Text

5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. Page 1 of 15 in Section 4.1 of Incoming Submittal Not Included
	ML20211C375
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Site:	Catawba
Issue date:	05/19/1999
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20211C370	List: ML20211C365; ML20211C375;
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	PROC-990519, NUDOCS 9908250226
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l CATAWBA NUCLEAR STATION l

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ASME INSERVICE TESTING PROGRAM REVISION 25 i May 1999 Prepared by: Date: I' /Y' i Reviewed by: b @ kt b / Date: 19/14Aa I N Approved by: /_ Date: I //9 /99 l

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l TABLE OF CONTENTS SECTION -. PAGES 1.0 Catawba Nuclear Station Program Document 1-38

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2.0 Table of Abbreviations 1-3 1

3.0 PUMP INSERVICE TESTING PROGRAM 3.1 Pump Inservice Testing General Data - Unit I and Unit 2 1-8 4.0 VALVE INSERVICE TESTING PROGRAM 4.1 Valve Inservice Testing General Data - Unit I and Unit 2 Page Number Steam Generator Blowdown Recycle System BB 1-7 Auxiliary Feedwater System CA 1 - 15 Feedwater System CF 1-8 Diesel Generator Fuel Oil System FD 1-2 Refueling Water System FW 1-5 l Instrument Air Lock System lA 1-6 Component Cooling System KC 1 - 11 Diesel Generator Engine Cooling Water System KD 1-1 Spent Fuel Cooling System KF 1-1 l Diesel Gen. Lube Oil System LD 1-4 Radiation System MI 1-6 :

Boron Recycle System NB 1-1 Reactor Coolant System NC 1-7 I

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Residual Heat Removal System ND 1-7 '

ice Condenser Refrigeration System NF 1-3 Safety injection System NI 1 - 37 Nuclear Sampling System NM 1 - 14 Containment Spray System NS 1-8 Chemical & Volume Control System NV 1 - 19 Containment Penetration Valve injection Water System NW 1 - 37 Fire Protection System RF 1-3 l

Nuclear Service Water System . RN 1 - 13 Page I of 2 Rev.25 05/31/99

TABLE OF CONTENTS O 4.0 VALVE INSERVICE TESTING PROGRAM - Continued 4.1 Valve Inservice Testing General Data - Unit I and Unit 2 Main Steam To Aux Equipment SA 1-2 Main Steam System SM 1-4 Main Steam to Atmosphere System SV 1-9 Breathing Air System VB 1-1 Diesel Generator Engine Starting Air System VG 1 - 12 Instrument Air System VI 1-4 Containment Purge Ventilation System VP 1-9 Containment Air Release & Addition System VO 1-2 Station Air System VS 1-1 Cont. Air Ret. & Hydrogen Skimmer System VX 1-1 Cont. Hydrogen Sample & Purge System VY 1-2 Decontamination System WE 1-1 Liquid Waste Recycle System WL 1-7 Control Area Chilled Water System YC 1-1 Makeup Demineralizer Water System YM 1-1 O

5.0 RELIEF REQUEST PAGES 5.1 Pumps -Generic Relief Request 1-1 5.2 Pumps -Specific Relief Request 1-1 5.3 Valves - Generic Relief Request 1-1 l

5.4 Valves - Specific Relief Request 1-1

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6.0 JUSTIFICATION FOR DEFERRAL 6.1 Valves - Justification for Deferral 1-1 7.0 CORRESPONDENCE Page 2 of 2 Rev.25 05/31/99 i

O CATAWBA NUCLEAR STATION ASME Section XI In-Service Testing Program Document I

May 1999 Revision 02 O

l Prepared by:

(/IE se 8 IB/ 97 Date:

Reviewed by: / Date: 6 /9 ~

O i ,,e ee bx: o.#ad D ete: c/n m

TABLE OF CONTENTS 1.0 Scope of Document 2.0 References 3.0 Definitions and Terms 4.0 Valve Program 4.1 Valve IST Program Scope 4.2 Exemption and Position Statements 4.3 Check Valve Testing 4.3.1 Test Frequency 4.3.2 Leak Testing 4.3.3 Full Stroke Testing (Open and Close) 4.3.4 Partial Stroke Testing 4.3.5 Sample Disassembly 4.3.6 Use of Non-Intrusive Testing Techniques (NITS) 4.4 Relief ValveTesting 4.5 Thermal Expansion Check Valves 4.6 Leak Rate Testing s 4.6.1 Appendix J (Containment isolation Valves) 4.7 Remote Position Indication and Testing from Remote Locations 4.8 Post Maintenance and Modification Testing (Retest) 4.9 Fail-Safe Testing 4.10 Skid-Mounted Valves 4.11 Valve Test Acceptance Criteria 4.11.1 Valve Stroke-Time Acceptance Criteria 4.11.2 Stroke-Time measurements and methods 4.11.3 Limiting Values for Stroke-Time Acceptance Criteria 4.11.4 Engineering Evaluations 5.0 Pump Program 5.1 Pump IST Program Scope 5.2 Exemption and Position Statements 5.3 Mini-flow and Full Flow Test'ing 5.4 Vibration Monitoring

5.4.1 Pump Drivers 5.4.2 Smooth Running Pumps 5.4.3 Vibration Points and Trending CNS ASME In-service Testing Program Rev. 02 Page 2 of 38 CNSSCOPE. DOC 05/31/99

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l TABLE OF CONTENTS 5.0 Pump Program (continued) 5.5 Post Maintenance and Modification Testing (Retest) 5.6 Skid-Mounted Pumps i 5.7 Test Acceptance Criteria 5.7.1 Pump Hydraulic Acceptance Criteria 1

6.0 Relief Request 6.1 Implementation of Relief Request 6.2 Interim Relief Request 7.0 Justification for Deferrals 7.1 Testing Deferral Justifications (Practicality Determinations) l 8.0 Appendices Appendix A: IST Program Responsibilities Appendix B: Appendix 8 Supplemental Testing Program i Appendix C: Notification of Program Changes 9.0 Enclosures Enclosure 9.1: Revising the Program Enclosure 9.2: Program Bases Philosophy Enclosure 9.3: Valve Data Sheet Enclosure 9.4: Pump Data Sheet Enclosure 9.5: Generic Relief Request Form Enclosure 9.6: Justification for Deferral Form Enclosure 9.7: Specific Relief Request Form Enclosure 9.8: System Piping Classification Correlation Enclosure 9.9: Summary of CNS IST Program Submittal Changes l Enclosure 9.10: Valve IST Stroke Time Data Evaluation Flow Chart Enclosure 9.11: NC PORV Stroke Requirement Position Statement Enclosure 9.12: SA-1 & SA-4 Position Statement Enclosure 9.13: Cold Shutdown List I

O CNS ASME In-service Testing Program Rev. 02 Page 3 of 33 CNSSCOPE. DOC 05/31/99

1.0 SCOPE OF DOCUMENT

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Technical Specification requires performance of pump and valve testing in accordance with ASME I Section XI. Failure to meet the requirements of this program is a violation of Technical Specifications l j and 10CFR 50.55a. '

The purpose of this program document is to specify the Catawba Nuclear Station (or hereafter referred to as

licensee" or *CNS") In-Service Testing Program for performing valve and pump testing. This document will also outline the process for additions, changes, and deletions of pumps and valves from the CNS IST Program.

