ML20063A929
| ML20063A929 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 11/01/1993 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20063A918 | List: |
| References | |
| PROC-931101, NUDOCS 9401270154 | |
| Download: ML20063A929 (200) | |
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ATTACHMENT 1 DUKE POWER COMPANY McGUIRE NUCLEAR STATION UNIT 2 Pump and Valve Inservice Testing Program P ADb 0500 369 G PDR 2,
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r DUKE POWER COMPANY McGUIRE NUCLEAR STATION ,
UNIT 2 PUMP INSERVICE TESTING PROGRAM l
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c McGuire UNIT 2 Page 1 of 2 TABLE OF CONTENTS l
- l. Pump inservice Testing Program l.1 Introduction 1-1 ,
1.2 Data Sheets 1 -10 1.3 General Relief Request 1-2 1.4 Specific Relief Request 1 - 11 i
ll. Valve Inservice Testing Program :
, l1.1 introduction 1-1 l1.2 Table of Abbreviations 1-1 II.3 Definitions of Testing Requirements and Attematives 1-2 II.4 System Data Sheets:
Steam Generator Blowdown Recycle . . . .. . . BB 1 - 1 Auxiliary Feedwater.. . . . . .CA1-3 Feedwater . . . . . .CF1-2 Diesel Generator Engine Fuel Oil . . .FD1-1 Refueling Water.. . . . . . .FW1-1 Airlock . . . . . . lA 1 - 1 Component Cooling . . .KC1-5 Diesel Generator Cooling Water.. . .KD1-1 Spent Fuel Cooling System.... . . . . KF 1 - 1 Diesel Lube Oil.. . . . . . . LD 1 - 1 Radiation Monitoring . .. . .MI1-1 Boron Recycle.. . . ..NB1-1 Reactor Coolant. . . .NC1-2 Residual Heat Removal ... .. .. .ND1-1 Ice Condenser Refrigeration.. . . .NF1-1 Safety injection.. . . .NI1-5 Nuclear Sampling.. . . .NM1-2 i
11/1/93
i McGuira UNIT 2 Page 2 of 2 TABLE OF CONTENTS Containment Spray . . .. . .NS1-2 Chemical and Volume Control. . . .NV1-4 Nuclear Service Water.. . . .RN1-4 Containment Ventilation Cooling Water.. . . . ..RV1-1 Main Steam Supply to Auxiliary Equipment / Turbine Exhaust.. .. . . SA 1 - 1 Main Steam... . . .. . . . .. .. .. .SM1-1 Main Steam Vent to Atmosphere.. . . . . . SV 1 - 2 Breathing Air. . . VB 1 - 1 Annulus Ventilation . . . . . VE 1 - 1 ,
Diesel Generator Starting Air.. . .VG1-3 instrument Air.. .. .VI1-2 'i Containment Purge Ventilation . . . VP 1 - 1 Containment Air Release and Addition. . . .VQ1-1 Station Air.. . . VS 1 - 1 Containment Air Return Exchange and Hydrogen Skimmer. . . . VX 1 - 1 Liquid Waste Recycle . . . , WL1 - 1 Diesel Generator Room Sump Pump. . . WN1 - 1 >
Makeup Demineralized Water. . .YM1-1 i
l1.5 General Relief Requests 0 II.6 Specific Relief Requests 1-5
- 11. 7 Justification of Deferral 1 -95 t
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DUKE POWER COMPANY McGUIRE NUCLEAR STATION - UNIT 2 PUMP INSERVICE TESTING PROGRAM ASME OM CODE-1987, OM Part 6 (OMa-1988 Addenda) ,
INTRODUCTION 1
The inservice testing of ASME Code Class 1,2 and 3 pumps provided with an emergency power source will be tested as required by ASME Operations and Maintenance Standards Part 6 (OM-6), OMa-1P88, of the ASME Code for Operation and Maintenance of Nuclear i Power Plants, as referenced in 10CFR50.55a (January 1,1993 Edition), except where j specific written relief nas been granted by the Nuclear Regulatory Commission. The '
effective date of the submittalis March 1,1994.
A description of the Inservice Testing Program, Justification for Testing Deferral, as well as Specific Relief Requests from code requirements determined to be impractical, is i described in the submittal.
NOTES: 1) OMa-1988 Part 6. 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 3 and analyzing the test will be used in place of a signature in the record of tests. Initials shall be construed as signatures to meet ,
the intent of OM-6.
