WE020 CONTAINMENT BUILDING CN-2568-01.00 I J- A PASS 2 1 GL MA c c N/A LTJ J SUPPLY OUTSIDE ISOL 8 2WE022 CONTAINMENT BUILDING CN-2568-01.00 I A PASS 2 1 GL MA c c N/A LTJ J SUPPLY INSIDE ISOL H-8 2WL321 INCORE INST SUMP CN-2565-02.04 / A/C ACT 2 0.75 CK SA OIC OIC N/A eve II PUMP DISCH TEST DRAIN H-06 CHECK cvo II LTJ J 2WL450A NCDTVENT CN-2565-02.00 /I- A ACT 2 0.75 GL MO 0 c FAI RPI 2Y CONTAINMENT ISOL 04 LTJ J FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 218 of 222 Valve Summary Listing Page 218 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2WL451B NCDT VENT CONT ISOL CN-2565-02.00 I J- A ACT 2 0.75 GL MO 0 c FAI RPI 2Y 04 LTJ J FSC Q ST-C Q 2WL462 NCDT RELIEF CN-2565-02.00 I c ACT NC 2 RV SA c OIC N/A RV I H-03 2WL805A REACTOR COOLANT CN-2565-02.00 /I- A ACT 2 3 GA MO 0 c FAI RPI 2Y DRAIN TANK PUMP 08 DISCH CONTAINMENT ISOL LT 2Y FSC Q ST-C Q 2WL806 REACTOR COOLANT CN-2565-02.00 /I- NC ACT 2 0.5 CK SA OIC OIC N/A eve II DRAIN TANK PUMP 08 DISCH CONTAINMENT ISOL BYPAS cvo II LTJ J 2WL807B NCDT PUMPS DISCH CN-2565-02.00 I J- A ACT 2 3 GA MO 0 c FAI RPI 2Y CONT ISOL 08 LT 2Y FSC Q ST-C Q

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Catawba 4~erval Standa Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 219 of 222 Valve Summary Listing Page 219 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2WL825A CONTAINMENT SUMP CN-2565-02.04 / A ACT 2 4 GA MO 0 c* FAI RPI 2Y PUMPS DISCH H-07 CONT Al NM ENT !SOL LT 2Y FSC a ST-C a 2WL826 INCORE INST/CONT AND CN-2565-02.04 / c ACT NC 0.75 RV SA c OIC N/A RV I EQUIP SUMP PUMPS H-10 DISCH RELIEF 2WL827B CONT SMP PMPS DISCH CN-2565-02.04 / J- A ACT 2 4 GA MO 0 c FAI RPI 2Y CONT ISOL 07 LT 2Y FSC a ST-C Q 2WL830 2CA TURBINE DRIVEN CN-2565-02.02 I c ACT 3 2 CK SA OIC OIC NIA eve II PUMP SUMP PUMP 2A D-08 DISCH CHECK cvo II 2WL832 2CA TURBINE DRIVEN CN-2565-02.02 / c ACT 3 2 CK SA OIC OIC N/A eve II PUMP SUMP PUMP 2B D-10 DISCH CHECK cvo II 2WL838 2A CA PUMP SUMP PUMP CN-2565-02.02 / c ACT 3 2 CK SA OIC OIC N/A eve II DISCH CHECK E-05 cvo II 2Wl840 2B CA PUMP SUMP PUMP CN-2565-02.02 I c ACT 3 2 CK SA OIC OIC NIA eve II DISCH CHECK D-06 cvo II

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 220 of 222 Valve Summary Listing Page 220 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2WL847 FLOOR DRAIN SUMP C CN-2565-02.02 I J- B ACT 3 4 PL AO c 0 0 FO Q DISCH TO ND I NS SUMP 10 FSO a 2WL848 FLOOR DRAIN SUMP C CN-2565-02.02 I J- B ACT 3 4 PL AO 0 c c FC a DISCH TO TURBINE 08 BUILDING SUMP FSC Q 2WL850 CA PUMP ROOM SUMP CN-2565-02.02 I c ACT 3 4 CK SA OIC 0 NIA BOC II DISCHARGE HEADER H-10 CHECK VALVE cvo II 2WL867A VUCDT CONTAINMENT CN-2565-02.01 / I- A ACT 2 4 GA MO 0 c FAI RPI 2Y ISOL 07 LT 2Y FSC a ST-C Q 2WL868 VUCDT CONTAINMENT CN-2565-02.01 /I- A/C ACT 2 1 CK SA O/C c NIA BOO II ISOL BYPASS CHECK 06 eve II LTJ J 2WL869B UNIT 2 VENT UNIT CN-2565-02.01 I A ACT 2 4 GA MO 0 c FAI RPI 2Y CONDENSATE DRAIN H-07 TANK CONTAINMENT ISOL LT 2Y FSC Q ST-C a

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Catawba 4l terval Standa 'ode ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 221 of 222 Valve Summary Listing Page 221 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2WL894 FLOOR DRAIN SUMP C CN-2565-02.02 / c ACT 3 2 CK SA O/C c N/A BOO II PUMPS DISCH CHECK E-09 eve II 2WLA21 SIG DRAIN PUMP DISCH CN-2565-02.06 / A PASS 2 3 GA MA c c NIA LT 2Y CONTAINMENT ISOL G-10 2WLA22 SIG DRAIN PUMP DISCH CN-2565-02.061 A/C ACT 2 0.75 CK SA OIC OIC NIA eve II CONTAINMENT ISOL H-10 CHECK cvo II LTJ J 2WLA24 UNIT 2 SIG DRAIN PUMP CN-2565-02.061 A PASS 2 3 GA MA c c NIA LT 2Y DISCH CONTAINMENT G-12 ISOL 2WLA33 SIG DRAIN PUMP DISCH CN-2565-02.061 c ACT NC 2 RV SA c OIC NIA RV I RELIEF H-07 2WN004 2A DIG ENG SUMP PUMP CN-2609-07.00 I J- c ACT 3 3 CK SA OIC 0 NIA BOC II 2A1 DISCH CHECK 6 cvo II 2WN006 2A DIG ENG SUMP PUMP CN-2609-07.00 I J- c ACT 3 3 CK SA OIC 0 NIA BOC II 2A2 DISCH CHECK 9 cvo II 2WN012 2B DIG ENG SUMP PUMP CN-2609-07.00 I c ACT 3 3 CK SA OIC 0 NIA BOC II 2B1 DISCH CHECK E-6 cvo II 2WN014 2B DIG ENG SUMP PUMP CN-2609-07.00 I c ACT 3 3 CK SA OIC 0 NIA BOC II 2B2 DISCH CHECK E-9 cvo II 2YM119B YM CONT ISOL CN-1601-03.011 A ACT 2 GL MO 0 c FAI RPI 2Y E-09 LTJ J FSC Q ST-C Q

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 222 of 222 Valve Summary Listing Page 222 of 222 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2YM121 YM HOR CONTAINMENT CN-1601-03.01 I A/C ACT 2 CK SA O/C c N/A BOO II ISOL CHECK E-11 eve II LTJ J

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Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 2 Valve Justifications Listing - Image Page 1 of 2 Justification for Deferral Item Number: CSJ-CN-88-01 Valve: 1888A, 188108, 1BB19A, 1BB21B, 1BB56A, 1BB57B, 1BB60A, 1BB61B 2BB8A, 2BB10B, 2BB19A, 2BB21B, 2BB56A, 2BB57B, 2BB60A, 2BB61 B Flow Diagram: CN-1580-01.00, CN-2580-01.00 Code Category: B ASME Class: 2 Function: The BB System operates continuously during most modes of unit operation, to control steam generator water chemistry and corrosion product buildup. This helps to control the corrosive attack on the steam generator materials .

