ML20212A270

Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valves Inservice Testing Program

ML20212A270
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/28/1999
From:	DUKE POWER CO.
To:
Shared Package
ML20212A269	List: ML20212A263 ML20212A270
References
PROC-990528, NUDOCS 9909160136
Download: ML20212A270 (450)

Text

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Duke Power McGuire Nuclear Station Units 1 and 2 Pump and Valve Inservice Testing Program and Br/ggf g* 4

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lO DUKE POWER A Duke Energy Company l

l McGuire Nuclear Station ASME Inservice Testing Program Revision 25 December 1998 l

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Prepared by: b, b. Date: 5 i9 99

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Reviewed by: /IdtfLA//[/ Date: 5//$/%

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Approved by: . . .

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TABLE OF CONTENTS r} EiN110H EAGES C'

1.0 McGuir a Nuclear Station Program Document 1-30 2.0 Table Of Abbreviations 1-3 3.0 PUMP INSERVICE TESTING PROGRAM 3.1 Pur p Inservice Testing General Data - Unit 1 and Unit 2 1-11 4.0 VALVT, INSERVICE TESTING PROGRAM 4.1 Valve Inservice Testing General Data - Unit I and Unit 2 Page Number Steam Generator Blowdown Recycle BB 1-2 Auxiliary Feedwater CA 1 - 14 Feedwater CF 1-5 Diesel Generator Fuel Oil FD 1-3 Refueling Water FW 1-4 e Nitrogen GN 1-1 Containment Personnel Airlock lA 1-4 Component Cooling KC 1-10 Diesel Generator Cooling KD 1-2 j Diesel Lube Oil LD 1-2  !

Miscellaneous instrumentation MI 1-2 Boron Recycle NB 1-1 Reactor Coolant NC 1-6 Residual Heat Removal and Low Head Safety injection ND 1-6  ;

Ice Condenser System NF 1-2 )

Medium Head Safetyinjection NI 1-26 Nuclear Sampling NM 1-7 Containment Spray NS 1-8 Chemical & Volume Control NV 1-15 Fire Protection - Interior RF 1-1 Nuclear Service Water RN 1-15 Containment Ventilation Cooling Water RV 1-4 Main Steam Supply to Auxiliary Equipment SA 1-3 Main Steam SM 1-3 q Main Steam Relief to Atmosphere SV 16 k,,/ Breathing Air VB 1-1 Control Room and Area Ventilation VC 1-1 Page 1 of 2 12/31/98

TABLE OF CONTENTS 1

O SECTION PAGES 4.0 VALVE INSERVICE TESTING PROGRAM Continued 4.1 Valve Inservice Testing General Data - Unit I and Unit 2 Annulus Ventilation VE 12 Diesel Generator Starting Air VG 1-5 Instrument Air VI 1-5 Containment Purge VP 1-4 Containment Air Release & Addition VO 1-2 Station Air VS 1-1 Containment. Air Return and Hydrogen Skimmer VX 1-2 Liquid Waste Recycle WL 1-5 Diesel Generator Room Sump Pump WN 1-2 Groundwater Monitoring and Sump WZ 1-1 Control Area Chilled Water YC 1-3 Demineralized Water YM 1-1 O

PAGES 5.0 RELIEF REQUEST 5.1 Pumps - Generic Relief Request 1-1 5.2 Pumps - Specific Relief Request 1-1 5.3 Valves- Generic Relief Request 1-1 5.4 Valves- Specific Relief Request 1-1 6.0 JUSTIFICATION FOR DEFERRAL 6.1 Valves -Justification for Def arral 1-4 7.0 SUPPIEMENTAL TEST PROGRAM 1-1 7.1 Supplemental Testing Program - Valves 1-10 .