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i 11/1/93 SECTION l.1 1 of 1 1I
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UNIT 2 - McGUIRE NUCLEAR STATION Pump Inservice Testing General Data Code Pump ID. Number Description Class Flow Diagram Applicable Relief Requests Test Frequency Remarks 2CAPU0001 Motor Driven Auxiliary 3 MC-2592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump 2A 2CAPU0002 Motor Driean Auxiliary 3 MC-2592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump 2B 2CAPU0003 Tubine Driven Auxiliary 3 MC-2592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump #2 2FDPU0054 DieselGenerator Fuel 3 MC-2609-3.0 RR-l.3.1, RR-1.4.2 Quarterly NONE Oil Transfer Pump 2A 2FDPUOO55 DieselGenerator Fuel 3 MC-2609-3.1 RR-I.3.1, RR-1.4.2 Quarterly NOI IE Oil Transfer Pump 2B 2KCPU0001 Component Cooling 3 MC-2573-1.0 RR-i.3.1, RR-l.4.3 Quarterly NONE Water Pump 2Al l 2KCPU0002 Component Cooling 3 MC-2573-1.0 RR-l.3.1, RR-l.4.3 Quarterly NONE ,
l Water Pump 2A2 ,
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- j. 2KCPU0003 Component Cooling 3 MC-2573-1.0 . RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 2Bi SECTioN 12 11/1/93 1oF8
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UNIT 2 - McGUIRE NUCLEAR STATION Pump Inservice Testing Specific Data Differential Reference Pump ID. Number Speed inlet Pressure Discharge Pressure Pressuie Vibration Flow Rate Pump Type Revision 2CAPU0001 Not Required RR-l.4.1 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 2CAPU0002 Not Required RR-l.4.1 Meets Code Meets Code RR-1.3.1 Nhets Code Centrifugal Requirements Requirements Requirements 2CAPU0003 Meets Code RR-l.4.1 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements Requirements 2FDPU0054 Not Required RR-l.4.2 RR-i.4.2 RR-l.4.2 RR-l.3.1 RR-l.4.2 Gear Positive Displacement 2FDPUOO55 Not Required RR-l.4.2 RR-l.4.2 RR-l.4.2 RR-l.3.1 RR-l.4.2 Gear Positive Dispiacement 2KCPU0001 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 2KCPU0002 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 2KCPU0003 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements SECTION 1.2 11/1/93 2 OF 8
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UNIT 2 - McGUIRE NUCLEAR STATION Pump Inservice Testing General Data Code Description Class Flow Diagram Applicable Relief Requests Test Frequency Remarks ;
Pump ID. Number 2KCPU0004 Component Cooling 3 MC-2573-1.0 RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 2B2 2 MC-2561-1.0 RR-L3.1, RR-l.4.4 Quarterly- The ND Testing Plan 2NDPU0001 Residual Heat Removal
- Pump 2A Miniflow; meets other code Refueling- requirements unless ,
Full Flow otherwise specified (RR-l.4.4) 2 MC-2561-1.0 RR-l.3.1, RR-L4.4 Quarterly- The ND Testing Plan 2NDPU0002 Residual Heat Removal Pump 2B Miniflow; meets other code Refueling- requirements unless Full Flow otherwise specified.
(RR-L4.4)
Safety injection Pump 2 MC-2562-3.0 RR-l.3.1, RR-l.4.5 Quarterly- The NI Testing Plan 2NIPU0009 2A Miniflow; meets other code Refueling- requirements unless Full Flow otherwise specified. '
(RR-L4.5)
Safety injection Pump 2 MC-2562-3.0 RR-l.3.1, RR-L4.5 Quarterly- The NI Testing Plan 2N!PU0010 2B Miniflow; meets other code Refueling- . requirements unless Full Flow otherwise specified.
(RR-l.4.5) 2NSPU0001 Containment Spray 2 MC-2563-1.0 RR-1.3.1 Quarterly _ NONE Pump 2A SECTioN I.2 3oF8 11/1/93 L___ _ _ _ _ _ _ . . _ _ . _ - - . - ._ - . .-- - - _ - . - _ - ~ . . - . - _ _ _ _ __-___ _ _-o
UNIT 2 - McGUIRE NUCLEAR STATION Pump inservice Testing Specific Data Differential Reference Pump ID. Number Speed inlet Pressure Dischcrge Pressure Pressure Vibration Flow Rote Pump Type Revision 2KCPU0004 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 2NDPU0001 Not Required RR-l.4.4 Meets Code Meets Code RR-l.3.1 RR-l.4.4 Vertical Line Requirements Requirements Shoft Centrifugal 2NDPU0002 Not Required RR-l.4.4 Meets Code Meets Code RR-l.3.1 RR-l.4.4 Vertical Line Requirements Requirements Shaft Centrifugal 2NIPU0009 Not Required RR-l.4.5 Meets Code Meets Code RR-l.3.1 RR-l.4.5 Centrifugal Requirements Requirements 2NIPU0010 Not Required RR-l.4.5 Meets Code Meets Code RR-l.3.1 RR-l.4.5 Centrifugal Requirements Requirements 2NSPU0001 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Vertical une Requirements Requirements Requirements Requirements Shaft Centrifugal i
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UNIT 2 - McGUIRE NUCLEAR STATION Pump Inservice Testing General Data Code Pump ID. Number Description Class Flow Diagram Appfcoble Relief Requests Test Froquency Remarks -
2NSPU0002 Containment Spray 2 MC-2563-1.0 RR-l.3.1 Quarterly NONE Pump 2B 2NVPUOO15 Centrifugal Charging 2 MC-2554-1.0 RR-l.3.1, RR-l.4.6 Quarterly- The NV Testing Plan Pump 2A Miniflow; meets other code Refue!ing- requirements unless otherwise specified.
Full Flow (RR-1.4.6) 2NVPU0016 Centrifugo! Charging 2 MC-2554-1.0 RR-l.3.1, RR-l.4.6 Quarterly- The NV Testing Plan Pump 2B Miniflow; meets other code Refueling- requirements unless Full Flow othenvise specified.