Test Requirement:

Basis for Deferral: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Full stroke testing of these BB system valves results in a plant reactivity transient of an approximate 0.6 percent power increase. To establish test conditions during normal plant operation, reactor engineering and plant operators must develop and implement a reactivity plan. Several industry documents which are based on industry operating experience, risk insights, etc. contain recommendations and practices that tend to discourage plant elected reactivity changes. For example, WANO SOER 2007-1 states economic and scheduling concerns are secondary to reactor safety. WANO GL 2005-03 Attribute Ill provides precautions to control activities that could affect core reactivity such as procedure details describing amount/rate of reactivity changes, new procedures, as well as maintenance activities during work planning activities. Attribute VI describes adequate work management processes that establish proper priority and coordination of work on systems that affect reactivity control and monitoring. Regulatory Guide DG-1287 paragraph 1.1.3 'Reduce Unnecessary Burdens' discusses changes to surveillances that may lead to plant transients or place unnecessary administrative burdens on plant personnel that are not justified by the safety significance of the surveillance requirement. It adds that these

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 2 of 2 Valve Justifications Listing - Image Page 2 of 2 changes might allow an increased allocation of the plant personnel's time to more safety-significant aspects. In addition, paragraph 2.3.4 'Assumption in Completion Time and Surveillance Frequency Evaluations' refers to surveillance frequency evaluations should consider a certain assumption: Notwithstanding the beneficial aspects of testing to detect failures that occur in a standby period, a number of adverse effects may be associated with the test, including downtime to conduct the test, errors of restoration after the test, test-caused transients, and test-caused wear of the equipment. NUREG-1482 revision2 paragraph 2.4.5 also discusses the risk associated with quarterly testing may outweigh the benefits that might otherwise be achieved. Thus, it is appropriate for licensees to weigh the safety impact against the benefits of testing as a basis for deferring testing from a quarterly frequency to cold shutdown or refueling outages. In summary, failures of these valves in the closed position have a short duration impact on the overall SG chemistry index. However, these valves have exhibited exemplary performance. Reactivity management impacts when combined with potential SG health effects from Chemistry Index changes support a Cold Shutdown test

frequency ..

Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions.

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-CA-05 Valve: 2CA0149, 2CA0150, 2CA0151, 2CA0152 Flow Diagram: CN-2592-1.1 Code Category: B ASME Class: 2 Function: Close on Feedwater Isolation signal and Phase "A" Containment Isolation signal.

Test Requirement: Exercise Fail to Safe Position every three months. Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months .

Basis for Deferral: The Westinghouse D-5 steam generator design requires these valves to be used for a portion of the main Feedwater flow during power operation. Closing these valves at 100% power would isolate this flow, possibly resulting in preheater damage.

Test Alternative & Frequency: These valves will be: Exercise Fail to Safe Position at Cold Shutdown conditions. Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-CF-01 Valve: 1CF0033, 1CF0042, 1CF0051, 1CF0060 2CF0033, 2CF0042, 2CF0051 , 2CF0060 Flow Diagram: CN-1591-1.1 CN-2591-1.1 Code Category: B ASME Class: 2 Function: Isolates main feedwater piping from the steam generators upon receipt of a feedwater isolation signal.

Test Requirement: Exercise Fail to Safe Position every three months.

Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Basis for Deferral: Closing these valves during power operation is considered impractical from an operating viewpoint. Closure would isolate feedwater to the steam generator which may result in a severe transient in the steam generator, possibly causing a unit trip. Test Alternative & Frequency: These valves will be: Exercise Fail to Safe Position at Cold Shutdown conditions. Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-CF-04 Valve:. 1CF0028, 1CF0037, 1CF0046, 1CF0055 2CF0028, 2CF0037, 2CF0046, 2CF0055 Flow Diagram: CN-1591-1.1 CN-2591-1.1 Code* Category: B ASME Class: 3 Function: Control valves normally modulated by the Digital Feedwater Control System (DFCS) to maintain proper steam generator water level. Automatic closure will occur upon transfer to the auxiliary shutdown panel, an inboard doghouse Hi-Hi water level, or a feedwater isolation signal.

Test Requirement: Measure Full Stroke Time - Quarterly Exercise valve (full stroke) to the position required to fulfill its function every 3 months.

Basis for Deferral: Closing these valves during power operation is considered impractical from an operating viewpoint. Closure would reduce feedwater to the steam generators which may result in a severe transient in the steam generator, possibly causing a unit trip. Test Alternative & Valves will be exercised (full stroke) to the closed position and Frequency: stroke timed during cold shutdown.

Catawba 4th lnterv~I Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 2 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-CF-05 Valve: 1CF0030, 1CF0039, 1CF0048, 1CF0057 2CF0030, 2CF0039, 2CF0048, 2CF0057 Flow Diagram: CN-1591-1 .1 CN-2591-1 .1 Code Category: B ASME Class: ANSI B31.1 (Class F)

Function: Bypass control valves normally modulated by the Digital Feedwater Control System (DFCS) to maintain proper steam generator water level. Automatic closure will occur upon transfer to the auxiliary shutdown panel, an inboard doghouse Hi-Hi water level, or a feedwater isolation signal. Test Requirement: Exercise Fail to Safe Position every three months. Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Basis for Deferral: Closing these valves during power operation is considered impractical from an operating viewpoint. Closure would reduce feedwater to the steam generators which may result in a severe transient in the steam generator, possibly causing a unit trip. Test Alternative & Frequency: These valves will be: Exercise Fail to Safe Position at Cold Shutdown conditions. Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions. These valves are Augmented and the CSJ is entered for record keeping purposes only. ASME Code requirements do not apply to Augmented components. The components entered on the document will not be shown on the Standard ISTC valve table, but will be shown as part or the Augmented Test Program .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-KC-01 Valve: 1KC320A,1KC332B,1KC333A 2KC320A,2KC332B,2KC333A Flow Diagram: CN-1573-1.3 CN-2573-1.3 Code Category: B ASME Class: 2 Function: Isolates flow to the reactor coolant drain tank heat exchanger upon receipt of a high containment pressure signal. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Basis for Deferral: Failure of one of these valves in the closed position during testing would inhibit the flow path through the reactor coolant drain tank heat exchanger. This would result in boiling of the water in the reactor coolant drain tank resulting in excess heat in containment. This increased heat load could cause unit shutdown due to exceeding Tech Spec containment temperature limits. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Justification for Deferral Item Number: CSJ-CN-KC-02 Valve: 1KC0338B, 1KC0424B, 1KC0425A 2KC0338B, 2KC0424B, 2KC0425A Flow Diagram: CN-1573-1.3 CN-2573-1. 3 Code Category: B ASME Class: 2 Function: Isolates flow for the reactor vessel support coolers, reactor coolant pump motor bearing coolers, and reactor coolant pump thermal barriers, upon receipt of a high-high containment pressure signal. Test Requirement: Measure Full Stroke lime - Quarterly Exercise valve (full stroke) to the position required to fulfill its function and stroke time every 3 months. Basis for Deferral: Failure of these valves in the closed position during testing would inhibit flow to the reactor vessel support coolers, reactor coolant pump motor bearing coolers, and reactor coolant pump thermal barriers. This action could result in unit shutdown and possible damage to the vessel and reactor coolant pumps. Test Alternative & Valve will be exercised (full stroke) to the position required to fulfill its safety Frequency: function and stroke timed during cold shutdown.