1.1 Program Period:

Second Ten Year Interval (120-month period beginning August 19,1995); )

Unit (s) 1 and 2 Concurrently

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1.2 Applicable ASME Code (s) and Addenda:

ASME/ ANSI OM-1987 Edition; PART 6 including OMb-1989 ANSI /ASME OM-1-1987 ASME/ ANSI OM-1987 Edition; PART 10 including OMa-1988 l 1.3 Program Changes:

The NRC and the ANil Will be notified of IST Program changes. However, component additions and deletions will be submitted and testing implemented or deleted without prior NRC approval.

l In the instance where a component has been added to the IST Program, testing and the g appropriate program changes will take place within 90 days of revising the program source i documents unless determined to be impractical. If a hardship is identified, notification will be i submitted to the NRC and an interim extension from testing implementation obtained.

The content of this program document is for non-mandatory compliance to recommendations stated in NUREG 1482 and is intended for the purpose of maintaining program continuity and documentin0 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.

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CNS ASME In-service Testing Program Rev. 02 Page 4 of 38 CNSSCOPE. DOC 05/31/99 I

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2.0 REFERENCES

O V The following documents were used as references in the development of this document:

Generic Letter 89-04 Generic Letter 8910 10 CFR 50, Appendix B 10 CFR 50.55a ASME Section XI (1989)

ASME OM-6 (OMb-1989), OM 10 (OMa-1988), and OM 1 (1987)

Technical Specifications Final Safety Analysis Report (FSAR)

Nuclear System Directive: 408. Testing I Reg. Guide 1.26 NRC Inspection Procedure 73756 Non-Mandatory

References:

NUREG/CP-0123, Proceedings of the NRC/ASME Symposiums on Pump and Valve Testing ;

NUREG-1482, Guidelines for in-service Testing at Nuclear Power Plants, April 1995 ANSI OM-1,1981 Req. for in-service Testing of Nuclear Power Plant Pressure Relief Devices.

OM-13,

Standard for Assessing the Operational Readiness for Power Operated Relief Valves."

OM-22,

Standard for Assessing the Operational Readiness for Check Valves.'

i ASME OMc CODE-1994 NRC Information Notice 97-90 k

CNS ASME in-service Testing Program Rev. 02 Page 5 of 38 CNSSCOPE. DOC 05/31/99

3.0 DEFINITIONS Cnd TERMS Generic Letter 89 the NRC letter providing additional requirements in testing MOVs to design basis conditions.

I Generic Letter 89 the NRC letter providing supplemental guidance on developing and enhancing plant IST programs.

ASME Section XI- the section of ASME Codes and Standards Manual that determines how to perform in- l service testing of light water reactor nuclear plant components.

ASME OM-10 Code - the part of ASME Section XI codes dealing with the in-service testing of valves.

ASME OM-6 Code - the part of ASME Section XI codes dealing with the in-service testing of pumps. 4 Frequencies - the interval of time between in-service testing of the components. These intervals are defined in CNS Technical Specifications:

1) Quarterly (3 months) - 115 days maximum

2) Cold Shutdown (CSD)- Average Coolant Temperature (Tavg) s 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. l IST Component - components (valves and pumps) that are required to be tested per ASME Section XI.

Sections 4.1 and 5.1 of this document define the criteria to be included in the IST Program.

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

" App. J Component" - components leak tested for containment integrity under 10CFR50, Appendix J.

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.

System Resistance- the hydraulic resistance to flow in a system.

Trending- 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.

l Leak Test - testing of valves to verify seat leakage is limited to a specified maximum.

l Stroke-Time - the time interval from valve actuation to the limit switch indication light at the end of the actuating cycle.

l 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 O refueling outage frequency as opposed to quarterly.

i CNS ASME in-service Testing Program Rev.02 Page 6 of 38 CNSSCOPE. DOC 05/31/99 L

4.0 VALVE PROGRAM 4,1 in-Service Testing (IST) Program i

V As required by 10CFR50.55a, valves 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, 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.

l b) All Category B and C valves that fall within the Duke ISI Class A, B, or C boundaries and are l active in the mitigation of the Design Basis Accidents (Design Basis Accidents are defined as those described in Chapter 15 of the FSAR).

c) Valves in systems specifically required by Technical Specifications to be tested per ASME Section l XI.

Valves that are active in certain non-Design Basis Events, are cold shutdown valves not associated with an FSAR 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 supplemental,10CFR50 Appendix B Program, or the IST Program. See Appendix B of this document for a discussion of the 10CFR50 Appendix B 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 othenvise determined by the licensee (reference NUREG 1482).

4.2 Valve Testing Program Exemptions and Position Statements O Valves tested under jurisdiction of this program will be tested per requirements of OM-10 (OMa-1988), 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 attematives.

4.2.1 Category A and A/C valves (containment and pressure isolation valves) will be leak tested in accordance with OM-10 section 4.2.2.

4.2.2 Valve stroke times will be recorded to at least the nearest second, except for valves, which have stroke times of less than one second. For these valves, a time of one second will be recorded.

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-10 section 4.2.1.8 (e).

Additionally, documented stroke times will be to the nearest full second.

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

4.2.4 OM-10, section 6.3 (h) requires 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 in place of a signature in the record of the tests.

4.2.5 11 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 l 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 j 2.4.5). !

O CNS ASME In-service Testing Program Rev. 02 Page 7 of 38 CNSSCOPE. DOC 05/31/99

f i 4.2 V:lva Testing Program Exemptions cnd Position Statement 3 (rontinu d) l NOTE: For cold shutdowns less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , valve testing does not have to be performed.

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(, However, for cold shutdowns expected to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , valve testing will commence as I soon as possible, but no later than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after reaching cold shutdown. Valve testing will l proceed in a normal manner until all testing is complete or the plant is ready to return to power.

A completion of all valve testing is not a prerequisite to return to power. Any testing not i completed by the end of one cold shutdown will be performed during subsequent cold I shutdowns, starting from the last test performed at the previous cold shutdown.

4.2.6 Manual valves that meet the scope requirements of OM-10 or are taken credit for 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. However, testing of such valves will be solely based on exercising requirements established by the licensee.

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 GL 89-04, Position 11. "The intent of 10 CFR 50 Appendix A, GDC-1, and Appendix B, Criterion XI, is that all components, such as pumps and valves, necessary for safe operation are to be tested to demonstrate that they will perform satisfactorily in service."

The licensee reserves the right to include valves which do not meet these criteria in the IST Program. These valves are typically tested in the Supplemental Program. In such cases, the licensee will specify how the component is tested or if a deviation frc,m the Code guidelines is allowable. CNS will not submit Relief Requests or Justification for Deferrals for "Non-Code"-

Class valves.

4.2.8 Thermal Relief Valves that meet the scope requirements of OM-10 or are taken credit for in the n 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 (V) 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 PART 1,1987 sections 1.3.3 and 1.3.4.

4.2.9 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.

4.2.10 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.

C l CNS ASME In-service Testing Program Rev.02 Page 8 of 38 CNSSCOPE. DOC 05/31/99

4.3 Check V:lva 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 conceming interpretations, guidance, and other options and testing attematives for check valves.

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.

4.3.2 Category A and A/C valves (containment and pressure isolation check valves) will be leak tested in accordance with OM-10 (OMa-1988) section 4.2.2.

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 i basis accident flow. If full flow is not possible, then the licensee will perform correlation testing, l partial stroking, or other attematives as provided by OM-10 section 4.3.3.3. Additionally, the l 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 l

subject to the range and accuracy requirements of the code. (ref. NUREG-1482, section 4.1.2).

4.3.4 Check valve exercising to verify the closed position will not require demonstration that the valve was open prior to closure.

1 4.3.5 Seismic boundary check valves will be included in the program.