7.2 Supplemental Testing Program - Pumps 1-1 l

l 8.0 CORRESPONDENCE O l Page 2 of 2 {

12/31/98

O McGUIRE NUCLEAR STATION ASME Section XI In-Service Testing Program Document December 1998 l i

REVISION 0 0

Prepared by: E L . IJ.dd Date: 6fl9f9i Reviewed by:/[deX//.] d Date: 5//4/99 O ,,,,,,,,,,; mzg;;, ,,,,, ,2 j,,

TABLE OF CONTENTS l

l 1.0 Scope of Document

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2.0 References i

3.0 Definitions and Terms 4.0 Valve Program 4.1 In-Service Testing (IST) Program 4.2 Valve Testing Program Exemptions and Position Statements 4.3 Check Valve Testing 4.4 Relief Valve Testing 4.5 Leak Rate Testing 4.6 Testing From Remote Locations 4.7 Post-Maintenance and Modification Testing (Retest) 4.8 Fail-Safe Testing of Valves 4.9 Skid-Mounted Valves 4.10 Valve Test Acceptance Criteria 5.0 Pump Program 5.1 In-Service Testing (IST) Program 5.2 Pump Testing Program Exemption and Position Statements 5.3 Mini-flow and Full-Flow Testing 5.4 Vibration Monitoring 5.5 Testing From Remote Locations 5.6 Post-Maintenance and Modification Testing (Retest) 5.7 Skid-Mounted Pumps 5.8 Pump Test Acceptance Criteria 6.0 Relief Requests 6.1 Implementation of Relief Request 6.2 Interim Relief Request 7.0 Justification for Deferrals 7.1 Testing Deferral Justifications (Practicality Determinations) 8.0 Appendices Appendix A: IST Program Responsibilities ApperEx B: 10CFR50, Appendix B Program Guidance Document Appendix C: Notification of Program Changes 9.0 Enclosures Enclosure 9.1: Revising the Program Document Enclosure 9.2: Program Bases Philosophy Enclosure 9.3: Generic Relief Request Form Enclosure 9.4.' Justification for Deferral Form Enclosure 9.5. Specific Relief Request Form Enclosure 9.6: System Piping Classification Correlation Enclosure 9.7: Summary of IST Program Submittal Changes im U

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1.0 SCOPE OF DOCUMENT l

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Technical Specifications require performance of pump and valve testing in accordance with ASME Section XI. Failure to meet the requirements of this program are a violation of Technical Specifications and 10CFR 50.55a.

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

" licensee" or "MNS") In-Service Testing (IST) 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 MNS IST program.

1.1 Program Period:

Second Ten-Year interval (120 month period beginning March 1,1994);

Unit (s) 1 and 2 Concurrently.

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 1.3 Program Changes:

The NRC shall be notified of IST program changes. In certain cases, component additions and deletions may 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 (q/ program changes will take place within 90 days of revising the program source documents unless determined to be impractical.

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 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.

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2.0 REFERENCES

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

NRC Generic Letter 89-04 NRC Generic Letter 89-10 NRC Generic Letter 91 18 NRC Generic Letter 96-06 i

10 CFR 50, Appenda B l

10 CFR 50.55a ASME OM-6 (OMb-1989), OM-10 (OMa-1988), and OM-1 (1987)

Technical Specifications Updated Final Safety Analysis Report (UFSAR)

Nuclear System Directive: 408. Tewing

Reg. Guide 1.26 1

NRC Inspection Procedure 73756 Non-Mandatory

References:

NUREGEP-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 in4ervice Testng of Nuclear Power Plant Pressure Relief Devices. j OM-13, " Standard for Assessing the Operational Readiness for Power Operated Relief Valves."

OM-22," Standard for Assessing the Operational Readiness for Check Valves."

ASME OMc CODE-1994 NRC Information Notice 97 90 t

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3.0 DEFINITIONS and TERMS G:neric Lett:r 89 the NRC letter providing additional requirements in testing MOVs to design basis conditions.

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-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.

Frequencies - the interval of time between in-service testing of the components. These intervals are defined in MNS 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.

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.

" 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 accomp!ishing a system safety function.

A Passive Component - a component that does not perform a mechanical motion during the course of V 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.

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

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

Limiting Stroke Time - the owner specified maximum time allowed for a valve to stroke before becoming l immediatelyinoperable.  ;

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.

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1 4.0 VALVE PROGRAM em t '

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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 ISI Class A, B, or C, which corresponds to ASME Class 1,2, or 3 respectively, under the scope of OM10, are included in the MNS IST Program. The following defines the criteria for inclusion of equipment in the

!ST Program:

a) All Category A valves that fall within the Duke ISI Class A, B, or C boundaries.

b) All Category B and C valves that fall within the Duke ISI Class A, B, or C boundaries and are active in the miti0ation 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 Section XI.

MNS 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 may be tested in the supplemental,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 i valves in the IST program. Until the scope of 10CFR50.55a is changed, the scope of the IST program will l 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).