(RR-l.4.6) 2NVPUOO27 Boric Acid Transfer 3 MC-2554-5.0 RR-l.3.1 Quarterly NONE Pumo 2A 2NVPUOO28 Boric Acid Transfer 3 MC-2554-5.0 RR-l.3.1 Quarterly NONE Pump 2B 2RNPU0003 Nuclear Service Water 3 MC-2574-1.1 RR-l.3.1, RR-l.4.7 Quarterly -NONE Pump 2A SECTION t.2 11/1/93 5OF8
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UNIT 2 - McGUIRE NUCLEAR STATION Pump Inservice Testing Specific Data Differential Reference Pump ID. Number Speed inlet Pressure Discharge Pressure Pressure Vibration Flow Rate Pump Type Revision 2NSPU0002 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Vertical Une Requirements Requirements Requirements Requirements Shatt Centrifugal 2NVPU0015 Not Required RR-l.4.6 Meets Code Meets Code RR-l.3.1 RR-l.4.6 Centrifugal Requirements Requirements 2NVPU0016 Not Required RR-l.4.6 Meets Code Meets Code RR-l.3.1 RR-l.4.6 Centrifugoi Requirements Requirements 2NVPU0027 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code . Centrifugal Requirements Requirements Requirements itequirements 2NVPU0028 !!ot Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code - Centrifugal Requirements Requirements Requirements Requirements 2RNPU0003 Not Required Meets Code Meets Code - Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements RR-l.4.7 Requirements l
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l UNIT 2 - McGUIRE NUCLEAR STATION Pump Inservice Testing General Data Code Pump ID. Number Description Class Flow Diogram Applicable Relief Requests Test Frequency Remarks
, 2RNPU0004 Nuclear Sen/ ice Water 3 MC-2574-1.1 RR-1.3.1, RR-l.4.7 Quarterly NONE Pump 2B i
2WNPU0094 Diesel Generator Sump 3 MC-2609-7.0 RR-l.3.1 Two Year Two year frequency Pump 2A2 for dry sump pumps per OMa-1988, Part 6 section 5.5.
2WNPL10096 Diesel Generofor Sump 3 MC-2609-7.0 RR-l.3.1 Two Year Two year frequency Pump 2A3 for dry sump pumps per OMa-1988, Part 6 section 5.5.
2WNPUOO9.5 Diesel Generator Sump 3 MC-2609-7.0 RR-1.3.1 Two Year Two year frequency Pump 2B2 for dry sump pumps per OMa-1988. Part 6 section 5.5.
2WNPUOO97 Diesel Generator Sump 3- MC-2609-7.0 RR-l.3.1 Two Year Two year frequency Pump 2B3 for dry sump pumps per OMa-1988, Part 6 section 5.5.
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UNIT 2 - McGUIRE NUCLEAR STATION Pump Inservice Testing Specific Data Differential Reference Purtp 10. Number Speed iniel Pressure Discharge Pressure Pressure Vibration Flow Rote Pump Type Revision 2RNPU0004 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements RR-IA.7 Requirements 2WNPUOO94 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Vertical Une Requirements Requirements Requirements Requirements Shaft Centrifugal 2WNPUOO96 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Vertical Une Requirements Requirements Requirements Requirements Shaft Centrifugo!
2WNPUOO95 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Vertical Une Requirements Requirements Requirements Requirements Shaft Centrifugal 2WNPU0097 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Vertical Une Requirements Requirements Requirements Requirements Shaft Centrifugal SECTION l.2 11/1/93 8oFB
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INSERT THE FOLLOWING SECTION UNDER TAB:
I.3 UNIT 2
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i General Relief Request l l
RELIEF REQUEST: 1.3.1
- i PUMPS
- All pumps in the Inservice Test Program t
TEST REQUIREMENTS: 1) OMa-1988 Part 6 Section 6.1 (Table 3a) specifies the allowable range ,
for acceptable operation of vibration measurements. i
- 2) OMa-1988 Part 6 Section 4.6.1.1 (Table 1) requires the accuracy of l' vibration amplitude measurements to be +/- 5 % of full scale.
l BASIS FOR RELIEF: 1) Experience has shown that smooth operating pumps (Vr s 0.075 i in/sec) often fall in the alert range of vibration measurement when compared to the acceptance criteria given in OMa-1988 Part 6, Table 3a. The Table included with this relief request allows for acceptable ranges of vibration measurement for this classification of pumps. This proposal provides an acceptable level of quality and safety given the minimum limits.
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- 2) Vibration measurement instrumentation currently in use is digital l instrumentation. Using our preser.t instrumentation and accounting for all ,j instrumentation uncertainties in the calibration process, the requirement l of +/- 5% instrument accuracy cannot be achieved.
ALTERNATE TESTING: In lieu of the vibration specifed in OMa-1988 Part 6 Table 3a, the following ranges shall be used. These ranges are based on current i vibration standards (vibration severity charts).