Catawba 4th Interval Standard Code ISTC IST 1.0.6 Catawba Nuclear Plant Interval 4 Page 1 of 2 Valve Justifications Listing- Image Page 1 of 2 Justification for Deferral Item Number: CSJ-CN-NC-02 Valve: 1NC0032B, 1NC0034A, 1NC0036B 2NC0032B, 2NC0034A, 2NC0036B Flow Diagram: CN-1553-1.1 CN-2553-1.1 Code Category: B ASME Class: 1 Function: Reactor Coolant System PORV opens to relieve pressure for the primary system. Test Requirement: Exercise Fail to Safe Position every three months. Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Stroke time valve open every three months. Basis for Deferral: The PORVs are operated automatically or by remote manual control and perform several design basis functions requiring open and close operations including: NC System pressure control in the mitigation of a steam generator tube rupture (SGTR) accident, NC System pressure control (depressurization) during plant cooldown, reduction in challenges to the Pressurizer Safety Relief Valves for overpressurization events, low temperature overpressure protection of the reactor vessel during startup and shutdown, and aid in maintaining integrity of the RCPB (related to controlling identified leakage and ensuring the ability to detect unidentified RCPB leakage). With NC32B open and incapable of closing or closed and experiencing excessive seat leakage, the valve is declared inoperable. These valves have a safety related function in the closed position to in order to maintain the system pressure boundary. This normally closed valve is a Class 1 to non-Code boundary valve. Also according to NRG Branch Technical Position RSB5-2 the full stroke exercise should take place during cold shutdown vs. quarterly during power operations due to the high probability of sticking open. Technical Specifications prevents Catawba from performing the surveillance test in Modes 1 and 2.

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 2 of 2 Valve Justifications Listing - Image Page 2 of 2 Test Alternative & Frequency: These valves will be: Exercise Fail to Safe Position at Cold Shutdown conditions. Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions.

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-NC-03 Valve: 1NC0250A, 1NC0251 B, 1NC0252B, 1NC0253A 2NC0250A,2NC0251B,2NC0252B,2NC0253A Flow Diagram: CN-1553-1.1 CN-2553-1 .1 Code Category: B ASME Class: 1 Function: Reactor vessel head vent.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open and closed every three months. Basis for Deferral: Opening these valves at full pressure could cause damage to the valve seating surfaces. A reactor coolant leak could be caused. Test Alternative & Valve will be cycled and timed during cold shutdown. Frequency:

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-ND-01 Valve: 1ND0001 B, 1ND0002A 2ND0001B,2ND0002A Flow Diagram: CN-1561-1.0 CN-2561-1.0 Code Category: A ASME Class: 1 Function: Valves open to provide suction to Residual Heat Removal Pump A during normal unit cooldown.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months . Basis for Deferral: These valves have been provided with an interlock which prevents their opening when Reactor Coolant System pressure is above approximately 425 PSIG. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-ND-02 Valve: 1ND0036B,1 ND0037A 2ND0036B, 2ND0037A Flow Diagram: CN-1561-1.1 CN-2561-1.1 Code Category: A ASME Class: 1 Function: Valves open to provide suction to Residual Heat Removal Pump B during normal unit cooldown.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months . Basis for Deferral: These valves have been provided with an interlock which prevents their opening when Reactor Coolant System pressure is above approximately 425 PSIG. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-ND-04 Valve: 1ND0032A, 1ND0065B 2ND0032A, 2ND0065B Flow Diagram: CN-1561-1.0, CN-1561-1.1 CN-2561-1.0, CN-2561-1.1 Code Category: B ASME Class: 2 Function: Cross connect cold leg injection flow path from the two trains of residual heat removal. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months . Stroke time valve close every three months. Basis for Deferral: Based on Engineering and Westinghouse evaluation, closing one of these valves renders both trains of residual heat removal inoperable. This is not allowed by Technical Specification in Modes 1-3 since both trains are required to be operable. Technical Specification requires one of train of ND to be operable in Mode 4. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-ND-05 Valve: 1ND0028A 2ND0028A Flow Diagram: CN-1561-1.0 CN-2561-1.0 Code Category: B ASME Class: 2 Function: Residual Heat Removal pump supply to NV and NI pumps. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months. Stroke time valve close every three months . Basis for Deferral: Opening valve provides flow path from FWST to suction of centrifugal charging pumps. This could result in a plant transient due to an increase in RCS Boron inventory. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-Nl-01 Valve: 1NI0009A, 1NI001 OB 2NI0009A, 2NI001 OB Flow Diagram: CN-1562-1.0 CN-2562-1.0 Code Category: B ASME Class: 2 Function: Opens to allow flow from centrifugal charging pump discharge to reactor coolant loop cold leg. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months . Stroke time valve open every three months. Stroke time valve close every three months. Basis for Deferral: Exercising these valves quarterly during power operations would result in flow of non-preheated water through the injection lines and thermal shocking of the injection nozzles. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-Nl-08 Valve: 1NI0100B 2NI0100B Flow Diagram: CN-1562-1.2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Provides suction for both trains of safety injection pumps from the refueling water storage tank. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months . Stroke time valve close every three months. Basis for Deferral: Failure of this valve in the closed position during testing would render both trains of safety injection pumps inoperable. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-Nl-09 Valve: 1NI0147B 2NI0147B Flow Diagram: CN-1562-1.2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Valve is normally open to provide miniflow path to the refueling water storage tank.
Test Requirement:

Basis for Deferral: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months. Stroke time valve close every three months. Failure of this valve in the closed position during testing would result in loss of miniflow path for both trains of safety injection pumps. This would result in pump damage due to dead heading the safety injection pumps in the event of a safety injection signal with reactor coolant pressure above 1520 psig (Safety Injection Pump Discharge Pressure). Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-Nl-12 Valve: 1NI0162A 2NI0162A Flow Diagram: CN-1562-1 .3 CN-2562-1.3 Code Category: B ASME Class: 2 Function: Valve is normally open to provide cold leg injection flow from both trains of safety injection pumps.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months . Stroke time valve close every three months. Basis for Deferral: Failure of this valve in the closed position during testing would result in loss of cold leg injection flow from the safety injection pumps rendering both trains of safety injection inoperable. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-Nl-15 Valve: 1 NI0173A, 1 NI0178B 2NI0173A, 2NI0178B Flow Diagram: CN-1562-1.3 CN-2562-1.3 Code Category: B ASME Class: 2 Function: Each valve isolates two of the four cold leg injection flow paths from the residual heat removal discharge crossover line.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months . Stroke time valve close every three months. Basis for Deferral: Based on Engineering and Westinghouse evaluation, closing one of these valves renders both trains of residual heat removal inoperable. This is not allowed by Technical Specification in Modes 1-3 since both trains are required to be operable. Technical Specification requires one train of ND to be operable in Mode 4. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-Nl-16 Valve: 1NI0183B 2NI0183B Flow Diagram: CN-1562-1.2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Opens to align hot leg injection during recirculation phase following safety injection actuation. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months . Stroke time valve close every three months. Basis for Deferral: Based on Engineering and Westinghouse evaluation, in order for a train of ND to be operable to perform its ECCS function, it must be able to discharge into all four cold leg injection lines. This is in the event of single train failure. With this additional valve open, one ND pump could then be aligned to all four cold leg injection paths plus two hot leg paths during an ECCS actuation. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-Nl-17 Valve: 1NI01848, 1NI0185A 2NI01848, 2NI0185A Flow Diagram: CN-1562-1.3 CN-2562-1.3 Code Category: B ASME Class: 2 Function: Opens to provide flow from the Containment Sump to the suction of Residual Heat Removal and Containment Spray Pumps during post accident recirculation phase.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months . Stroke time valve open every three months. Stroke time valve close every three months. Basis for Deferral: To prevent water from entering lower containment when cycling I these valves, piping downstream must be drained. This results in making one train of ECCS inoperable for an extended period of time until completion of the test, refilling the piping and realignment of isolation valves. Also, the large amount of potentially contaminated water that must be drained is a major Health Physics and Radwaste Chemistry problem. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-Nl-18 Valve: 1NI0332A, 1 NI0333B 2NI0332A, 2NI0333B Flow Diagram: CN-1562-1 .2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Aligns discharge of ND Pump 1A to suction of NI and NV Pumps. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months. Stroke time valve close every three months . Basis for Deferral: If one of these valves were to fail in the open position during testing, the FWST would be aligned to the suction of the charging pumps. This could result in an increase in RCS Boron inventory and could result in plant shutdown. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-Nl-19 Valve: 1NI0136B 2NI0136B Flow Diagram: CN-1562-1.2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Valve is opened for the recirculation phase of ECCS operation to allow flow from the residual heat removal pumps to the safety injection pumps.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months . Stroke time valve open every three months. Stroke time valve close every three months. Basis for Deferral: Based on Engineering evaluation, opening this valve during power operation could degrade ND system flow in the event of a Large Break LOCA. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-Nl-21 Valve: 1NI0121 A, 1NI0152B 2NI0121 A, 2NI0152B Flow Diagram: CN-1562-1.2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Valves 1(2)NI0121 A and 1(2)NI0152B are motor operated gate valves on the discharge side of NI Pump A and B to NC Loops B&C and A&D, respectively. The valves are normally closed during the injection phase and cold leg recirculation phases of ECCS operation to prevent diversion of flow via the NC hot legs.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months. Stroke time valve close every three months. Basis for Deferral: Exercising the valves in modes 1-3 can result in challenging NI pump discharge relief valves and overpressurization of NI piping due to reactor coolant leakage pressurizing piping downstream. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-Nl-22 Valve: 1NI0144A, 2NI0144A Flow Diagram: CN-1562-1.2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Valves NI0144A are motor operated valves on the NI Pump B miniflow line. The valves are open during the injection mode when the NI Pumps are operating. During the recirculation mode, when the NI Pumps are taking suction from the containment sump (via the ND System), the valves are closed to isolate the miniflow line. Closure of the valves prevents the possibility of introducing reactor coolant water into the FWST and diversion of flow from the NC System. The valves are also interlocked with valves ND0028A & NI0136B such that they can not be opened unless valves ND0028A and NI0136B are closed.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months. Stroke time valve close every three months. Basis for Deferral: If NI0144A was closed for testing and of a loss of offsite power with the loss of Train A diesel generator as the single failure occurred, the valve could not be reopened which would result in a loss of both NI pumps. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-Nl-23 Valve: 1 NI0334B, 2NI0334B Flow Diagram: CN-1562-1.2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Provides flowpath from B Train of Residual Heat Removal to B Train of Chemical and Volume Control, and from A Train of Residual Heat Removal to A Train of Safety Injection. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months . Stroke time valve close every three months. Basis for Deferral: Closing this valve during power operation degrades both trains of Safety Injection. With the single failure of Train B diesel generator, Train A of Safety Injection, which is provided suction from Residual Heat Removal via NI0334B or NI0136B, would be inoperable (since NI0136B is normally closed). Train B of Safety Injection would already be inoperable due to the single failure. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CN-Nl-24 Valve: 1NI0103A, 2NI0103A Flow Diagram: CN-1562-1.2 CN-2562-1.2 Code Category: B ASME Class: 2 Function: Provides flow from the Refueling Water Storage Tank to the A Train Safety Injection Pump suction. This valve also provides a flow path from the B Train Residual Heat Removal Pump to the A Train Safety Injection Pump and both Centrifugal Charging Pumps .

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve open every three months.

                         , Stroke time valve close every three months.

Basis for Deferral: Closing this valve during power operations degrades both trains of the Chemical and Volume Control System. In the event of a loss of offsite power with the loss of the Train A Diesel Generator as the single failure when the valve was closed, B Train NV would be lost for sump recirculation mode of operation. Train A NV would already be inoperable due to the single failure. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-NS-03 Valve: 1NS0038B, 1NS0043A 2NS0038B, 2NS0043A Flow Diagram: CN-1563-1.0 CN-2563-1.0 Code Category: B ASME Class: 2 Function: Residual Heat Pump A (and B) to Containment Spray Header Containment Isolation Valve.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months . Basis for Deferral: If an accident occurred with one of these valves open, injection flow would be diverted from both trains of the ND System. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-NV-01 Valve: 1NV0015B 2NV0015B fJ Flow Diagram: CN-1554-1.0 CN-2554-1.0 Code Category: A ASME Class: 2 Function: Valves closes to isolate flow to the letdown heat exchanger.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months .

Basis for Deferral:

Test Alternative & Failure of this valve in the closed position during testing would result in loss of pressurizer level control and could result in plant shutdown. Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: CSJ-CN-NV-02 Valve: 1NV0089A, 1NV0091B 2NV0089A,2NV0091B Flow Diagram: CN-1554-1.0 CN-2554-1.0 Code Category: B ASME Class: 2 Function: These valves isolate the return flow path from the reactor coolant pump seal water supply.

Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months . Basis for Deferral: Closure of one of these valves during power operation would increase backpressure on the seals, reducing leakoff flow and lifting relief valve 1(2)NV0087 to divert leakoff to the PRT. Damage to RCP seals could result. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN~NV-03 Valve: 1NV0188A, 1NV0189B 2NV0188A,2NV0189B Flow Diagram: CN-1554-1 .1 CN-2554-1.1 Code Category: B ASME Class: 2 Function: Valves close to isolate the volume control tank (normal charging supply) upon receipt of a safety injection signal. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months . Basis for Deferral: Closure of one of these valves during normal unit operation would isolate the normal suction for the charging pumps. Alternate suction paths would result in increasing the reactor coolant system boron inventory and could result in plant shutdown. In addition, seal water for the reactor coolant pumps would be inhibited. This may result in damage to the reactor coolant pump seals. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-NV-04 Valve: 1NV0312A, 1NV0314B 2NV0312A, 2NV0314B Flow Diagram: CN-1554-1 .2 CN-2554-1.2 Code Category: B ASME Class: 2 Function: Valves close to isolate the charging line to the Reactor Coolant System upon receipt of a safety injection signal. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Basis for Deferral: Closure of one of these valves during power operation would isolate charging flow to the Reactor Coolant System. This could result in loss of pressurizer level control and cause plant shutdown. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number.: CSJ-CN-NV-10 Valve: 1NV0252A, 1NV0253B 2NV0252A,2NV0253B Flow Diagram: CN-1554-1.7 CN-2554-1. 7 Code Category: B ASME Class: 2 Function: Aligns refueling water storage tank (FWST) to the suction of the centrifugal charging pumps upon receipt of a safety injection signal. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its

Basis for Deferral:

function every three months . Stroke time valve open every three months. Stroke time valve close every three months. If one of these valves were to fail in the open position during testing, the FWST would be aligned to the suction of the charging pumps. This would result in an increase in RCS Boron inventory and could result in a plant shutdown. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve open at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 2 Valve Justifications Listing - Image Page 1 of 2 Justification for Deferral Item Number: CSJ-CN-NV-11 Valve: 1NV001 OA, 1NV0011 A, 1NV0013A 2NV0010A,2NV0011A,2NV0013A Flow Diagram: CN-1554-1.0 CN-2554-1.0 Code Category: B ASME Class: 2 Function: These valves must automatically close to isolate containment upon receipt of a Pressurizer Low Level signal, if either valve 1(2)NV0001 A or 1(2)NV0002A closes, upon receipt of a Phase A Containment Isolation Signal (ST), or on a concurrent failure of the PD pump and both centrifugal charging pumps. These valves are cross-interlocked with valves 1(2)NV0001 A and 1(2)NV0002A such that they will automatically close if either 1(2)NV0001 A or 1(2)NV0002A is not in the "Open" position. These valves can be operated from the Auxiliary Shutdown Panel, and cannot be opened unless valves 1(2)NV0001A and 1(2)NV0002A are both open. Test Requirement: Exercise Fail to Safe Position every three months. Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Basis for Deferral: Letdown header relief valve 1(2)NV0014 has experienced lifting and subsequent seat leakage as a result of pressure transients during orifice swaps for stroke time testing of valves 1(2)NV001 OA, 1(2)NV0011 A, and 1(2)NV0013A. Leakage past 1(2)NV0014 is considered Reactor Coolant (NC) system leakage. This leakage directly impacts Technical Specification. Based on the above, testing of these valves is impractical and non-conservative during power operation. Test Alternative & Frequency: These valves will be:

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 2 of 2 Valve Justifications Listing - Image Page 2 of 2 Exercise Fail to Safe Position at Cold Shutdown conditions. Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions.

Justification for Deferral Item Number: CSJ-CN-NV-12 Valve: 1NV0001A, 1NV0002A 2NV0001A, 1NV0002A Flow Diagram: CN-1554-1.0 CN-2554-1.0 Code Category: B ASME Class: 1 Function: Valves closes to isolate flow to the letdown heat exchanger on a Pressurizer low level signal. Test Requirement: Exercise Fail to Safe Position every three months. Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Basis for Deferral: Failure of this valve in the closed position during testing would result in loss of pressurizer level control and could result in plant shutdown. Failure of a letdown valve in the closed position coincident with normal charging flow could also result in a high RCS water level trip. Test Alternative & Frequency: These valves will be: Exercise Fail to Safe Position at Cond Shutdown conditions. Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CN-RF-02 Valve: 1RF0389B,1 RF0447B 2RF0389B,2RF0447B Flow Diagram: CN-1599-2.2 CN-2599-2.2 Category: A ASME Class: 2 Function: Opens to allow Fire Protection (RF) System supply to the containment fire suppression headers. Closes to provide containment isolation .

Test Requirement:

Basis for Def erral: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Opening these valves during power operations could introduce water into normally dry headers. Containment entry at power is required to drain the headers. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-RN-02 Valve: 1RN0437B 2RN0437B Flow Diagram: CN-1574-2.8 CN-2574-2.2 Code Category: B ASME Class: 2 Function: This valve closes on a high-high containment pressure signal to isolate the supply header to lower containment. Test Requirement: Exercise valve (full stroke) to the position required to fulfill its function every three months. Stroke time valve close every three months. Basis for Deferral: Failure of this valve in the closed position during testing would result in loss of nuclear service water flow to the reactor coolant pump motor coolers. This would result in unit shutdown and possible damage to the reactor coolant pumps. Test Alternative & Frequency: These valves will be: Exercise valve (full stroke) to the position required to fulfill its function at Cold Shutdown conditions. Stroke time valve close at Cold Shutdown conditions .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing- Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-RN-03 Valve: 1RN0484A, 1RN04878 2RN0484A, 2RN0487B Flow Diagram: CN-1574-2.2 CN2574-2.1, CN-2574-2.2 Code Category: B ASME Class: 2 Function: Valves close on a high-high containment pressure signal to isolate the lower containment return header. Test Requirement: Measure Full Stroke Time - Quarterly Exercise valves (full stroke) to the position required to fulfill its function and stroke time every 3 months . Basis for Deferral: Failure of one of these valves in the closed position during testing would result in loss of nuclear service water flow to the reactor coolant pump motor coolers. This would result in unit shutdown and possible damage to the reactor coolant pumps. Test Alternative & Valve will be exercised (full stroke) to the position required to fulfill Frequency: its function and stroke timed during cold shutdown.

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-VI-02 Valve: 1VI0077B 2VI0077B Flow Diagram: CN-1605-1.4 CN-2605-1.5 Code Category: A ASMEClass: 2 Function: Provides containment isolation. Closes upon receipt of a containment high-high pressure signal. Test Requirement: Measure Full Stroke Time - Quarterly Exercise valve (full stroke) to the position required to fulfill its function and stroke time every 3 months . Basis for Deferral: Failure of this valve in the closed position during testing would result in loss of instrument air supply to valves and controls within containment. This would result in loss of normal reactor coolant letdown, containment ventilation unit controls, normal air supply to the power operated relief valves, etc., thereby possibly causing unit shutdown. Test Alternative & Frequency: Valve will be exercised (full stroke) to the position required to fulfill its function and stroke timed during cold shutdown. Leak rate performance testing will be performed at refueling .