4.2 Valve Testing Program Exemptions and Position Statements 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 MNS 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 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).

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 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.

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4.2 V:lva Testing Program Exemptions and Prition Statements (continued) g 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 b 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 l outage frequency is not a deviation from the code (reference NUREG-1482, Section 2.4.5).

NOTE: For cold shutdowns less than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, valve testing does ngl have to be performed. For cold shutdowns expected to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, valve testing may commence as soon as possible, but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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. A completion of all valve testing is not a prerequisite to retum 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.

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, exercising of such valves will be based on practical frequencies as determined by the licensee. When such frequencies are other than quarterly, it will be documented in the deferral.

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 II,"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 g licensee may c.pt to include valves which do not meet these criteria in the IST Program or in the Q Supplemental Prcoram. In such cases, MNS 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 safety analysis for being capable of relieving pressure due to thermal expansion 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 PART 1,1987 sections 1.3.3 and 1.3.4. The licensee may opt to replace certain thermal relief devices as allowed in OMc - 1994 (App.1). ,

4.2.9. 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 between 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 4 Expansion Check Valves relieve this pressure back to containment.

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4.2 V;lva Testing Program Exemptions cnd P:cition Ctatement3 (ccntinued) 4.2.9. Thermal Expansion Check Valves - continued The amount of opening required to relieve possible over pressurization is small enough such that O 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 are categorized as Active.

The following valves are designated as thermal expansion check valves which protect penetrations. The open function on some of 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 6-112 of the UFSAR.

FW 1(2) FW5,1FW67,2FW63 KC 1(2)KC47,1(2)KC279,1(2)KC280,1(2)KC322,1(2)KC340 NB 1(2)NB262 NC 1(2)NC57,1(2)NC259,1(2)NC261 )

NF 1(2)NF229 NI 1(2)NI436 NM 1(2)NM420,1(2)NM421 NV 1(2)NV1002 RF 1RF823,1RF834 WL 1(2)WL24,1(2)WL385 l YM 1(2)YM116 l The following valves are also designated as thermal expansion check valves, however these valves are not Type C tested. The open function on some of these valves may be tested, however this is not for thermal relief capability. These vcives are also listed in Table 6-112 of the UFSAR.

NC 1(2)NC59,1NC284 NI 1 (2)N112, 1 (2)N115, 1(2)NI60, 1 (2)N182, 1(2)N1124, 1 (2)N1125, 1 (2)N1126, 1 (2)N1156, 1(2)N1157,1(2)N1165,1(2)NI175,1(2)N1180,1(2)N1354 NM 1(2)NM424,1(2)NM425,1(2)NM426,1(2)NM427 NS 1 (2)NS13,1 (2)N S16,1 (2)NS30,1 (2)N S33,1(2)NS41,1 (2)NS46 NV 1 (2)NV12, 1 (2)NV14, 1 (2)NV15, 1 (2)NV20, 1 (2)NV22, 1 (2)NV29, 1 (2)NV31, 1 (2)NV45, 1 (2) NV47, 1 (2) NV61, 1 (2)NV63, 1 (2)NV77, 1 (2) NV79, 1 (2) NV96, 1 (2) NV810, 1 (2)NV81 1, 1(2)NV812,1(2)NV813,1(2)NV841,1(2)NV1008 4.2.10 Containment Purge Valves (VPs), which are passive in the closed direction, will be leak tested j per 10 CFR 50, Appendix J but not stroke-timed for IST purposes. Containment Purge valves are l

" passive" in Modes 14. During a postulated fuel handling accident inside the containment, no l credit for containment isolation or mixit,g 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.

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4.3 Check Valve Testing

% Check valves tested under the jurisdiction of this program will be tested per Code requiremems at the specified frequencies unless it has been determined to be impractical. This section of the program document is to provide the MNS positions conceming interpretations, guidance and other options and testing alternatives for check valves in the IST program.

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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. (ref. NUREG-1482,4.1.1) 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 basis accident flow, if full flow is not practical, then the licensee will perform correlation testing, partial stroking, or other attematives as provided by OM 10 section 4.3.2.2. Additionally, the code allows l 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 the code. (ref. NUREG-1482, section 4.1.2).

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

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-10 (OMa-1988),

n section 4.3.2.4 (c).

U 4.3.7 Where applicable to the MNS 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.