Acceptable Alert Required 4 Range Range Action Range i
For all pumps when 0 to 0.19 in/sec > 0.19 s 0.45 in/sec > 0.45 in/sec Vr s 0.075 in/sec For centrifugal pumps, s 2.5
- Vr > 2.5
- Vr to 6
- Vr or > 6
- Vr or when Vr > 0.075 in/sec > 0.325 to 0.70 in/sec > 0.70 in/sec For reciprocating pumps, s 2.5
- Vr > 2.5
- Vr to 6
- Vr > 6
- Vr when Vr > 0.075 in/sec For internal gear positive s 2.5
- Vr > 2.5
- Vr to 6
- Vr > 6
- Vr displacement pumps, 11/1/93 SECTION l.3 10F 2 i
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when Vr > 0.075 in/sec RELIEF REQUEST: 1.3.1 (Continued)
In lieu of the vibration instrument accuracy requirements of OMa-1988 Part 6, Table 1, the loop accuracy of vibration measurements will be +/-
6.56 % of reading. This accuracy is based on the Root Sum of Squares method and includes the accuracy of the vibration probe' (+/- 5.0%) and the accuracy of the calibration instrument (+/- 4.25%). This accuracy is the best that can be reasonably obtained from the state of the art instrumentation used.
11/1/93 SECTION 1.3 2OF2
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UNIT 2
McGuire Unit 2 Specific Relief Request RELIEF REQUEST: 1.4.1 PUMPS: 2CAPU0001,2A CA Pump 2CAPU0002,28 CA Pump 2CAPU0003, Unit 2 Turbine Driven CA Pump TEST REQUIREMENT: OMa-1988 Part 6, Section 4.6.1.2.a requires that the full scale range of the instrument shall be three times the reference value or less.
BASIS FOR RELIEF: The installed process instrumentation for the CA pump suction gauge is a -
0-100 psig,0.5 % accuracy. Typical values for the CA suction pressure during the CA pump testing is 20-25 psig; therefore, the process gauge does not meet the three times criteria. The accuracy of the process gauge (0.5 %) is well below the requirements specified in Table ifor pressure instrument accuracy (2 %). The actual reading error at test pressure due to the process instrument accuracy is 2.5 % (0.5
- 100/20).lf a 0-60 psig test instrument is used (which meets the three times criteria) and it has an accuracy of 2 %, then the reading error would be 6 % (2
- 60/20). When the requirements of OMa-1988 Part 6, Section 4.6.1.2.a and Table 1 are combined, the actual instrument error introduced into the test is less than the code allowable (2.5 % vs. 6 %).
Using the process instrument for suction pressure data does not degrade the quality of the test and meets the intent of the instrumentation requirements of the code; just not the .specify range requirements of
- OMa-1988 Part 6 Section 4.6.1.2.a.
ALTERNATE TESTING: The installed process instrumentation will be used to measure CA suction pressure for the 2A CA,2B CA and Unit 2 Turbine Driven CA pump tests.
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11/1/93 SECTION l.4 1 OF 11 l
McGuire Unit 2 Specific Relief Requesj RELIEF REQUEST: 1.4.2 PUMPS: 2FDPU0054,2A D/G Fuel Oil Transfer Pump 2FDPU0055,28 D/G Fuel Oil Transfer Pump TEST REQUIREMENT: Test pumps in accordance with OMa-1988 Part 6, Table 3b BASIS FOR RELIEF: The characteristics of these pumps and system configuration are such that the comparison of discharge pressure to the acceptance criteria in the code places the pumps in constant alert range. Additionally, the flow >
rate evaluation is based on pump performance and derived such that the pump is not constantly in the alert range.
ALTERNATE TESTING: The D/G Fuel Oil Transfer Pumps are internal gear positive displacement ,
pumps. The performance curve for these pumps is relatively flat. -
Capacity of these pumps is independent of discharge pressure when operating properly and below the cracking pressure of the pump internal relief valve. Since discharge pressure can be affected by the differential pressure of the filters downstream of the pumps and other normal
- operating conditions associated with these pumps, discharge pressure will be monitored for information purposes, but it will not be compared to any acceptance criteria. If the discharge pressure were to be compared to the acceptance criteria, due to the previously stated reasons, these pumps would be constantly in the alert range. Pumps will be tested by measuring level rise in the Fuel Oil Day Tank over time and converting the results to a flow in gallons per minute. This method provides a flow rate that meets the instrument accuracy requirements of 2 % (Table 1).
The test flow rate (O) will be compared to acceptance criteria established in accordance with Table 3b except the acceptable range has been widened on the high side and the High Alert Value has been increased.
As a result, the High Required Action Range has also been increased.
The increased acceptance criteria band is to allow for instrument fluctuations. The new limits are:
Acceptable Range: 0.94*Qr to 1.07*Or Low Alert Range: 0.90*Qt to 0.94*Or High Alert Range 1.07*Qr to 1.10*0r Low Required Action Range: < 0.90*Qr High Required Action Range: > 1.10*0r 11/1/93 SECTION l.4 2 OF 11
I McGuire Unit 2 Specific Relief Request RELIEF REQUEST: 1.4.2 (Continued) ,
These pumps are designed to produce a flow rate of 22 gpm. The requirements of the Diesel Generator are approximately 6 gpm. Five vibration points are monitored and trended on the Fuel Oil Transfer Pumps. Acceptance criteria for the vibration points is calculated based on Relief Request 1.3.1. Vibration data is trended on a quarterly basis similar to the flow test results. Any degradation in the performance of the Fuel Oil Transfer pumps will first appear in the vibration data. Also, the Fuel Oil Transfer pumps are conservatively designed in the discharge pressure that can be obtained. The capabilities of the pump are not ' ,
challenged during the quarterly test with respect to discharge pressure.