4.3.6 Check valves included in the Sample Disassembly portion of the IST Program will be disassembled and inspected under the provisions and guidelines given in GL 89-04 and per OM- j 10 (OMa-1988), section 4.3.2.4 (c). i k 4.3.7 Where applicable to the CNS IST Program, back flow testing of check valves will be performed in accordance with GL 89-04 guidance. Examples of methods that may be used to verify valve closure are as follows:

Pump discharge check valves - verified closed by meeting a parallel pump's acceptance ;

criteria while cross-connected; !

Appendix J testing; e 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; e Observation of externalindication on valve stem.

4.3.8 As per recommendations stated in NUREG 1482, the licensee recognizes the NRC's acceptance of non-intrusive techniques (N.I.T.) for testing check valves. The licensee has purchased N.I.T. equipment and is investigating incorporation into the testing program.

However, this N.I.T. equipment has only recently been introduced to the industry and was not supplied from the vendor under the elements of the O.A. program as with other equipment utilized for testing safety related components. This places the burden on the licensee to validate the technology (e.g. software qualifications, calculation validity, engineering correlation, etc.).

Therefore, it is the licensee's position that (N.I.T.) is a voluntary option and will be evaluated on a specific application basis if full stroke exercising or sample disassembly cannot be performed.

CNS ASME In-service Testing Program Rev. 02 Page 9 of 38 CNSSCOPE. DOC 05/31/99

4.4 Relief V:lvaTesting Relief valves tested under the jurisdiction of this program will be tested per code requirements of OM-1,1987, unless it has been determined to be impractical. This section of the program document is to provide the site's

positions conceming interpretations, guidance, and testing attematives for relief valves. Relief valves shall be considered for inclusion in the program if they provide overpressure protection for portions of systems that perform a specific function in shutting down a reactor or in mitigating the consequences of an accident.

4.4.1 Relief valves that are not credited for assisting in mitigating the consequences of an accident and are only instalied for over-pressure protection are considered passive.

4.4.2 Generic Relief Requests CN-GRV-01, CN-GRV-02, and CN-GRV-03 may not apply to all safety or relief valves. Actual valve testing requirements and/or test procedures should be reviewed to determine if these Relief Requests apply.

4.5 Thermal Expansion Check Valves A review of piping configurations inside containment, which could result in thermal expansion over pressurization, was conducted to insure protection had been provided, if necessary. Thermal expansion results when an incompressible fluid trapped between two closed valves inside containment is heated to post accident containment temperatures and expands. Pressure relief is required to prevent failure of the piping betwaen the valves. Relief is accomplished by the slight movement in the open direction of an existing check valve or a check valve placed there for that purpose. Relief for containment penetrations is accomplished by the opening of the inside containment isolation check valve or a bypass check valve around a motor operated inside containment isolation valve. Containment penetrations equipped with Thermal Expansion Check Valves relieve this pressure back to containment.

The amount of opening required to relieve possible over pressurization is small enough such that there is not a credible failure of the check valve in the open direction, which would prevent this. These valves will not be tested in the open direction, unless there are other requirements to do so. All Thermal Expansion Check valves do have a safety function to open and therefore will be categorized as Active.

4.5.1 The following valves are designated as thermal expansion check valves, which protect containtnent penetrations. The open function on these valves may be tested, however this is not for thermal relief capability. These thermal expansion check valves are part of the containment penetration boundary and as such do receive Type C test and are listed in Table 6-77 of the UFSAR.

o 1(2)FW0005 0 1(2)KC0047,1(2)KC0279,1(2)KC0340 0 1(2)NB0262 0 1(2)NC0057 0 1(2)NF0229,1(2)NF0235 0 1(2)NIO471,1(2)N10485 0 1(2)NM0424,1(2)NM0425 0 1(2)NV0090,1(2)NV0874 0 1(2)RF0392,1(2)RF0448 0 1(2)RN0405,1(2)RN0438,1(2)RN0485 0 1(2)WLO321,1 (2)W LOB 06,1(2)WLOB68,1 (2)W LA022 0 1(2)YM0121 4.5.2 The following valves are designated as thermal expansion check valves and are listed in Table 6-77 of the UFSAR, however these valves are not Type C tested. These valves are classified as Pressure isolation Valves (PlVs) and do have leakage requirements per Technical Specification.

The open function on these valves may be tested, however this is not for thermal relief capability.

o 1(2)N1124,1(2)NI125,1(2)N1128,1(2)N1129,1(2)N1156,1(2)N1159,1(2)N1165,1(2)N1167, 1(2)N1169,1(2)N1171,1(2)N1175,1(2)N1176,1(2)N!180,1(2)N1181 CNS ASME in-service Testing Program Rev. 02 Page 10 of 38 CNSSCOPE. DOC 05/31/99

4.5 Thermal Expan:lon Check V:lves - Continued

! 4.5.3 The following valves are designated as thermal expansion check valves and are listed in Table 6-77 of the UFSAR, however these valves are not Type C tested. The open function on these valves is tested by disassembly.

0 1(2)NS0013,1(2)NS0016,1 (2)N S0030,1 (2)N S0033,1 (2)N S0041,1(2)N S0046 4.5.4 The following valves are designated as thermal expansion check valves, however these valves are not Type C tested nor is the open function tested. There are no testable requirements, however these valves will be listed in Section 4.1 of this manual with a note to refer back to Section 4.5 for more information. These valves are listed in Table 6 77 of the UFSAR.

0 1(2)BB0052,1(2)BB0053,1(2)BB0054,1(2)BB0055 0 1(2)KC0280,1(2)KC0322 0 1(2)NM0426,1(2)NM0427,1(2)NM0428,1(2)NM0429 0 1(2)NV0022,1 (2)NV0046,1 (2)NV0057,1(2)NV0068,1 (2)NV0079,1 (2)NV00861 0 1(2)NWOO37,1(2)NWOO107 4.5.5 The following valves are designated as thermal expansion check valves, however these valves are not Type C tested. These valves are classified as Pressure Isolation Valves (PlVs) and do i have leakage requirements per Technical Specification. The open function may be tested, however this is not for thermal relief capability. The valves are not listed in Table 6-77 of the UFSAR.

1 0 1 (2) N 10060, 1 (2)N 10071, 1 (2)N 10082, 1 (2) N 10094, 1 (2) N 10126, 1 (2) N I O 134, 1 (2) N 10157, I 1(2)N10160 4.5.6 The following valves are designated as thermal expansion check valves, however these valves are not Type C tested nor is the open function tested. There are no testable requirements, O however these valves will be listed in Section 4.1 of this manual with a note to refer back to Section 4.5 for more information. These valves are not listed in Table 6-77 of the UFSAR.

o 1(2)ND0116,1(2)ND0117 0 1(2)NV0033,1(2)NV0034,1 (2)NV0049,1 (2)NV0060,1(2)NV0071,1 (2)NV0082, 1 (2 )NV0492, 1 (2)NV0493, 1 (2)NV0494, 1 (2)NV0495, 1 (2)NV0878, 1 (2) NV0879, 1(2)NV0880,1(2)NV0881 4.6 Leak Rate Testing All category A valves will be tested per OM-10, section 4.2.2, except those valves which function in the course of plant operation in a manner that demonstrates adequate seat leak-tightness need not be leakage tested. In i such cases (e.g., Containment Purge Isolation Valves) proper administrative controls will be implemented and {

the valves leak tested during refueling outages. '

l 4.6.1 Category A containment isolation valves shall be tested per 10CFR50, Appendix J and shall be included in the program per GL 89-04, Position 10. Where a valve is identified as a containment

[ isolation valve in the Technical Specification or FSAR and if it is determined to be an " active *'

valve with respect to this function, it will be exercised to the closed position when there is an associated requirement for leak testing.