1 . Appendix J Testing -

0 Measure back flow through the valve using an open vent on the backside of the valve or ultrasonic flow measurement techniques; o Pressure drop across a pump; o Pump wind-milling; o Observation of externalindication on valve stem.

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F 4.3 Check Valve Testing (continued) 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 16ensee's position that (N.I.T.) is a voluntary option and will be evaluated on a specific application basis.

4.4 Relief Valve Testing 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 provides the site's positions concerning interpretations, guidance, and testing alternatives for relief valves. A relief valve 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.

4.5 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. In such cases (e.g.,

Containment Purge Isolation Valves) proper administrative controls will be implemented and the valves leak tested during refueling outages.

4.5.1 Category A containment isolation valves will 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 UFSAR 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.

4.6 Testing from Remote Location 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 will 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.

4.7 Post Maintenance and Modification Testing (Retest) l (Reference Nuclear System Directive 408 Testing, Sections 408.9 and 408.10) l l

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I l 4.8 Fall-Safe Testing of Valves l

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All fail-safe valves will 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 perform that function with power and/or air removed (or simulated power and/or air removal).

4.9 Sidd-Mounted Valves Until the scope of components for 10CFR50.55a is expanded to include all safety-related valves, and until the OM codes and standards specifically address skid-mounted valves, the testing of the ' major' components supported by skid mounted valves will be an acceptable means for verifying the operational readiness of the skid-mounted valves or sub-assemblies (ref. NUREG 1482, section 3.4). 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, the licensee will document within the IST program any exceptions or deferrals and may submit these to the NRC for approval prior to implementation.

4.10 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 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. Trending of valve IST-TAC will be performed by the licensee on a periodic basis. IST-TAC should not be confused with the acceptance criteria specified in UFSAR, DBD associated TAC Sheets, or Technical Specifications (such acceptance criteria is often the most limiting values that can 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 N exceeded. Valve IST-TAC will be evaluated to verify that other acceptance criteria specified (UFSAR, (d DBD, Tech. Specifications, etc.) will not be exceeded.

Leakage criteria for valves (other than those tested in accordance to 10CFR50, Appendix J, Technical Specifications, or system specific criteria) will be determined based on leakage rates specified by the licensee or using the guidance provided in 4.2.2.

Relief valve IST-TAC will be established per OM-1,1987 or in specified cases, TAC may be determined from the owner's calculations as permitted per OM Code,1994 Appendix 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. This valve shall be immediately declared inoperable.

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4.10 Valve Test Acceptance Criteria (continued) 4.10.1 Valve Stroke-Time Acceptance Criteria:

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( CASE 3 : The valve fails to meet the acceptance stroke time, but strokes in less than the

') LIMITING-VALUE. Per OM-10, the valve shall be either declared inoperable or immediately stroked again to achieve an acceptable stroke time. Per the McGuire 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 the acceptable range on the second stroke, then the valv*e will be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 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 .ol the new stroke data is acceptable and new baselines must be established. Such results must be documented in the test procedure,

c. In the event the initial stroke and the second test results are inconsistent, but the ,

engineering evaluation shows the new stoke-time is acceptable, a third test may be performed to verify consistent behavior. Documentation of the third test will be optional if it shows Do deviation from the second stroke.

4.10.2 Valve Stroke-Time Measurements and Methods:

McGuire normally uses the OAC for stroke-timing. However, valve stroke-times may be measured with a stopwatch. The stopwatch is started when the valve is actuated and it is stopped when the testing coordinator has determined the proper signal is received indicating the valve has completed hq the full stroke.

4.10.3 Limiting-Value Stroke-Time Acceptance Criteria:

Limiting-Values for stroke-times will be established in accordance with guidance given in Generic I Letter 89-04, Position 5. 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 Tvoe Limitina Value Calculation EMO (> 10 secs.) 1.3R (up to the nearest 5sec. increment)

EMO (s 10 secs.) 1.5R (up to the nearest 5sec. increment)

AOV (> 10 secs.) 2.0R (up to the nearest 5sec. increment)

AOV (s 10 secs.) 2.25R (up to the nearest 5sec. increment)

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

4.10.4 Engineering Evaluations: (Reserved for completion in future revision)

V MNS ASME in-service Testing Program Page 12 of 30 MNSSCOPE. DOC 12/31/98 l

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l 5.0 PUMP PROGRAM 5.1 in-Service Testing (IST) Program p 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.