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CN-NV-07 Valve: INV0202B, INV0203A 2NV0202B, 2NV0203A Flow Diagram: CN-1554-1.6 CN-2554-1.6 Code Category: B ASMEClass: 2 Function: Valves can be closed to isolate the centrifugal charging pump miniflow line during cold leg injection phase following a LOCA. Test Requirement: Measure Full Stroke Time - Quarterly Exercise valve (full stroke) to the position required to fulfill its function and stroke time every 3 months. Basis for Deferral: Failure of one of these valves in the closed position during test would isolate the centrifugal charging pumps miniflow line. This path must remain open in the event of a LOCA until the operator verifies a primary side break at which time the valves are closed. In the event of a secondary side break, the minifiow path must remain open in order to prevent possible dead heading and damaging the centrifugal charging pumps. Test Alternative & Valve will be exercised (full stroke) to the position required to fulfill its Frequency: function and stroke timed during cold shutdown.

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Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 1 of 1 Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Item Number: CSJ-CN-SM-01 Valve: 1SM0001, 1SM0003, 1SM0005, 1SM0007 2SM0001, 2SM0003, 2SM0005, 2SM0007 Flow Diagram: CN-1593-1.0 CN-2593-1.0 Code Category: B ASME Class: 2 Function: Main steam isolation valves. Test Requirement: Measure Full Stroke Time/Failed to Safe Position - Quarterly Exercise valve (full stroke) to the position required to fulfill its function, stroke time, and verify fail safe actuation every 3 months. Basis for Deferral: Closure of these valves during power operation could introduce a severe transient in the main steam lines which could cause a unit trip. Test Alternative & : Valves will be exercised (full stroke) to the position required to fulfill Frequency its function, stroke timed, and fail safe actuation verified during startup after cold shutdown.

Catawba 4th Interval Standard Code ISTC Catawba Nuclear Plant Interval 4 IST 1.0.6

Valve Justifications Listing - Image Page 1 of 1 Justification for Deferral Page 1 of 1 Item Number: ROJ-CN-Nl-25 Valve: IN10054A, INI0065B, 1NI0076A, 1NI0088B 2NI0054A, 2NI0065B, 2NI0076A, 2NI0088B Flow Diagram: CN-1562-1.1 CN-2562-1 .1 Code Category: B ASME Class: 2
- Function:

Test Requirement: Valve is administratively open with power removed during normal operation. Some accidents require closure of these valves to prevent injecting nitrogen into the NC System. Measure Full Stroke Time - Quarterly Exercise valve full stroke to the position required to fulfill its function and stroke time every three months. Basis for Deferral: Valves cannot be full or partial stroke exercised during power operations since closure of any of the four valves violates TS 3.5.1. Test Alternative & These valves will be exercised (Open/Closed) to the position Frequency: required to fulfill their safety function during refueling.

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                                                                                                                      . IST 1.0.6 Page 1 of 2 Pump Summary Listing Page 1 of 2 PUMP ID               FUNCTION       DRAWING/COOR GROUP   CLASS     TYPE       FIXED ACTUAL TEST FREQ PROCEDURE         NOTES ORVAR. SPEED  REQ 1NVPUSB    STANDBY MAKEUP PUMP        CN-1554-01.08 Aug-B   NC     Positive    Fixed  GE600   dP  2Y Displacement Q   2Y

Catawba 4th Interval Augmented Pumps Catawba Nuclear Plant Interval 4 IST 1.0.6 Page 2 of 2 Pump Summary Listing Page 2 of 2 PUMP ID FUNCTION DRAWING/COOR GROUP CLASS TYPE FIXED ACTUAL TEST FREQ PROCEDURE NOTES OR VAR. SPEED REQ 2NVPUSB STANDBY MAKEUP PUMP CN-2554-01.08 Aug-8 NC Positive Fixed GE600 dP 2Y Displacement Q 2Y

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Catawba 4th Interval Catawba Nuclear Plant Interval 4

Augmented Valves IST 1.0.6 Page 1 of 10 Valve Summary Listing Page 1 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CACK0360 CA PUMP #1 (TD) FLOW CN-1499-CA.10-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 1D SIG I CHECK VALVE #1 cvo 18M 1CACK0361 CA PUMP #1 (TD) FLOW CN-1499-CA.10-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 1D SIG I CHECK VALVE #2 cvo 18M 1CACK0400 18 CA PUMP (MD) FLOW CN-1499-CA.07-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 1D SIG I CHECK VALVE #1 cvo 18M 1CACK0401 18 CA PUMP (MD) FLOW CN-1499-CA.07-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 1D SIG I CHECK VALVE #2 cvo 18M 1CACK0440 18 CA PUMP (MD) FLOW CN-1499-CA.07-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 1C SIG I CHECK VALVE #1 cvo 18M 1CACK0441 18 CA PUMP (MD) FLOW CN-1499-CA.07-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 1C SIG I CHECK VALVE #2 cvo 18M 1CACK0480 CA PUMP #1 (TD) FLOW CN-1499-CA.10-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 1C SIG I CHECK VALVE #1 cvo 18M

Catawba 4th Interval Catawba Nuclear Plant Interval 4

Augmented Valves IST 1.0.6 Page 2 of 10 Valve Summary Listing Page 2 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CACK0481 CA PUMP #1 (TD) FLOW CN-1499-CA.10-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 1C SIG I CHECK VALVE #2 cvo 18M 1CACK0520 CA PUMP #1 (TD) FLOW CN-1499-CA.10-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 18 S/G I CHECK VALVE #1 cvo 18M 1CACK0521 CA PUMP #1 (TD) FLOW CN-1499-CA.10-00 Aug-C ACT 3 0.5 CK SA OIC O/C N/A eve 18M CONTROL TO 18 S/G I CHECK VALVE #2 cvo 18M 1CACK0560 CA (MD) FLOW CONTROL CN-1499-CA.07-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M TO 18 S/G CHECK VALVE I

          #1 cvo  18M 1CACK0561  CA (MD) FLOW CONTROL CN-1499-CA.07-00 Aug-C   ACT   3     0.5  CK    SA    O/C   O/C     N/A  eve  18M TO 18 S/G CHECK VALVE         I
          #2 cvo  18M 1CACK0600  CA (MD) FLOW CONTROL CN-1499-CA.07-00 Aug-C   ACT   3     0.5  CK    SA    O/C   O/C     N/A  eve  18M TO 1A S/G CHECK VALVE         I
          #1 cvo  18M 1CACK0601  CA (MD) FLOW CONTROL CN-1499-CA.07-00 Aug-C   ACT   3     0.5  CK    SA    O/C   O/C     N/A  eve  18M TO 1A S/G CHECK #2            I cvo  18M 1CACK0640  CA PUMP #1 (TD) FLOW  CN-1499-CA.10-00 Aug-C  ACT   3     0.5  CK    SA    O/C   O/C     N/A  eve  18M CONTROL TO 1A S/G             I CHECK VALVE #1 cvo  18M