O CNS ASME in-service Testing Program Rev. 02 Page 11 of 38 CNSSCOPE. DOC 05/31/99

4.7 Testing from Remote Location O Section 4.1 of OM-10 requires valves with remote position indication to be tested 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. Other valve operating parameters, such as timing will not be performed from the remote location during this testing.

4.8 Post Maintenance and Modification Testing (Retest)

(Reference Nuclear System Directive 408 Testing, Sections 408.9 and 408.10) 4.9 Fail-Safe Testing of Valves All Fall-Safe valves shall be tested in accordance with OM-10, section 4.2.1.6. Control valves 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 pederm that function with power and/or air removed (or simulated power and/or air removal).

4.10 Skid-Mounted Valves Until the scope of components for 10CFR50.55a is expanded to include all safety-related pumps and valves, and until the OM codes and standards specifically address skid-mounted components, the testing of the ' major' components supported by skid mounted equipment will be an acceptable means for verifying the operational readiness of the skid-mounted equipment sub-components and assemblies. The licensee however, may opt to include certain components contained on these skids in the IST Program for testing and trending purposes. In O such cases, the licensee will document within the IST Program any exceptions or deferrals and may submit these to the NRC for approval prior to implementation.

4.11 Valve Test Acceptance Criteria All valve test acceptance criteria (IST-TAC) will be developed in accordance with the provisions specified in OM.

10. The applicable acceptance criteria will be developed when the valve is known to be performing in a satisfactory manner. Where IST-TAC other than that required by code is established for a given valve (e.g.,

additional N.I.T. diagnostics), the documentation of that criteria will be at the discretion of the licensee and not required to be part of the test record. Trending of valve IST TAC will be pedormed by the licensee on a periodic i basis. Leakage criteria for valves (other than those tested in accordance to 10CFR50, Appendix J) will be ,

determined based on leakage rates specified by the licensee or using the guidance specified in 4.2.2. Relief j valve IST-TAC will be established per OM-1,1987.

I Such IST-TAC should not be confused with the acceptance criteria specified in DBDs, DBD associated TAC )

Sheets, Technical Specifications, or any FSAR. Such acceptance criteria are the most limiting values and can l not be exceeded. IST TAC are set to verify operational readiness of the valves and to identify valve degradation before the 'most limiting' acceptance criteria is exceeded. IST TAC are based upon stroke times measured when the valve is know to be in good working order and are controlled within the test procedures. Attemately, DBD-TAC are specific cnteria associated with a valve's design basis.

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CNS ASME In-service Testing Program Rev. 02 Page 12 of 38 CNSSCOPE. DOC 05/31/99

4.11 Valve Test Acceptance Criteria (continued) 4.11.1 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 does not move at all on the first try or exceeds the LIMITING VALUE. OM-10 immediately refers to this valve as being inoperable. An engineering evaluation needs to be done to determine the cause of the valve failure and system operabiiity.

CASE 3 : The valve fails to meet the acceptance stroke time, but strokes in less than the LIMITING-VALUE. Per OM-10, the valve ghg! 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 test procedure. A third valve stroke may be performed to demonstrate consistent valve operation.

b. If the valve does not fall within tho acceptable range on the second stroke, then the valve will be analyzed within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months OR declared inoperable (if applicable). An evaluation must be performed to determine the root cause of the failed test. The evaluation may determine that either corrective maintenance must be performed on the valve p.r the new stroke data is acceptable and new baselines must be established. Such results must be erther documented in the test procedure or per the site Problem identification Process (PIP).

c. In the event the initial stroke and the second test results are inconsistent, but the engineering evaluation shows the new stoke- l l time is acceptable, a third test may be performed to venfy consistent behavior. Documentation of the third test will be optionalif it shows no deviation from the second stroke.

4.11.2 Valve Stroke-Time Measurements and Methods:

l Valve stroke-times are measured with a stopwatch to the nearest second. The stopwatch is l started when the valve is actuated and it is stopped when an indication light is received indicating l that the valve has completed its full stroke.

O CNS ASME In-service Testing Program Rev. 02 Page 13 of 38 CNSSCOPE. DOC 05/31/99 L

4.11.3 Limiting-Value Stroke-Time Acceptance Criteria:

Limiting-Values for stroke-times will be established in accordance with guidance given in Generic

\ Letter 89-04, Position 5. It is the position of the licensee that these values will be determird as follows (with the limitations of Tech. Specs. and Safety Analysis limits being the most limiting):

Valve Tvoe Limitino Value Calculation EMO (> 10 secs.) 1.3R (to the nearest 0 or 5sec.)

EMO (s 10 secs.) 1.5R (to the nearest 0 or 5sec.)

POV (> 10 secs.) 2.OR (to the nearest 0 or 5sec.)

POV (s 10 secs.) 2.25R (to the nearest 0 or 5sec.)

Note: Where 'R' represents the valve reference value at acceptable operation.

4.11.4 Engineering Evaluations: (Discussion to be completed for CNS in later revision) l l

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l I CNS ASME in-service Testing Program Rev.02 Page 14 of 38 CNSSCOPE. DOC 05/31/99

5.0 PUMP PROGRAM

( 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 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 Section XI.

b) All pumps that fall within the Duke ISI Class A, B, or C boundaries that are provided with an emerDency power source and are also active in mitigating the consequences of the Design Basis Accidents (Design Basis Accidents are defined as those described in FSAR Chapter 15).

Currently Catawba Nuclear Station is under the requirements of the ASME Code and Standards, OM PART 6,1987 Edition, including OMb-1989 (which is OMa-1988 plus Errata Addenda to correct Table 3).

5.2 Pump Testing Program Exemptions and Position Statements Pumps tested under the jurisdiction of this program will be tested per code requirements of OM-6 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 attematives.

5.2.1 Section 7.3 of the OM-6 code requires the signature of the person or persons responsible for Ci conducting and analyzing the test. The dated initials of the person or persons responsible for conducting and analyzing the test may be used in place of a signature in the record of the tests.

5.2.2 Developed head acceptance (criteria and data) should be rounded to the nearest 0.5 psi, if possible, in most cases the suction gauges used will allow this type of accuracy.

5.2.3 Vibration acceptance (criteria and data) should be truncated to 2 decimal places for operability determinations. The full four-digit display number should still be recorded.

5.2.5 Pumps whose only safety function is predicated on plant shutdown and recovery from a fire per commitments made as a result of 10CFR50, Appendix R are not required to be included in the IST Program. The licensee will test these in accordance with Appendix R requirements.

5.2.6 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.

5.2.7 Pumps, which ca" mly be tested during plant operation, will be tested within 1 week following plant startup to comply with section 5.4 guidance. If the testing schedule is not maintained during plant shutdowns, the affected pump (s) must be tested before entering an operational mode, which requires the pump (s) to be operable. The licensee howevt. may elect to delay repairs and/or retest of pumps not required to be operable for plant startup or other operational modes.

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5.3 Mini-flow and Full Flow Pump Testing (Discussion to be completed at a later date.)

5.4 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. This purpose of this section of the program document is to provide the site's positions conceming interpretations, guidance, and other options of vibration monitoring and analysis. Specific positions to certain sections to follow are currently being developed by the in Service Testing Working Group Team (ISTWG) and will be submitted in future revisions.

5.4.1 Pump drivers. (Discussion to be completed in future revision) 5.4.2 Smooth Running Pumps. (Discussion to be completed in future revision) 5.4.6 Vibration points for pumps. (Discussion to be completed in future revision) 5.5 Post Maintenance and Modification Testing (Retest)

(Reference Nuclear System Directive: 408 Testing. sections 408.9 and 408.10) 5.6 Skid-Mounted Pumps Until the scope of components for 10CFR50.55a, is expanded to include all safety-related pumps and valves, and until the OM codes and standards specifically address skid-mounted components, the testing of the ' major'

^ component supported by skid-mounted equipment will be an acceptable means for verifying the operational readiness of the skid-moun%d equipment sub-components and assemblies. The licensee however, may opt to include certain components contained on these skids in the IST Program for testing purposes. In such cases, the licensee will not be obligated to submit Relief Requests or Justification for Deferrals nor will it be obligated to trend the performance of such components as is required for components that meet the scope of OM-6.