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

1 Current!y McGuire Nuclear Station is under the requirements of the ASME Code and Standards, OM PART 6, l 1987 Edition, including OMb-1989 (which is OMa-1988 plus Errata Addenda to correct Table 3). This was the Code in eff ect 12 months prior to the anniversary date of the MNS 120-month update.

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 MNS positions on interpretations, guidance and other options regarding testing alternatives.

l l 5.2.1 Section 7.3 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.

5.2.2 Pumps whose only safety function is predicated on plant shutdown and recovery from a fire per O. 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.

5.2.3 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 i testing puPose only.

l 5.3 Mini-flow and Full Flow Pump Testing. (Discussion to be completed in future revision) l l

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l 5.4 Vibration Monitoring Pump vibrations monitored under the jurisdk. tion of this program will be performed per code requirements l r t

at the specified frequencies unless it has been determined to be impractical or a specific deviation from l code is needed . This purpose of this section of the program document is to provide the site's positions l conceming interpretations, guidance, and other options of vibration monitoring and analysis. Specific l

positions to certain sections 70 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 r:ompleted in future revision) 5.4.3 Vibration points for pumps. (Discussion to be completed in future revision) 5.5 Testing required from Remote Locations (Not Applicable to McGuire Nuclear Station) 5.6 Post Maintenance and Modification Testing (Retest)

(Reference Nuclear System Directive: 408 Testing, sections 408.9 and 408.10) 5.7 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-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 purposes. In such cases, the licensee will not be obligated to submit Relief Requests or Justification for C Deferrals. The licensee may opt to trend the performance of such components as is required for components that meet the scope of OM-6.

5.8 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 criterio will be at the discretion of the licensee and may not be part of the test record.

'IST-TAC' may not necessarily be the same acceptance criteria specified in DBDs, DBD associated TAC Sheets, Technical Specifications, or UFSAR. IST TAC are 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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~80 RELIEF REQUESTS The purpose of a Relief Request is to submit a request for NRC rewew and approval of attemative testing to l those requirements of the Code that cannot be followed, if the testing on the component can not be

~

performed due to plant configuration, plant safety, equipment limitations, type, or hazards to personnel, relief from the code wiH be requested. Submitted relief requests win:

1) Give an alternative method that ensures an acceptable level of quality and safety.

2) Explan the hardship with meeting the code requirement.

3) Prowde a schedule or allemative test frequency (or duration for interim Relief i

Request).

Each Ten Year interval, when the site testing program is being upgraded to the new testing requirements, aN relief requests win be rowewed and re-submitted to insure that their reasons for issuance are stiN valid. In cases where a " Specific Relief" was prewously submitted to the NRC and app:wal granted, but the conditions and prowsions do not change (i.e. no code change or modification to equipment or system) to eliminate the relief, the. relief win continue to be applicable the next interval. Relief Requests will not be written for any non-Code Class components that are included in the IST Program at the licensee's discretion.

6.1 Implemenhng Relief Requests:

When a Relief Requests is submitted for those requirements which have been determined to be clearty lir, viscid, the licensee reserves the right to implement the proposed attemative testing while the NRC is reviewing the Relief Request, provided the attemative does not compromise the level of safety provided by the code testing requirement (reference from NUREG-1482, section 2.5).

6.2 Interim Relief Requests:

When a Relief Request is required on an interim basis, the licensee win 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 implementation 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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l 1 7.0 JUSTIFICATIONS FOR DEFERRALS:

Justification for Deferrals (JFDs) will be written when a component can not be tested at the specified code 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 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 I 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 l sufficient duration to complete all tests, testing will start within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of reaching cold shutdown conditions (reference OM-10, section 4.3.2.2, OMa-1988 Addenda), or c) be performed at the next available cold shutdown consistent with the above criteria if an l l opportunity to test the valve is not available. Completion of the IST is not a prerequisite )

i to return to operation.

l Any testing required to be performed during a refueling outage shall be completed prior to plant operation.

I 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 I first available opportunity.

7,1 Testing Deferral Justifications:

7.1.1 Purpose

The purpose of the Justification for Deferral form is to document the reason 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, 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 9.4.

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80 APPENDICES Appendix A: ISTPROGRAM RESPONSIBILITIES 1.0 SITEIST ENGINEER ,

1 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:

e 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, e ensure all IST-TAC is accurate and not in conflict with other specified TAC, e coordinating and implementing the program update and renewal per 10CFR50 every p 10 years.