System limitations restrict the discharge pressure to less than or equal to 55 psig; however, the Fuel Oil Transfer pumps could easily pump against 150 psig.
Since the pumps are installed with considerable safety margin with respect to flow and discharge pressure, the most prudent data to use for trending for pump degradation would be the velocity vibration data. By trending the five velocity vibration data points, the acceptability of the widened High Alert and Required Action ranges for flow are justified. The +
flow ensures system operability is met and the pump internal relief valve is not lifting prematurely while the vibration test ensures an adequate trending program is in place to ensure continued operability during testing intervals. ,
The D/G Fuel Oil Storage Tank is the suction source for the Fuel Oil Transfer pumps and is monitored to maintain level as required by McGuire Technical Specifications. This level ensures adequate NPSH; therefore, a suction pressure reading is not required. ,
in addition, monthly Diesel Generator starting and loading (as required by McGuire Technical Specifications) will assess the hydraulic condition of the subject auxiliary pumps and demonstrates the capability of the individual components to perform their design function.
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11/1/93 SECTION l.4 3 OF 11 l
McGuire Unit 2 Specif.ic Relief Reauest RELIEF REQUEST: 1.4.3 r
PUMPS: 2KCPU0001,2A1 Component Cooling Water Pump 2KCPU0002,2A2 Component Cooling Water Pump 2KCPU0003,2B1 Component Cooling Water Pump 2KCPU0004,2B2 Component Cooling Water Pump TEST REQUIREMENT: OMa-1988 Part 6, Section 4.6.1.2.a requires that the full scale range of the instrument shall be three times the reference value or less.
! I BASIS FOR HEi.iEF: The installed process instrumentation for the KC pump suction gauge is a -
0-60 psig,0.5 % accuracy. Typical values for the KC suction pressure during the KC pump testing is 15-20 psig; therefore, the process gauge does not meet the three times criteria. The accuracy of the process l gauge (0.5 %) is well below the requirements specified in Table 1for pressure instrument accuracy (2 %). The actual reading error at test pressure due to the process instrument accuracy is 2 % (0.5
- 60/15).lf a 0-45 psig test instrument is used (which meets the three times criteria) and it has an accuracy of 2 %, then the reading error would be 6 % (2
- 45/15). When the requirements of OMa-1988 Part 6, Section 4.6.1.2.a l and Table 1 are combined, the actual instrument error introduced into the l
test is less than the code allowable (2 % vs. 6 %). Using the process instrument for suction pressure data does not degrade the quality of the test and meets the intent of the instrumentation requirements of the code; just not the specify range requirements of OMa 1988 Part 6 Section 4.6.1.2.a.
r ALTERNATE TESTING: The installed process instrumentation will be used to measure KC suction pressure for the 2A1,2A2,2B1, and 2B2 KC pump tests.
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l 11/1/93 SECTION 1.4 4 OF 11 t
i McGuire Unit 2 Specific Relief Request RELIEF REQUEST: 1.4.4 PUMPS: 2NDPU0001,2A Residual Heat Removal Pump 2NDPU0002,2B Residual Heat Removal Pump TEST REQUIREMENT: 1) OMa-1988 Part 6, Section 5.2.b requires the resistance of the system to be varied until either the measured differential pressure or the measured flow rate equals the reference value.
- 2) OMa-1988 Part 6, Section 4.6.1.2.a specifies the range of each instrument shah be three times the reference value or less.
BASIS FOR RELIEF: 1) When testing these pumps on line, the only flow path available is through the miniflow control valve in the line, which yields a test point back on the head curve. As stated in Generic Letter 89-04, minimum flow lines are not designed for pump testing purposes. The test point for monitoring pump performance for degradation should be in a more stable region on the pump performance curve. Also, the amount of time the pump is run at miniflow should be minimized.
- 2) Also, range requirements will be waived for the quarterly test. The purpose of the quarterly is to verify Tech Spec requirements are met and to obtain vibration data for trending. The instrumentation used for the quarterly Residual Heat Removal Pump test will meet accuracy requirements for assuring Residual Heat Removal Pump operability per Technical Specifications.
ALTERNATE TESTING: The Residual Heat Removal Pumps will be tested according to the following program, which is consistent with Generic Letter 89-04.
Quarterlv The Residual Heat Removal Pumps will be tested quarterly to verify ;
Technical Specifications are met. The test measures differential ;
pressure and velocity vibration data. The differential pressure and j velocity vibration data will be trended. The instrumentation range I requirements of OMa-1988 Part 6, Section 4.6.1.2.a will be waived. The i instrumentation used to measure suction and discharge pressure will I meet applicable accuracy requirements for the determination of l operability per Technical Specifications. The instrument used to measure vibrations will meet the requirements specified in relief request 1.3.1. The j test loop used in the test has a flow measuring orifice installed, however, the system resistance cannot be adjusted with the associated throttling valve without invalidating the Residual Heat Removal system flow balance (a Tech Spec balance of flow to all 4 cold legs.) Therefore, flow through this loop will be recorded for information only.