5.7 Pump Test Acceptance criteria All pump test acceptance criteria (IST TAC) will be developed in accordance with the provisions specified in OM-

6. 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 not required to be part of the test record. Trending of pump IST-TAC will be performed by the licensee on a periodic basis.

Such 'IST-TAC'should not be confused with the acceptance criteria specified in DBDs, DBD associated TAC Sheets, Technical Specifications, or any FSAR. Such acceptance criteria are the most limiting values and can not be exceeded. IST-TAC are set to verify operational readiness of the pumps and to identify pump degradation before the 'most limiting' acceptance criteria are exceeded. IST-TAC are based upon performance data measured when the pump is know to be in good working order and are controlled within the test procedures. Attematively, DBD TAC are specific criteria associated with a pump's design basis.

5.7.1 Pump Hydraulic Acceptance Criteria: (Discussion to be included in future revision) l

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6.0 Relief Requests The purpose of a Relief Request is to exclude components from testing requirements of the Code that cannot be followed. Therefore, if the testing on the component can not be performed due to plant configuration, plant safety, v equipment limitations, type, or hazards to personnel, relief from the code will be requested. Submitted relief requests will:

{

1) give an attemative method that ensures an acceptable level of quality and safety, l

2) explain the hardship with meeting the code requirement,

3) provide a schedule or attemative test frequency (or duration for interim Relief Request).

Relief Request for components that are in the IST Program will be sent to the NRC for approval. Each Ten Year interval, when the site testing program is being upgraded to the new testing requirements, all relief requests will be reviewed and re-submitted to insure that their reasons for issuance are still valid. In cases where a " Specific Relie" was previously submitted to the NRC and approval granted, but the conditions and provisions do not change (i.e. no code change or modification to equipment or system) to eliminate the relief, the relief will not require re-evaluation for the next Ten Year interval. Relief Requests will not be written for any non-Code Class components that are included in the IST Program.

6.1 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 attemative testing while the NRC is reviewing the Relief Request, providing the licensee has assured the attemative does not compromise the level of safety provided by the code testing requirement. This position is referenced from NUREG-1482, section 2.5.

6.2 Interim Relief Requests:

When a Relief Request is required on an interira basis, the licensee will submit the relief for review, but as with section 6.1, may implement the relief while the NRC is reviewing the request. Updates to schedules or impacts to modification implemeMation of the component with interim relief will be communicated to the NRC as the program is updated, interim Relief Requests shall be withdrawn when the licensee no longer requires them.

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7.0 Justifications for Deferrals:

Justification for Deferrals (JFDs) will be written when a component can not be tested at the specified frequency.

This could be due to an impracticality of testing the component at power or due to plant safety concems 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 or Refueling Outage 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 retum to operation. For outages when the planned length is not of sufficient duration to complete all tests, testing will start within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of reaching cold shutdown conditions. This is supported by the position stated in OM-10, section 4.3.2.2, OMa 1988 Addenda, c) be performed at the next available cold shutdown consistent with the above criteria if an opportunity to test the valve is not available (Completion of the IST is not a prerequisite to retum 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 cornponent out of service or inoperable. Retest and corrective actions shall be performed at the first available opportunity.

7.1 Testing Deferral Justifications:

7.1.1 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. Removing one train for testing or entering a Limiting Condition of Operation (LCO) is not sufficient basis for not performing the required tests, unless the 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. Other factors such as the effect on plant safety and the difficulty of the test should be considered. As stated earlier, testino should not interfere with oower oroduction.

Note: The Justification of Deferral Form is found in Enclosure 9.6.

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8.0 APPENDICES l

l 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.

The IST Engineer will be responsible for updating and maintaining the IST Database.

The IST Engineer will be responsible for coordinating and implementing the program update and renewal per 10CFRSS every 10 years.

2.0 GO IST Coordinator:

The General Office (GO) IST Coordinator will be an individual responsible for overall corporate IST

(- Program management. He/she ensures Duke Power's 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 (OM-6, OM-10, GL 89-04, I NUREG-1482 etc.).

The GO IST Coordinator will be 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 GO IST Coordinator will provide support for intemal and extemal IST Program audits.

The GO IST Coordinator will be the Single Point of Contact on any issues that involve site-site interaction. The GO IST Coordinator will be responsible for ensuring consistency where practical.

The GO IST Coordinator will represent Duke Power's interest for Code development.

The GO 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.

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I 7 Appendix A: IST PROGRAM Responsibilities (Continued)

(

V) 2.0 GO IST Coordinator (continued):

The GO 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 Mechanical Systems and Eauipment Enaineerina (MSE)

MSE Systems is responsible for the folloiving: i e ensuring the accuracy of IST datasat information, l

. defining test acceptance criteria (TAC),

e ensuring code testing requirements are met, e documenting reasons for scope or code deviation, e providing tech. assistance for developing test procedures, )

. complete valve and pump data sheets for program revisions !

MSE Equipment is responsible for the following:

Notifying the IST Engineer of maintenance that could affect the baseline data for any IST component,

. Overall administration of the relief valve testing program (OM-1),

. Administrating the check valve sample disassembly program, Provide input when evaluating specific component issues (why failed test, baseline changed, etc.,)

{d Each Mechanical System Engineer is responsible for the components within their systems, which are in the program. If the status of component changes, the MSE is responsible for initiating the required changes to the program (see Appendix C).

4.0 Civil / Electrical and Nuclear Enoineerina (CEN)

CEN is responsible for the following:

e notifying the IST Engineer of maintenance that could affect the baseline data for any IST component, e provide input when evaluating specific component issues (why failed test, baseline changed, etc..)

5.0 Operations Performance Test Group (OTG)

This group is responsible for the following:

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

6.0 Operations Procedure Group f This group is responsible for the following:

l

. updating and maintaining all IST procedures,

/ e verifying all technical changes with the IST Engineer.

b)

CNS ASME In-service Testing Prograrn Rev. 02 Page 20 of 38 CNSSCOPE. DOC 05/31/99

! Appendix B: 10CFR50, Appendix B Program (Supplemental Testing Program) v The scope of the Catawba Pump and Valve Testing Program includes:

(1) all components that are active in mitigating the consequences of Design and non-Design Basis Events, or required for cold shutdown, (2) provide a containment isolation function, (3) or are designated by station Technical Specifications to be included in testing programs.

l This scope is further divided into IST testing and 10CFR50, Appendix B testing. (Reference Duke Power Company's Oconee Nuclear Station's 11/1/90 Generic Letter 89-04 response - M. S.

j Tuckman to NRC)

Selected components tested under guidelines of 10CFR50, Appendix B portion of the Catawba Pump and Valve testing program provide a function important to the safety of nuclear power plant operation, but are not explicitly under the scope of GiE OM Codes and Standards or considered beyond the scope of 10CFR50.55a. SpecificeM /,ine 10CFR50, Appendix B Program includes:

(1) pumps and valves not included in the IST Program, which are active in certain non-Design Basis Events, l

I (2) are cold shutdown valves not associated with a FSAR Chapter 15 event, (3) are significant to plant safety, N or are of economic importance.