Catawba 4th Interval Catawba Nuclear Plant Interval 4

Augmented Valves IST 1.0.6 Page 3 of 10 Valve Summary Listing Page 3 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1CACK0641 CA PUMP #1 (TD) FLOW CN-1499-CA.10-00 Aug-C ACT 3 O.S CK SA OIC O/C N/A eve 18M CONTROL TO 1A S/G I CHECK VALVE #2 cvo 18M 1CACK1740 RC TO CA SUCTION -AIR CN-1499-CA.16-00 Aug-C ACT NC O.S CK SA O/C O/C N/A eve 18M SUPPLY CHECK VALVE I cvo 18M 1LD002 1A D/G ENG DRIVEN CN-1609-02.00 IF- Aug-C ACT NC 1.S RV SA c O/C N/A RV 10Y LUBE OIL PUMP SUCTION 9 RELIEF 1LD032 1B D/G ENG DRIVEN CN-1609-02.02 / F- Aug-C ACT NC 1.S RV SA c O/C N/A RV 10Y LUBE OIL PUMP SUCTION 9 RELIEF 1NV234 BORIC ACID TO CN-1SS4-01.07 I Aug-C ACT 2 2 CK SA O/C O/C N/A cvo 18M CHARGING PUMP CHECK G-12 DA SY 1NV423 1A BORIC ACID CN-1SS4-01.04 / F- Aug-C ACT 3 CK SA O/C O/C N/A cvo 18M TRANSFER PUMP DISCH 09 CHECK DA SY 1NV439 1B BORIC ACID CN-1SS4-01.04 / Aug-C ACT 3 CK SA O/C O/C N/A cvo 18M TRANSFER PUMP DISCH C-09 CHECK DA SY 1SM18S 1SM1 ACCUMULATOR CN-1S93-01.08 / J- Aug-C ACT 3 0.7S CK SA O/C O/C N/A eve CM AIR SUPPLY CHECK OS cvo CM 1SM189 1SM1 ACCUMULATOR CN-1S93-01.08 / J- Aug-C ACT 3 0.7S RV SA c O/C N/A RV 10Y RELIEF OS 1SM193 1SM3 ACCUMULATOR CN-1 S93-01.08 / Aug-C ACT 3 0.7S CK SA O/C O/C N/A eve CM AIR SUPPLY CHECK E-OS cvo CM 1SM197 1SM3 ACCUMULATOR CN-1S93-01.08 / Aug-C ACT 3 0.7S RV SA c O/C N/A RV 10Y RELIEF E-OS

Catawba 4th Interval Catawba Nuclear Plant Interval 4

Augmented Valves IST 1.0.6 Page 4 of 10 Valve Summary Listing Page 4 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1SM201 1SM5 ACCUMULATOR CN-1593-01.08 / Aug-C ACT 3 0.75 CK SA O/C O/C N/A eve CM AIR SUPPLY CHECK E-12 cvo CM 1SM205 1SM5 ACCUMULATOR CN-1593-01.08 I Aug-C ACT 3 0.75 RV SA c O/C N/A RV 10Y RELIEF E-12 1SM209 1SM7 ACCUMULATOR CN-1593-01.08 / J- Aug-C ACT 3 0.75 CK SA O/C O/C N/A eve CM AIR SUPPLY CHECK 12 cvo CM 1SM213 1SM7 ACCUMULATOR CN-1593-01.08 / J- Aug-C ACT 3 0.75 RV SA c O/C N/A RV 10Y RELIEF 12 1VA028B 1A AUX BLDG FILTER CN-1577-1.2 / J-3 Aug-B ACT NC 6 BF MO c O/C FAI FSC 2Y UNIT (ABFU-1A)

MINIFLOW INLET FSO 2Y RPI 2Y 1VA029A 1A AUX BLDG FILTER CN-1577-1.2 / H-4 Aug-B ACT NC 6 BF MO c 0 FAI FSO 2Y UNIT (ABFU-1A) MINIFLOW OUTLET RPI 2Y 1VA030B 1B AUX BLDG FILTER CN-1577-1.2 / H-5 Aug-B ACT NC 6 BF MO c 0 FAI FSO 2Y UNIT (ABFU-16) MINI FLOW OUTLET RPI 2Y 1VA031A 1B AUX BLDG FILTER CN-1577-1.2 /Jes Aug-B ACT NC 6 BF MO c O/C FAI FSC 2Y UNIT (ABFU-1B) MINIFLOW INLET FSO 2Y RPI 2Y

Catawba 4th Interval Catawba Nuclear Plant Interval 4

Augmented Valves IST 1.0.6 Page 5 of 10 Valve Summary Listing Page 5 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 1VE004 1AVS-D-4 (VE FAN 1A CN1564-01.00 I G- Aug-B ACT NC BF MO c 0 FAI FSO 2Y MINIFLOW DAMPER) 8 (1VE-4)

RPI 2Y 1VE009 1AVS-D-9 (VE FAN 1B CN1564-01.00 I G- Aug-B ACT NC BF MO c 0 FAI FSO 2Y MINIFLOW DAMPER) 8 (1VE-9) RPI 2Y

Catawba 4th Interval Catawba Nuclear Plant Interval 4

Augmented Valves IST 1.0.6 Page 6 of 10 Valve Summary Listing Page 6 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CACK0360 CA PUMP #2 (TD) FLOW CN-2499-CA.10-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 2D SIG I CHECK VALVE #1 cvo 18M 2CACK0361 CA PUMP #2 (TD) FLOW CN-2499-CA.10-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 2D SIG I CHECK VALVE #2 cvo 18M 2CACK0400 28 CA PUMP (MD) FLOW CN-2499-CA.07-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 2D SIG I CHECK VALVE #1 cvo 18M 2CACK0401 28 CA PUMP (MD) FLOW CN-2499-CA.07-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 2D SIG I CHECK VALVE #2 cvo 18M 2CACK0440 28 CA PUMP (MD) FLOW CN-2499-CA.07-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 2C SIG I CHECK VALVE #1 cvo 18M 2CACK0441 28 CA PUMP (MD) FLOW CN-2499-CA.07-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 2C SIG I CHECK VALVE #2 cvo 18M 2CACK0480 CA PUMP #2 {TD) FLOW CN-2499-CA.10-00 Aug-C ACT 3 0.5 CK SA OIC OIC NIA eve 18M CONTROL TO 2C SIG I CHECK VALVE #1 cvo 18M