2.0 GOIST COORDINATOR The General Office (GO) IST Coordinator will be an individual responsible for overall l corporate IST program management. He/she ensures corporate strategin for the IST 1 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 8941, NUREG-1482 etc.).

The GO IST Coordinator is the technical consultant on any Code-related issues that require interpretation or involve Operability determinations (at the discretion of the NT Engineer and site management). The GO IST Coordinator will provide support for intemal and extemalIST program audits.

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

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

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Appendix A: ISTPROGRAM RESPONSIBILITIES (Continued) 2.0 GOIST COORDINATOR-Continued The GO IST Coordinator is responsible for assisting with review and updating the IST program per 10CFR50 each 10-year interval. He/she will assist the sites in preparing, submitting, and reviewing interim revisions to the IST program. The IST Coordinator will assist the site IST Engineer in developing position statements, Relief Requests, and Justification for Deferrals. He/she will perform periodic reviews of site Relief Requests and/or Justification for Deferrals for consistency and compliance.

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 ENGINEERING (MSE)

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

MSE (site) is responsible for the following:

. ensuring the accuracy of IST dataset information, e defining test acceptance criteria (TAC),

e ensuring code testing requirements are met, e documenting reasons for scope or code deviation, O e e

providing tech. assistance for developing test procedures, complete valve and pump data sheets for program revisions, e notifying the IST Engineer of maintenance that could affect the baseline data for any IST component, e overall administration of the relief valve testing program (OM-1),

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

4.0 OPERATIONS PERFORMANCE TEST GROUP (OTG)

This group is responsible for the following:

e input data into procedure and IST Administrator, e performing tests,

. 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.

5.0 OPERATIONS PROCEDURE GROUP This group is responsible for the following:

e updating and maintaining all IST procedures, O- . ' verifying all technical changes with the IST Engineer.

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l Appendix C:

McGUIRE NUCLEAR STATION 10CFR50, Appendix B,- Program Guidance Document 1.0 - SCOPE The Appendix B Program establishes 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 requimments and acceptance limits contained in applicable design documents. 'lhis program shall include the followmg:

. Periodic test during plant operation of structures, systems, and components.

. Trending of test parameters at owner specified fmquencies.

l . Test procedures shall include provisions for assuring that all prerequisites and acceptance criteria

! for the given test have been met. In addition, adequate test insitumentation shall be used and testing performed under suitable environmental conditions (as per 10 CFR 50, App B).

Test frequencies will be as specified in the ASME OM Code unless o'.herwise documented in

l. Section 6.0, " APPENDIX B PR0 GRAM POSITIONS /EXCEFilONS."

Deviations from .' guidelines' will be documented in Section 6.0, " APPENDIX B PROGRAM POSITIONS /EXCEFFIONS."

O 2.0 PuMe ^ND vAtvE TEST SELECTION CR1TER1A The pumps and valves in this program shall be limited to those pumps and valves not covered in the scope of ASME Section XI or ASME OM Code.

3.0 PROGRAM ELEMENTS l Pump and Valve Selection - This task involves identifying all components that fall within the I

scope of 10 CFR Part 50, Appendix B scope.

l l Testing Support - Develop acceptance criteria, necessary test procedures, and establish the correct l . frequencies for performing operational tests.

l l

l Demonstrate OperabiHty - Perform base-line testing (if applicable) of components to ensure functionality of the component and to obtain data for future surveillance activities.

Documentation and Trending-l . 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 l

l extent of future testing, MNS ASME In-service Testing Program Page 19 of 30 MNSSCOPE. DOC 12/31/98

' Appendix B: 10CFR50, Progrtm Guid nca De ; mznt - Continued 4.0 PROGRAM ORGANIZATION AND RESPONSIBILITIES General Office IST/Engineerine Coordinator - This is the central corporate engineering support for the Nuclear Generation Department. He/she is responsible for the following:

l l . General direction for program elements.

.. Program oversight and liaison.

l . 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 IST/ Engineering Contact - This is the station engineering support for the Nuclear Generation Department. He/she is responsible for the following:

l . 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 engmeering documents in an auditable format and condition.

. 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.