(4)

The CNS 10CFR50, Appendix B Program will be administered using the ASME IST Code as guidance for testing and trending. The acceptance criteria and testing intervals used to test Appendix B components should be specified by the IST Engineer. Relief Requests and Justification for Deferrals will not be submitted for Appendix B components. If the requirements of the ASME Code cannot be followed for components in the Appendix B Program, deviations from Code

' guidelines' will be documented in the section " SUPPLEMENTAL PROGRAM POSITIONS."

The 10CFR50, Appendix B components will be tested using approved Duke Power "A" procedures and requirements of 10CFR50, Appendix B. Deviations from standard test practices will be allowed only if substantiated in writing per the methods outlined in this document. l l

APPENDIX B: SUPPLEMENTAL PROGRAM POSITIONS:

I B.1 Per Catawba's GL 89-04 response,10 CFR 50, Appendix B manual valves are only stroked at a I refueling frequency.

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CNS ASME in-service Testing Program Rev.02 Page 21 of 38 CNSSCOPE. DOC 05/31/99 m.

l Appendix C: Notification of Program Changes

\_/

The System Engineer shall initiate program changes as changes are made to the respective system, DBDs, or l l

active / passive valve calculations. Notification of extemal customers (e.g. Regulatory Compliance Group) of such changes to the program will occur by issuing the appropriate administrative mechanis'u (i.e. PIP, Minor Modification Request, etc.).

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

e changing the active / passive status of a component, e changing the leakage requirements of the component, '

e changing the piping classification of the component (Duke Class and ISI Class),

e something changes with how the component may be tested, e a commitment is made or changed for testing or operation of a component, e taking credit for a new function, flow path, etc.,

e a modification to the component is planned which can/will significantly affect the components baseline Test Acceptance Criteria (TAC).

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O CNS ASME In-service Testing Program Rev. 02 Page 22 of 38 CNSSCOPE. DOC 05/31/99

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9.0 ENCLOSURES

l Enclosure 9.1 - REVISING THE PROGRAM

1. Process for Revisina the IST Proaram Mechanical Systems Engineering Management Procedure MSE 1.16, " Administration and Control of the Catawba inservice Testing Program", 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 Diaarams (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 attematives. 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 modif' cations, 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 i applicable drawings with relief requests that are very detailed and are submitted to supplement the IST 1 Program.

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l Enclosure 9.2 (RESERVED FOR " PROGRAM BASES PHILOSOPHLY")

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1 CNS ASME In-service Testing Program Rev. 02 Page 24 of 38 CNSSCOPE. DOC 05/31/99

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l Enclosure 9.3

(

l (m

(j Valve Data Sheet l

Revision Addition Deletion Reason for change Valve Number Description Valve Type BA BF CK DI EX GB GT PG PR RV SC ST SV VB Valve Size Actuator Type AO HO MA ML MO MR PA SA SO l l

Flow Diagram Coordinate System Engineer PROFS ID I Containment isolation Valve Yes No Generic Letter 89-10 Valve Yes No Active Valve Yes No ESF Valve Yes No Auxiliary Safe Guard Valve Yes No Skid Mounted Valve Yes No l /N Vent / Drain Yes No U Valve Category l

A B C D (See OM-10 section 1,4)

ASME Class A B C N (non code class) l l

Required Accident Position Open Closed Throttled Cold Shutdown Position Open Closed Throttled Alternate Feedwater Path Yes No DBD Time OPEN DBD Time CLOSED TS Time OPEN TS Time CLOSED FSAR Time OPEN FSAR Time CLOSED Valve Test Type FS PS ST LJ LT Test Direction OC CO BOTH Test Frequency Q CSD RF I Test Procedure L) i l

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Enclosure 9.4 O Pump Data Sheet Pump (s): -

Revision Addition Deletion Reason for Change Pump information ISI Class A B C Duke Class A B C D F G 1!

Pump Manufacturer -

)

Pump Type Pump BEP (Design Pt.) -

gpm psi Driver Manufacturer -

Driver Size -

OFD -

Coor.

ES Actuation Channels 1 2 3 4 5 6 Procedure No(s).: -

Accident Pump Flow -

Delta P Required -

l Full Flow Requirement -

l TAC Sheets -

Procedure No(s): -

)

Test frequency O CSD RF !

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CNS ASME In-service Testing Program Rev. 02 Page 26 of 38 CNSSCOPE. DOC 05/31/99

l Enclosure 9.5 Catawba Units 1 and 2 Generic Relief Reauest item Number:

Component Number (s):

l Flow Diagram (s): 1 Function (s):

ISI Class / Duke Class:

Code Category:

Test Requirement (s): l Basis for Relief:

Code Attemative:

CNS ASME In-service Testing Program Rev. 02 Page 27 of 38 CNSSCOPE. DOC 05/31/99

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l Catawba Units 1 and 2 Justification for Deferral item Number:

Component Number (s):

Flow Diagram (s):

1 Code Category:

ASME Class:

Function (s):

Test Requirement:

Basis for Deferral:

Test Altemative & Frequency:

I CNS ASME in-service Testing Program Rev. 02 Page 28 of 38 CNSSCOPE. DOC 05/31/99

- Enclosure 9.7 Catawba Units 1 and 2 Specific Relief Reauest item Number:

Component Number (s):

1 Flow Diagram (s): !

Function:

ASME Class:

Code Category:

Test Requirement: 1 I

l l Basis for Relief:

l Attemate Testing:

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O CNS ASME In-service Testing Program Rev.02 Page 29 of 38 CNSSCOPE. DOC 05/31/99

Enclosure 9.8 System Piping Classification Correlation Seismic Normally Duke (1) NRC ANSI Pressure Contains System Safety. Quality Duke QA Safety Boundary Seismic Radioactiv Piping fgla, ted GrouD Condition Class Code Des. Criteria (6) Intecrity Cateaory e Material Classification A YES A 1 1 Class 1, ASME Sect. ill YES SC-l YES B YES B 1 2 Class 2, ASME Sect. lll YES SC-1 YES C YES C 1 3 Class 3, ASME Sect. til YES SC-l YES E NO D(3) 2(4) NNS(2) ANSI B31.1.0 NO N/A YES F No D 4 NNS(2) ANSI B31.1.0 YES SC-II(7) NO G NO -

-(4) -

ANSI B31.1.0 NO N/A NO H NO -

-(4) - Duke Power Spec. NO N/A NO H (HVAC) YES -

-(6) -

Duke Power Spec YES SC-l NO NOTES:

(1) Safety Related as used herein is in accordance with 10CFR50 Appendix A General Design Criteria for Nuclear Power Plants and is applicable to function only; i.e., structures, systems, and components required to function

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

V NNS = Non-Nuclear Safety i

(2) j (3) Class E piping is equivalent to NRC Quality Group D; i.e., the system is designed to normally carry a radioactive fluid; however, is considered NNS as a component failure would not result in a calculated potential exposure in excess of the limits established by 10 CFR PART 20.

(4) Class E, G, and H piping systems may also be assigned QA Condition 3 and/or 4 to denote additional requirements for fire protection of safety related components and/ or seismic structural integrity (except pressure boundary) to preclude adverse interactions with Safety related structures, systems and components, respectively; refer to Duke Nuclear Guide 1.29.

(5) Code and Standards Applicability: Duke Power Company establishes an ' effective code date" in accordance with 10CFR50, par. 50.55a for Catawba Nuclear Station. Due to the numerous code and standards references applicable to each station, no attempt is made to specifically identify these references as they are amended, superseded, or substituted. Duke reviews and complies with all or portions of the latest versions of the above Codes and Standards unless materials and/ or design commitments have progressed to a stage that it is not practical to make a change. Whers 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 maintained.