Catawba 4th Interval Catawba Nuclear Plant Interval 4

Augmented Valves IST 1.0.6 Page 7 of 10 Valve Summary Listing Page 7 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CACK0481 CA PUMP #2 (TD) FLOW CN-2499-CA.10-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 2C SIG I CHECK VALVE #2 cvo 18M 2CACK0520 CA PUMP #2 (TD) FLOW CN-2499-CA.10-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 2B S/G I CHECK VALVE #1 cvo 18M 2CACK0521 CA PUMP #2 (TD) FLOW CN-2499-CA.10-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 2B S/G I CHECK VALVE #2 cvo 18M 2CACK0560 CA PUMP (MD) FLOW CN-2499-CA.07-00 Aug-C ACT 3 0.5 CK SA O/C O/C NIA eve 18M CONTROL TO 2B S/G I CHECK VALVE #1 cvo 18M 2CACK0561 CA PUMP (MD) FLOW CN-2499-CA.07-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 2B S/G I CHECK VALVE #2 cvo 18M 2CACK0600 CA PUMP (MD) FLOW CN-2499-CA.07-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 2A S/G I CHECK VALVE #1 cvo 18M 2CACK0601 CA PUMP (MD) FLOW CN-2499-CA.07-00 Aug-C ACT 3 0.5 CK SA O/C O/C N/A eve 18M CONTROL TO 2A S/G I CHECK VALVE #2 cvo 18M

Catawba 4th Interval Catawba Nuclear Plant Interval 4

Augmented Valves IST 1.0.6 Page 8 of 10 Valve Summary Listing Page 8 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2CACK0640 CAPT #2. (TD) FLOW CN-2499-CA.10-00 Aug-C ACT 3 O.S CK SA O/C O/C N/A eve 18M CONTROL TO 2A S/G I CHECK VALVE #1 cvo 18M 2CACK0641 CAPT #2. {TD) FLOW CN-2499-CA.07-00 Aug-C ACT 3 O.S CK SA O/C O/C N/A eve 18M CONTROL TO 2A S/G I CHECK VALVE #2.

cvo 18M 2CACK1740 RC TO CA SUCTION -AIR CN-2499-CA.16-00 Aug-C ACT NC O.S CK SA O/C O/C N/A eve 18M SUPPLY CHECK VALVE I cvo 18M 2LD002 2A D/A ENG DRIVEN CN-2609-02.00 I F- Aug-C ACT NC 1.S RV SA c O/C N/A RV 10Y LUBE OIL PUMP SUCTION 9 RELIEF 2LD032 2B DIG ENG DRIVEN CN-2609-02.02 I F- Aug-C ACT NC 1.S RV SA c O/C N/A RV 10Y LUBE OIL PUMP SUCTION 9 RELIEF 2NV234 BORIC ACID TO NV PUMP CN-2SS4-01.07 I Aug-C ACT 2 2 CK SA O/C O/C N/A cvo 18M CHECK G-12 DA SY 2NV423 2A BORIC ACID CN-2SS4-01.04 / F- Aug-C ACT 3 CK SA O/C O/C N/A cvo 18M TRANSFER PUMP DISCH 09 CHECK DA SY 2NV439 2B BORIC ACID CN-2SS4-01.04 / Aug-C ACT 3 CK SA O/C O/C N/A cvo 18M TRANSFER PUMP DISCH C-09 CHECK DA SY 2SM18S 2SM1 ACCUMULATOR CN-2S93-01.08 / J- Aug-C ACT 3 CK SA O/C O/C N/A eve CM AIR SUPPLY CHECK OS cvo CM 2SM189 2SM1 ACCUMULATOR CN-2S93-01.08 / J- Aug-C ACT 3 RV SA c O/C N/A RV 10Y RELIEF OS

Catawba 4th Interval Catawba Nuclear Plant Interval 4

Augmented Valves IST 1.0.6 Page 9 of 10 Valve Summary Listing Page 9 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2SM193 2SM3 ACCUMULATOR CN-2593-01.08 / Aug-C ACT 3 0.75 CK SA O/C O/C N/A eve CM AIR SUPPLY CHECK E-05 cvo CM 2SM197 2SM3 ACCUMULATOR CN-2593-01.08 I Aug-C ACT 3 0.75 RV SA c O/C N/A RV 10Y RELIEF E-05 2SM201 2SM5 ACCUMULATOR CN-2593-01.08 I Aug-C ACT 3 0.75 CK SA O/C O/C N/A eve CM AIR SUPPLY CHECK E-12 cvo CM 2SM205 2SM5 ACCUMULATOR CN-2593-01.08 I Aug-C ACT 3 0.75 RV SA c O/C N/A RV 10Y RELIEF E-12 2SM209 2SM7 ACCUMULATOR CN-2593-01.08 / J- Aug-C ACT 3 CK SA O/C O/C N/A eve CM AIR SUPPLY CHECK 12 cvo CM 2SM213 2SM7 ACCUMULATOR CN-2593-01.08 I J- Aug-C ACT 3 RV SA c O/C N/A RV 10Y RELIEF 13 2VA028B 2A AUX BLDG FILTER CN-1577-1.2/ J-12 Aug-B ACT NC 6 BF MO c O/C FAI FSC 2Y UNIT (ABFU-2A)

MINIFLOW INLET FSO 2Y RPI 2Y 2VA029A 2AAUX BLDG FILTER CN-1577-1.2 / H- Aug-B ACT NC 6 BF MO c 0 FAI FSO 2Y UNIT (ABFU-2A) 11 MINIFLOW OUTLET RPI 2Y 2VA030B 2B AUX BLDG FILTER CN-1577-1.2 / H- Aug-B ACT NC 6 BF MO c 0 FAI FSO 2Y UNIT (ABFU-2B) 11 MINIFLOW OUTLET RPI 2Y

Catawba 4th Interval

Catawba Nuclear Plant Interval 4
Augmented Valves IST 1.0.6 Page 10 of 10 Valve Summary Listing Page 10 of 10 VALVE ID FUNCTION DRAWING/COOR CAT ACT/ CLASS SIZE TYPE ACT POSITION TEST FREQ PROCEDURE NOTES PASS REQ NORM SAFE FAIL 2VA031A 2B AUX BLDG FILTER CN-1577-1.2/ J-10 Aug-B ACT NC 6 BF MO c O/C FAI FSC 2Y UNIT (ABFU-2B)

MINIFLOW INLET FSO 2Y RPI 2Y 2VE004 2VE-4 (VE FAN 2A CN-2564-01.00- Aug-B ACT NC BF MO c 0 FAI FSO 2Y MINIFLOW ISOL) (2AVS-D- 010 I G-8 4) RPI 2Y 2VE009 2VE-9 (VE FAN 2B CN-2564-01.00- Aug-B ACT NC BF MO c 0 FAI FSO 2Y MINIFLOW ISOL) (2AVS-D- 010 I G-8 9) RPI 2Y}}

CNS-16-067, ASME OM Code In-Service Testing Program Document

Contents

Text

1.2 REFERENCES

Purpose:

1.0 Scope

Applicable Code Edition and Addenda

Reason for Request

Subject:

Purpose:

References:

Subject:

Purpose:

References:

Subject:

Purpose:

Conclusion:

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Subject:

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CNS-16-067, ASME OM Code In-Service Testing Program Document

Text

1.2 REFERENCES

Purpose:

1.0 Scope

Applicable Code Edition and Addenda

Reason for Request

Subject:

Purpose:

References:

Subject:

Purpose:

References:

Subject:

Purpose:

Conclusion:

References:

Subject:

Purpose:

References:

Subject:

Subject:

Purpose:

Subject:

Purpose:

Navigation menu

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