11/1/93 SECTION L4 5 OF 11
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McGuire Unit 2 Specific Relief Request RELIEF REQUEST: 1.4.4 (Continued)
Befuelina Outace During each refueling outage, a code pump test - including velocity vibration measurements - will be performed at a test point in the stable region of the performance curve.
As an alternative to repeat testing at a single test point in the stable region, a reference curve may be obtained with applicable acceptance curves plotted. Using this technique, the full flow test point (also in the stable region of the pump curve) will be bound by flow points obtained in the development of the reference curve. The data obtained is then evaluated against acceptance criteria and Chapter 15 basis acceptance curves to verify pump operability. When baseline vibration data varies significantly over the pump head curve, vibration acceptance criteria will be developed for flow regions of the head curve.
The test method selected will depend on plant refueling conditions, maintenance performed on the pump, and the quantity of pump data required. Either method selected will ensure that the pump is tested in the full flow region of the head curve and that system operability is verified. Each test methodology is consistent with the intent of Code requirements and Generic Letter 89-04.
11/1/93 SECTION l.4 6 0F 11
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l McGuire thit 2 Specific Relief Requ_qs1 RELIEF REQUEST: 1.4.5 i
PUMPS: 2NIPU0009,2A Safety injection Pump 2NIPU0010,2B Safety injection Pump ;
TEST REQUIREMENT: 1) OMa-1988 Part 6 Section 5.2.b requires the resistance of the system to be varied until either the measured differential pressure or the measured flow rate equals the reference value.
- 2) OMa-1988 Part 6, Section 4.6.1.2.a specifies the range of each ,
instrument shall be three times the reference value or less.
BASIS FOR RELIEF: 1) When testing these pumps on line, the only flow path available is through the miniflow line which has a flow restricting orifice. The orifice yields a test point back on the head curve. As stated in Generic Letter ,
89-04, minimum flow lines are not designed for pump testing purposes.
The test point for monitoring pump performance for degradation should be in a more stable region on the pump performance curve. Also, the amount of time the pump is run at miniflow should be minimized.
- 2) Also, range requirements will be waived for the quarterly test. The purpose of the quarterly is to verify Tech Spec requirements are met and to obtain vibration data for trending. The instrumentation used for the quarterly Safety Injection Pump test will meet accuracy requirements for assuring Safety injection Pump operability per Technical Specifications. .
ALTERNATE TESTING: The Safety injection Pumps will be tested according to the following program, which is consistent with Generic Letter 89-04, Quarteriv l The Safety injection Pumps will be tested quarterly to veriry Technical Specifications are met. The test measures differential pressure and velocity vibration data. The differential pressure and velocity vibration data will be trended. The instrumentation range requirements of OMa-1988 Part 6, Section 4.6.1.2.a will be waived. The instrumentation used to measure suction and discharge pressure will meet applicable accuracy requirements for the determination of operability per Technical Specifications. The instrument used to measure vibrations will meet the requirements specified in relief request 1.3.1. The test loop has a flow measuring orifice installed, however, there is no means provided to vary the system resistance to set either the flow or differential pressure.
Therefore, flow through this loop will be recorded for information only.
RELIEF REQUEST: 1.4.5 (Continued) -
11/1/93 SECTION I.4 !
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McGuire Unit 2
.Saecific Relief Request Refueling Outagg During each refueling outage, a code pump - including velocity vibration measurements - will be performed at a test point in the stable region of the performance curve.
As an alternative to repeat testing at a single test point in the stable region, a reference curve may be obtained with applicable acceptance ,
curves plotted. Using this technique, the full flow test point (also in the stable region of the pump curve) will be bound by flow points obtained in the development of the reference curve. The data obtained is then evaluated against acceptance criteria and Chapter 15 basis acceptance curves to verify pump operability. When baseline vibration data varies significantly over the pump head curve, vibration acceptance criteria will be developed for flow regions of the head curve.
The test method selected will depend on plant refueling conditions, maintenance performed on the pump, and the quantity of pump data required. Each method selected will ensure that the pump is tested in the full flow region of the head curve and that system operability is verified.
Each tet,t methodology is consistent with the intent of Code requirements and Generic Letter 89-04.
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McGuire Unit 2 Specific Relief Request-RELIEF REQUEST: 1.4.6 -
PUMPS: 2NVPUOO15,2A Centrifugal Charging Pump 2NVPU0016,2B Centrifugal Charging Pump TEST REQUIREMENT: 1) OMa-1988 Part 6, Section 5.2.b requires the resistance of the system to be varied until either the measured differential pressure or the measured flow rate equals the reference value.
- 2) OMa-1988 Part 6, Section 4.6.1.2.a specifies the range of each ,
instrument shall be three times the reference value or less.
i BASIS FOR RELIEF: 1) When testing these pumps on line, the only flow path available is ,
through a combination of the normal charging line and the miniflow line to the Volume Control Tank. This test yields a test point back on the head curve. As stated in Generic Letter 89-04, the test point fer monitoring pump performance for degradation should be in a more stable region on the pump performance curve. Also, the miniflow is not instrumented for flow. The flow through the line is assumed to be at the flow rate corresponding to the orifice design conditions.
- 2) Also, range requirements will be waived for the quarterly test. The -
purpom of the quarterly is to verify Tech Spec requirements are met and to obtain vibration data for trending. The instrumentation used for the quarterly Centrifugal Charging Pump test will meet accuracy requirements for assuring Centrifugal Charging Pump operability per Technical Specifications.