(6) HVAC Duct Systems may be constructed of either sheet metal or piping materials depending upon the design function and requirements. Non-Safety Related HVAC may be assigned QA Condition 4, SC-Il Support Restraints to preclude adverse interactions with safety related structures, systems, and components. Refer to Duke Nuclear Guide 1.29.

(7) Class F for piping systems is used when pressure boundary protection is required. Seismic Category 11 hangers may be use on Class E, G, or H piping systems when pressure boundary integrity is not required. See Duke Guide 1.29.

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Enclosure 9.9 Summary of IST Program Submittal Changes (Wi!! be composed and distributed to all recipients of changes / revisions).

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Enclosure 9.10 VALVE IST STROKE TIME DATA EVALUATION FLOW CHART

/ TEST VALVE 3ST N STROKE

\ /

U U U U VALVE STROKE VALVE STRCKE TIME ' VALVE STROKE TIME TIME WITHIN NOT WITHIN THE EXCEEDS LIMITING VEVE MES NM REFERENC3 RANGE REFERENCE RANGE STROKE TIME VALUE m

V PERFORM A 2ND STROKE TEST V

lI DEcLAxE THE N 2ND STROKE Is

/~} VALVE WITHIN RErER mCE RANGE NOT WITHIN THE } $

VALVE INOPERABLE E REFERU CE RmGE ) DOCUMUT 7N T.S.A.:.L.

U aun U 1 DOCUMENT s V

PERFORM ENG. PERFORM E

,30,, ,3, EVALUATION CORRECTIVE ACTIcN gg WITHIN 96 FOR VALVE HOURS v

U V DETE****

m [ REVISE REr. Race PERroRM F

(REBASELINE) STROKE TEST E

NEEDED ,g E

1I ,.

7( h N

VAI.VE CPERABLE

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CNS ASME In-service Testing Program Rev. 02 Page 32 of 38 CNSSCOPE. DOC 05/31/99

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m$yg P-O t n

e m e n n t C

N-t ar s

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En:leure 9.12 CATAWBA NUCLEAR STATION i

MECHANICAL SYSTEMS ENGINEERING SA-1 & SA-4 POSITION STATEMENT j Subiect: SA-1 & SA-4 Exclusion from the Inservice Testing Program

Purpose:

The purpose of this letter is to document Engineering's position for not including valves SA-1 & SA-4 in the IST Program.

Position Statement: j 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 oflocal 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 i CAPT. However, CAPT operation can continue with one of these valves closed providing that steam is available from the opposite SM piping.

T/S 3.6.3 and Table 3.6-2 are applicable to valves that are required to close on an ESF signal to ensure penetrations passing through containment are isolated during an accident. Those j systems and penetrations essential for reactor core protection are not automatically isolated !

during such events. SA-1 and SA-4 are listed as Containment Isolation Valves in T/S 3.6.3 Table 3.6-2, but are not closed on an ESF signal.

Valves SA-3 (S/G B Main Steam to CAPT Stop Check) and SA-6 (S/G C Main Steam to CAPT :

Stop Check) are stop check valves located in the Aux. Building Elevation 543' Mechanical Penetration Room, downstream (CAPT side) of valves SA-1 and SA-4 respectively, before the SA piping joins together to supply the CAPT. The piping and supports for SA-3 and SA-6 are procured and maintained within the constraints of ASME Class II (Duke Class B) standards; and are therefore, of acceptable construction to extend the penetration beyond the identified Containment Isolation Valves (SA-1 and SA-4). These valves are required to be open for CAPT operation when supplying steam to the CAPT from the respective SM piping. However, CAPT operation can continue with one of these valves closed provided steam is available from the opposite SM piping.

Catawba FSAR Table 6.2.4.1, Containment Isolation System Design Basis (10CFR50, Appendix l A, Criterion 57, Closed System Isolation Valves) originally listed valves SA-1 and SA-4 as l Containment Isolation Valves. However, these valves have since been replaced in the FSAR table by valves SA-3 and SA-6, following a Design Study performed as a result of PIP 1-C 0008. The Design Study concluded that these valves and associated piping are of a sufficient design and construction for use as Containment Isolation Valves (as discussed previously) due to 3 accessibility concerns with SA-1 and SA-4 for certain scenarios requiring the isolation of one steam supply to the CAPT. For the Main Steam Line break, environmental conditions in the Doghouse may prevent Operator access to these valves.

CNS ASME in-service Testing Program Rev. 02 Page 34 of 38 CNSSCOPE. DOC 05/31/99

Enclosure 9.12 (continued)

CATAWBA NUCLEAR STATION

( MECHANICAL SYSTEMS ENGINEERING l SA-1 & SA-4 POSMON STATEMENT 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:

i

1) Steam Generator Tube Rupture (SGTR) and

2) Main Steam Line Break.

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 are used in the EPs 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. 3 Therefore, if accessible, closing SA-1 and SA-4 would be preferable over SA-3 and SA- l

6. In each of these accident scenarios, the time required for an Operator to close the l applicable valve has been estimated and factored into the Accident Analyses and r resultant dose calculations. Calculated off-site doses are within allowable values for I

these scenarios.

For the SGTR scenario, failure to isolate steam to the CAPT from the S/G with the I

, tube rupture would allow indefinite release of main steam to the atmosphere via the l

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 S/G, rendering the CAPT inoperable due to the loss of all steam supply, and 1 also affecting the operation / 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 i and isolate the faulted steam line. Unless the steam line break is located in the O Interior Doghouse, closing SA-1 and SA-4 would be preferable over SA-3 and SA-6. !

CNS ASME In-service Testing Program Rev.02 Page 35 of 38 ,

CNSSCOPE. DOC 05/31/99

E 1

)

Enclosure 9.12 (continued) l CATAWBA NUCLEAR STATION MECHANICAL SYSTEMS ENGINEERING SA-1 & SA-4 POSITION STATEMENT FSAR Table 6-77 was revised to list SA-1 and SA-4 as the Containment Isolation Valves for penetrations M261 and M363. Applicable Operations EP's and AP's were revised to use SA-1 and SA-4 as the first response with the option for using SA-3 and SA-6. i l

The NRC has reviewed and approved an exemption to 10CFR50, Appendix A, GDC57 by letter dated December 29,1998, from Peter S. Tam, Senior Project Manager, Office of Nuclear Reactor Protection, Nuclear Regulatory Commission.

!O l

l l

O CNS ASME In-service Testing Program Rev.02 Page 36 of 38 CNSSCOPE. DOC 05/31/99 i

c t

Enclosure 9.13 CATAWBA NUCLEAR STATION MECHANICAL SYSTEMS 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 oflinks, 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)N10100B 24 1(2)ND0002A 47 1(2)NIO183B 70 1(2)NIO342*

2 1(2)NIO103A 25 1(2)ND0036B 48 1(2)NV0188A 71 1(2)NV0813*

l 3 1(2)NIO144A 26 1(2)ND0037A 49 1(2)NV0189B 72 1(2)NV0254*

i 4 1(2)N10147B 27 1(2)NIO173A 50 1(2)NV0202B 73 1(2)NI0009A 5 1(2)NI0162A 28 1(2)N10178Il 51 1(2)NV0203A 74 1(2)NI0010B 6 1(2)NIO121A 29 1(2)NV0252A 52 1(2)NV0312A 75 1(2)NIO184B 7 1(2)NIO152B 30 1(2)NV0253B 53 1(2)NV0314B 76 1(2)NIO185A l