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Appendix B: 10CFR50, Program Guid:nca DocumInt - Continued 5.0 DEFINITIONS actiw: a valve that must perform a mechanical motion during the course of accomplishing a system safety function.

. passiw: a valve that does not perform a mechanical motion during the course of accomplishing system safety function.

safetv-related: required to mitigate the consequences of an accident, shutdown, or maintain shutdownof thereactor, component: an item in a nuclear power plant such as a vessel, pump, valve, or piping system.

cold shutdown: (see plant technical specifications).

engineering evaluation: an evaluation of indications that exceed allowable acceptance standards to determme if the margins required by .the design specifications and construction code are maintained.

exercisine (of a tw/w): 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 O cvcle.

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 stand &v: (see plant technical specifications).

operational readiness: the ability of a component or system to perform its intended function when required.

owner the organization legally responsible for the operation, maintenance, safety, and power generation of the nuclear power plant.

normal plant overating conditions: the operating conditions during reactor startup, operation at power, hot standby, and reactor shutdown conditions. (Note: test conditions are excluded),

obturator: valve closure member (disk, gate, plug, ball, etc.)

reference tulues: one or more values of test parameters measured or determined when the equipment is known to be operating acceptably.

O MNS ASME In-service Testing Program Page 21 of 30 MNSSCOPE. DOC 12/31/98

)

Appendix B: 10CFR50, Progrrm Guidrnca Docum nt - Continued 6.0 APPENDIX B PROGRAM POSITIONS /EXCEITIONS 6.1 The MNS 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 Deferrais will not be subrnitted for Appendix B components.

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

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.

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Appendix C: NOTIFICATION OF PROGRAM CHANGES The System Engineer shall initiate program changes as changes are made to the respective system, DBDs, or p active / passive valve calculations. Notification of extemal customers (e.g. Regulatory Compliance Group) of such t, changes to the program will occur by issuing the appropriate administrative mechanism (i.e. PIP, Minor Modification Request, etc.).

To ensure Code compliance for the MNS 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, fk>w path, etc.,

e a modification to the component is planned which can/will significantly affect the components baseline TAC.

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9.0 ENCLOSURES

Enclosure 9.1 (RESERVED FOR *REVISlNG THE PROGRAM DOCUMENT *)

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Enclosure 9.2 (RESERVED FOR " PROGRAM BASES PHILOSOPHY")

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Enclo:ure 9.3 McGuire Unit 1 G McGuire Unit 2 V

9eneric Relief Reauest item Number:

Component Number (s):

Flow Diagram (s):

i Function (s):

l lSI Class / Duke Class:

l 1

! Code Category-l Test Requirement (s):

Basis for Relief:

l Code Attemative:

I i

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'dNS ASME in-service Testing Program Page 26 of 30 MNSSCOPE. DOC 12/31/98

Enclosure 94 0 McGuire Unit 1 McGuire Unit 2 3 Justification for Deferral item Number:

Component Number (s):

Flow Diagram (s):

Code Category:

ASME Class: {

Function (s):

Test Requirement:

O BasisforDeferral:

Test Altemative & Frequency-O MNS ASME In-service Testing Program l Page 27 of 30 '

MNSSCOPE. DOC 12/31/98 L

Enclosure 9.5 McGuire Unit 1 O McGuire Unit 2 Specific Relief Reauest item Number:

Component Number (s):

Flow Diagram (s):

Function:

ASME Class:

Code Category:

Test Requirement:

O '

Basis for Relief:

I i

Altemate Testing:

{

O MNS ASME in-service Tessing Program Page 28 of 30 MNSSCOPE. DOC 12/31/98 a

Enclosure 9.6 (O) v Systern Piping Classification Correlation Seismic Normally Duke (1) NRC ANSI Pressure Contains System Safety Quality Duke OA Safety Boundary Seismic Radioactive Piping Related Group Condition Class Code Des. Criteria (6) Intearity Cateaory Material Classification A YES A 1 1 Class 1, ASME Sect.111 YES SC-1 YES B YES B 1 2 Class 2, ASME Sect.111 YES SC-1 YES C YES C 1 3 Class 3, ASME Sect.111 YES SC-1 YES E NO D(3) 2(4) NNS(2) ANSI B31.1.0 NO N/A YES F YES -

(4) NNS(2) ANSI B31.1.0 YES SC-1 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-1 NO NOTES:

(1) Safety Related as used herein is in accordance with 10CFR50 Appendix A General Design Cnteria for Nuclear Power Plants and is applicable to function only; i.e., structures, systems, and components required to function j such that the facility can be operated without undue risk to the health and safety of the public are safety related. i (2) NNS = Non-Nuclear Safety (3) Class E piping is equivalent to NRC Ouality Group D; i.e., the system is designed to normally carry a radioactive j fluid; however, is considered NNS as a component failure would not result in a calculated potential exposure an 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 I 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 establishes an ' effective code date" in accordance with 10CFR50, par. 50.55a for McGuire 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. When 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 i function and requirements. Non-Safety Related HVAC may be assigned QA Condition 4, SC-11 Support i Restraints to preclude adverse interactions with safety related structures, systems, and components. Refer to Duke Nuclear Guide 1.29.

(7) 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.

f3 b

MNS ASME In-service Testing Program Page 29 of 30 MNSSCOPE. DOC 12/31/98 L

Enclocure 9.7 -

- Summary of IST Program Submittal Changes O

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O MNS ASME In-service Testing Program Page 30 of 30 MNSSCOPE. DOC 12/31/98 l i

, ;.1 l- _ _a

McGuire Unit 1 McGuire Unit 2 TABLE OF ABBREVIATIONS

[

Duke System Designed for ANS Safety Valve Class Code Desien Criteria Seismic Loading Q_an a

A Class 1, ASME Section III,1971 Yes 1 B Class 2, ASME Section III,1971 Yes 2 C Class 3, ASME Section III,1971 Yes 3 D Class 2, ASME Section III,1971 No 2 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 -

NNS=Non-Nuclear Safety Numbering Sequence for Relief Request and Justification For Deferral Examples:

RELIEF REQUEST JUSTIFICATION FOR DEFERRAL MC. SRP- VG. 01 MC. VG. 01 SEQUENCE SEQUENCE SYSTEM (N/A if Generic) SYSTEM STATION (SPECIFIC or QENERIC)

RELIEF for (EUMP orXALVE)

STATION bi u

I 12/31/98 SECI1ON 2.0 Rev.25 Page i of 3

~

McGuire Unit 1 McGuire Unit 2 l TABLE OF ABBREVIATIONS b VALVE TYPE Description BA Ball BF Butterfly CK Check CT Control DI Diagram EX Explosive i GB Globe GT Gate KT Kerotest PG Plug PR Pressure Regulating RV Relief SC Stop Check ST Stop SV Solenoid VB Vacuum Breaker i

TEdT TYPE Description O BT New Baseline Test

{'

.CSE Contact System Engineering CVE Contact Valve Engineering CVED Contact Valve Engineering for DP Test Requirements EX Explosive Valve Test ,

FS Full Stroke Exercise Valve To Safety Position (s)

FT

)

Failed To Safe Position '

IS Instrumented Electrical Stroke LJ Irak Rate Test Valve To App J Requirements (s)

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

LTTS leak Test Per Tech Spec Requirements NT No Test Required PI Verify The Valve Remote Position Indication PIS Pre And Post Maintenance Instrumented Electrical Stroke PS Partial Stroke Exercise Valve RV Safety And Relief Valve Test SD Sample Disassembly SFB System Flow Balance SP Special Test For Particular Component Or Situation ST Measure Full Stroke Time Of Valve TTB Torque Test Bench US- _ Functional (Uninstrumented) Stroke Only 12/31/98 SECTION 2.0

)

Rev.25 Page 2 of 3

l McGuira Unit 1 McGuire Unit 2 FREQUENCY Description 2RF Every Other Refueling Outage 2Y Testing Once Every Two Years 6M Tested Every 6 Months CS Tested At Cold Shutdown CSDRF Tested Each Cold S/D And Each RFO ILRT Tested Every ILRT Outage M Tested Once Monthly NA No Specified Test Frequency Notel See Technical Specification Note 2 6 Month, See Technical Specification Note 3 CSD, Hot Tested Prior To LTOP NPT No Periodic Test Required Q Tested Once Quarterly 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 s Outage VV Visual Verification Frequency W Tested Once Weekly Y Tested Once Yearly OM-10 VALVE CATEGORIES Category A leakage is Critical Category B Ieakage is NOT Critical Category C Self Actuating (Checks, Reliefs, Etc.,)

12/31/98 SECTION 2.0 Rev.25 Page 3 of 3 e

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