ALTERNATE TESTING: The Centrifugal Charging Pumps will be tested according to the following program, which is consistent with Generic Letter 89-04.
Quarterly The Centrifugal Charging Pumps will be tested quarterly to verify Technical Specifications are met. The test measures differential -
pressure and velocity vibration data. The bifferential pressure and velocity vibration data will be trended. The tr.strumentation range requirements of0Ma-1988 Part 6, Section 4.6.1.2.a will be waiv ed. The instrumentation used to measure suction and discharge pressure will ;
meet applicable accuracy requirements for the determination of .
operability per Technical Specifications. The instrument used to measure vibrations will meet the requirements specified in relief request 1.3.1. The flow through the rniniflow line to the Volume Control Tank will be assumed to be constant at the orifice design conditions (60 gpm).
11/1/93 SECTION 1.4 9 OF 11
McGuire Unit 2 Specific Relief Reauest RELIEF REQUEST: 1.4.6 (Continued)
Refuelina Outaae During each refueling outage, a code pump - including velocity vibration -
measurements - will be performed at a test point in the stable region of the performance curve.
As an alternative to repeat testing at a single test point in the stable region, a reference curve may be obtained with applicable acceptance curves plotted. Using this technique, the full flow test point (also in the stable region of the pump curve) will be bound by flow points obtained in the development of the reference curve. The data obtained is then evaluated against acceptance criteria and Chapter 15 basis acceptance curves to verify pump operability. When baseline vibration data varies significantly over the pump head curve, vibration acceptance criteria will be developed for flow regions of the head curve.
The test method selected will depend on plant refueling conditions, maintenance performed on the pump, and the quantity of pump data required. Each method however will ensure that the pump is tested in the full flow region of the head curve and that system operability,is verified.
Each test methodology is consistent with the intent of Code requirements and Generic Letter 89-04, 11/1/93 SECTION I.4 10 OF 11
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McGuire Unit 2 Specific Relief Request RELIEF REQUEST: 1.4.7 i
PUMPS: 2RNPU0003,2A Nuclear Service Water Pump 2RNPU0004,2B Nuclear Service Water Pump TEST REQUIREMENT: OMa-1988 Part 6, Section 4.6.1.6 requires the frequency response range of the vibration measuring transducers to be from one-third minimum pump shaft rotational speed to at least 1000 Hz.
BASIS FOR RELIEF: The Nuclear Service Water pumps are designed to operate at 1185 rpm.
This speed yields a frequency of 19.75 Hz (1185/60). The vibration instrumentation used cannot be calibrated M th s required one-third minimum shaft speed of 6.58 Hz (19.75/3).
ALTERNATE TESTING: in lieu of OMa-1988 Part 6 Section 4.6.1.6, the vibration instrumentation will be calibrated over a range of 10 to 1000 Hz. This calibration range encompasses most of the noise contributors, and repeatability within this range is very good. Accuracy of measurement within this range is addressed in relief request 1.3.1.
e 7
f 11/1/93 SECTION 1.4 11 OF 11
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DUKE POWER COMPANY McGUIRE NUCLEAR STATION a
UNIT 2 VALVE INSERVICE TESTING PROGRAM 1
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11.1 r
UNIT 2
McGuire Unit 2 DUKE POWER COMPANY McGUIRE NUCLEAR STATION - UNIT 2 VALVE INSERVICE TESTING PROGRAM INTRODUCTION The inservice testing of ASME Code Categories A. B. C and D will be performed as required by ASME OM-Code-1987, Part 10 OMa-1988 addenda included, (Inservice Testing of Valves in Light-Water Reactor Power Plants), as incorporated in 10CFR50.55a. These rules for IST were instituted by 1989 edition of ASME Section XI and will be adhered to, except where specific written relief has been granted by the Commission. The effective date for this ten year submittalis March 1,1994, NOTES: 1) The dated initials of the person responsible for the action may be used in place of a signature in the record of tests. Initials shall be construed as signatures to meet the intent of OMa-1988, Section 6.3.
- 2) Category A and A/C valves include containment isolation valves (CIV) and pressure isolation valves (PlV). CIVs are leak tested in accordance with 10CFR50, Appendix J, and Section 4.2.2.3, unless specific relief is requested.
- 3) Generic Letter 89-04, provides guidance for sample disassembly of check valves as an altemative to verify operability of check valves. The check valves where sample disassembly will be utilized will be specifically referenced in the contents of the
- submittal and performed according to the guidelines of Generic Letter 89-04.