8 1(2)NIO332A 31 1(2)SM0001 54 1(2)NV0010A 77 1(2)NIO125*

9 1(2)NIO333B 32 1(2)SM0003 55 1(2)NV0011A 78 1(2)NIO129*

l 10 1(2)NIO334B 33 1(2)SM0005 56 1(2)NV0013A 79 1(2)CF0028 11 1(2)KC0320A 34 1(2)SM0007 57 1(2)VI0O77B 80 1(2)CF0030 12 1(2)KC0332B 35 2CA0149 58 1(2)FWOO28 81 1(2)CF0037 l 13 1(2)KC0333A 36 2CA0150 59 1(2)FW0056 82 1(2)CF0039 l 14 ' 1(2)NC0250A 37 2CA0151 60 1(2)ND0010 83 1(2)CF0046 15 1(2)NC0251B 38 2CA0152 61 1(2)ND0044 84 1(2)CF0048 16 1(2)NC0252B 39 1(2)CF0033 62 1(2)NI0060* 85 1(2)CF0055 l

17 1(2)NC0253A 40 1(2)CF0042 63 1(2)NI0071* 86 1(2)CF0057 18 1(2)NV0015B 41 1(2)CF0051 64 1(2)NI0082* 87 1(2)NV0089A 19 1(2)NV0001A 42 1(2)CF0060 65 1(2)NI0094* 88 1(2)NV0091B 20 1(2)NV0002A 43 1(2)NS0038B 66 1(2)NIO175* 89 1(2)V10077B 21 1(2)ND0032A 44 1(2)NS0043A 67 1(2)NIO176*

22 1(2)NC0065B 45 1(2)ND0028A 68 1(2)NIO180*

23 1(2)ND0001B 46 1(2)NI0136B 69 1(2)NIO181*

Denotes partial stroke CNS ASME In-service Testing Program Rev. 02 Page 37 of 38 CNSSCOPE. DOC 05/31/99 1

m Enclosure 9.13 (continued)

CATAWBA NUCLEAR STATION MECHANICAL SYSTEMS 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)NV0091B are considered Cold Shutdown valves; however, exercising these valves while the reactor coolant pumps are in operation could result in pump damage.

OM Part 10 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 following valves are considered to be Cold Shutdown valves although they are actually tested in Mode 3 following each cold shutdown of greater than 30 days: 1(2)CA0037, 1(2)CA0041, 1(2)CA0045, 1(2 )CA0049, 1(2)CA0053, 1(2)CA0057, 1(2)CA0061, 1(2)CA00G5.

In addition, the following valves are also considered Cold Shutdown valves although the movement to close test is actually performed in Mode 4 during Pressure Boundary Valve testing:

O 1(2)NIO124 1(2>NIO125, 1(2>NIO12e. 1(2>NiO128, 1(2)NIO12e, 1(2)NIO134, 1(2>NiO15e.

1(2)NIO157, 1(2)NIO159, 1(2)NI0160, 1(2)NFI165, 1(2)NI0167, 1(2)NI0169, 1(2)NIO171, 1(2)NI0175, 1(2)NIO176, 1(2)NIO180 1(2)NIO181.

Testing of these valves during Modes 3 and 4 as described above in allowed per NUREG 1482, section 3.1.1.2.

3. The PORVs, valves 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 9.11 in the IST Program Document for further guidance for testing valves 1(2)NC0032B,1(2)NC0034A, and

~

1(2)NC0036B.

I I

i l

I O l CNS ASME In-service Testing Program Rev. 02 Pago 38 of 38 CNSSCOPE. DOC 05/31/99

r Ccttwbs Unit 1 Cctawbs Unit 2 TABLE OF ABBREVIATIONS Duke System Designed for ANS Safety l Valve Class Code Desien Criteria Seismic Loading Gass a

A Class 1, ASME Section III,1971 Yes 1 B Class 2, ASME Section III,1971 Yes 2 C Class 3, ASME SectionIII,1971 Yes 3 E ANSI B31.1.0 (1967) No NNS F ANSI B31.1.0 (1967) Yes NNS G ANSI B31.1.0 (1967) No -

H Duke Power Company Specification No -

j l

l NNS = Non-Nuclear Safety i

. Numbering Sequence for Relief Request and Justification For Deferral Examples:

RELIEF REQUEST JUSTIFICATION FOR DEFERRAL i CN- SRP- VG- 01 CN- VG- 01 SEQUENCE SEQUENCE SYSTEM (N/A if Generic) SYSTEM l

STATION (SPECIFICor QENERIC)

EELIEF for(EUMP or VALVE)

STATION -

O ;

05/31/99 SECTION 2.0 Rev.25 Page 1 of 3

Catswba Uniti Catawba Unit 2 TABLE OF ABBREVIATIONS

(~

( VALVE TYPE Description BA Ball BF Butterfly CK Check CT Control DI Diagram EX Explosive GB Glove GT Gate KT Kerotest ND Needle PG Plug PR Pressure Regulating RV Relief SC Stop Check ST Stop SV Solenoid TW Three Way VB Vacuum Breaker FREQUENCY Description O 2RF 2Y 6M Every Other Refueling Outage Testing Once Every Two Years Tested Every 6 Months CS Tested At Cold Shutdown CSDRF Tested Each Cold S/D And Each RFO I ILRT Tested Every ILRT Outage M Tested Once Monthly i NA No Specified Test Frequency l Notel See Technical Specification ,

Note 2 6 Month, See Technical Specification l Note 3 CSD, Hot Tested Prior To LTOP NPT No Periodic Test Required NT No Test Required ).

Q Tested Once Quarterly l QCS Tested Quarterly And Each Cold Shut Down ;

QRF Tested Quarterly And Each Refueling Outage RF Tested Every Refueling Outage RR Per Relief Request RV Test Relief Valve Per Om-1 Schedule SD Disassemble One Valve Per Group Each Refueling Outage UNK Unknown VV Visual Verification Frequency W Tested Once Weekly Y Tested Once Yearly '

05/31/99 SECTION 2.0 Rev.25 Page 2 of 3 l

Cettwbs Unit 1

{ Catawba Unit 2 TEST TYPE Description AM Acoustic Monitoring ASGC Aux Safeguards Circuitry Test BT New Baseline Test CAL Calibration CSE Contact System Engineering CVE Contact Valve Engineering i CVED Contact Valve Engineering for DP Test Requirements EX Explosive Valve Test FS Full Stroke Exercise Valve To Safety Position (s)

Fr Failed To Safe Position IS Instrumented Electrical Stroke LJ Leak Rate Test Valve To App } Requirements (s)

LT Leak Rate Test Valve To Section XI Requirements (s)

LTNW Qualified Seal System Leak Rate Test (CNS only)

LTrS Leak Test Per Tech Spec Requirements MFVT Miniflow Verification Test MV MOVATS/ Votes-MOV's NTS See Program Document - Section 4.5 NT No Test Required PF Piping Flush PI Verify The Valve Remote Position Indication PIS Pre And Post Maintenance Instrumented Electrical Stroke O

PS PartialStroke Exercise Valve PSTT Pump Source Transfer Test ,

PV MOVATS/ Votes-POV's i RV Safety And Relief Valve Test l RVPR Safety And Relief Valve Test - Pressure Regulator !

SD Sample Disassembly SFB System Flow Balance SFT Failed to Safe Position and Timed SP Special Test For Particular Component Or Situation ST Measure Full Stroke Time Of Valve TTB Torque Test Bench UNK Unknown US Functional (Uninstrumented) Stroke Only OM-10 VALVE CATEGORIES Category A Leakage is Critical Category B Leakage is NOT Critical Category C Self Actuating (Checks, Reliefs, Etc..)

05/31/99 SECTION 2.0 Rev.25 Page 3 of 3

O DUKE POWER CATAWBA NUCLEAR STATION l

1 O

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ML20211C375

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ML20211C375

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2.0 REFERENCES

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