t 11/1/93 SECTION l1.1 1 of 1 .i
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II.2 i
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TABLEOF ABBREVIATIONS ANS l Duke System Designed for Safety l Valve Class C,rde Desien Criteria Seismic Loadine Class A Class 1, ASME Section Ill,1971 Yes 1 1 B Class 2, ASME Section III,1971 Yes 2 l
C Class 3, ASME Section III,1971 Yes 3 l l
D Class 2, ASME Section III,1971 No 2 l E ANSI B31.1.0 (1967) No NSS I
F ANSI B31.1.0 (1967) Yes NSS G ANSI B31.1.0 (1967) No -
l H Duke Power Company Specification No --
LEGEND CAT - Category . PC - Procedure Check CIV - Containment Isolation Valve PIV - Pressure Isolation Valve CL - Class Q - Quarterly CS - Cold Shutdown RF - Refueling Outage FS - Fail Safe RR - Relief Request LT - Leak Test SD - Sample Disassembly MTC - Movement Test Closed SP - Setpoint MTO - Movement Test Open ST - Stroke Time (cycle and time)
MTO.C - Movement Test Open and Closed TS - Technical Specification ,
l RELIEF REOUEST JUSTIFICATION OF DEFERRAL 2- MC- RR - VG - 1 2- MC - CA 1 i
l SEQUENCE l SEQUENCE SYSTEM j RELIEF REQUEST STATION STATION UNIT UNIT 11/1/93 SECTION 11.2 1OF1
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II.3 UNIT 2 1
McGuire Unit 2 DUKE POWER COMPANY McGUlRE NUCLEAR STATION - UNIT 1 DEFINITION OF TESTING REQUIREMENTS AND ALTERNATIVES Cold Shutdown (CS) Testing will be performed when the unit is entering, during or recovering from a cold shutdown of sufficient duration to establish necessary test conditions. In the case of frequent shutdowns, the testing will not be performed more than once per three (3) months. Testing will commence as soon as the cold shutdown condition is achieved but not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown, and continue until complete or the plant is ready to return to power. Completion of all valve testing is not a prerequisite to return to power. Any testing not completed at one cold shutdown will be performed during any subsequent cold shutdowns that may occur before refueling to meet the code specified testing frequency. Any valve speci-fied to be tested during Cold Shutdown (CS) may be tested during Refueling Outage (RF) conditions.
Stroke Time (SJJ Valve will be tested to verify that its stroke time is less than or equal to the maximum allowable stroke time specified by McGuire Nuclear Station. Stroke time is defined as the time interval from initiation of the actuating signal to the limit switch at the end of the actuating cycle.
Leak Test (LT) Valve will be tested to verify that the seat leakage is limited to a specific maximum amount.
Movement Tests (MT) Valve will be tested to verify that the valve is operable and capable of ful-filling its intended purpose. No timing is involved. Movement tests will be performed by passing full accident flow through the valve, acoustic emission monitoring of the disc in either the open or closed position, leak testing to verify closure, sample disassembly, or other NRC accepted rneans.
Quarteriv (Q1 Testing will be performed at least once per three months.
11/1/93 SECTION 11.3 1OF2
i McGuire Unit 2 -
D Refueling Outage (RF) Testing will be performed when the unit is shut down for refueling. Test-ing may be done while in No Mode as well as Modes 3,4,5 and 6. j Refueling Outage (RF*) Valve will normally be tested during refueling outages, not to exceed 24 months per Appendix J to 10CFR50.
Refuelino Outage (RF#) Valve will normally be tested on a routine basis via a sample valve disassemble program (1 valve from a group of identical valves under similar conditions). Failure of one valve of the group during a refueling outage will result in all remaining valves of the group being tested during that outage.
Setooint (SP) Valve will be tested to verify that it will relieve pressure at its specified l setpoint. Testing will be performed per the requirements of IWV-3510.
]
i Failsafe (FS) Valve will be tested to verify it will reposition to its design safe position upon loss of control air per IWV-3415. j l
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Eaniya Valve does not perform a mechanical motion during the course of accom-plishing a system safety function. (IWA-9000) j i
11/1/93 SECTION 11.3 2OF2
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Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT *1 REQ'MT #2 REQST DETERRAL REMARKS ALTERNAllVES REV STEAM GENERATOR BLOWDOWN RECYCLE (BB) 2BB-0001B 2580-1.0 H-02 2 B ACT Gate AOV ST-O - - - - - -
2BB-0001B 2580-1.0 H44 2 B ACT Gate AOV ST-O - - - - - -
2BB-00028 2580-1.0 H-12 2 8 ACT Gate AOV ST-O - - - - - -
288-0004B 2580-1.0 H 10 2 B ACT Gate AOV ST-O - - - - - -
2BB-0005A 2580-1.0 F-02 2 B ACT Gate AOV ST-O - - - - - -
2BB-0006A 2580-1 0 F-04 2 B ACT Gate AOV ST-O - - - - - -
2BB-0007A 2580-1.0 F-12 2 B ACT Gate AOV ST-O - - - - - -
2BB-0008A 2580-1.0 F-10 2 B ACT Gate AOV ST-O - - - - - -
l 11/1/93 BB - 1 of 1
i Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW . FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUST!F OF TEST VALVE NUMitER DIAGRAM COOR CLASS CATEGORY - PAS TYPE TTTE REQMT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV AUXILIARY FEEDWATER (CA) 2CA-0007AC 2592-1.1 B-10 3 8 ACT Gate EMO ST-O - - - - - -
2CA-0008 2592-1.1 B-11 3 C ACT Check -
MTC-O - -
2-MC-CA3 -
2CA-0009B 2592-1.1 C-OS 3 B ACT Gate EMO ST-O - - - - - -
2CA-0010 2592-1.1 C-05 3 C ACT Check -
MTC-Q - -
2-MC-CA3 - - -
2CA-0011 A 2592-1.1 0-04 3 B ACT Gate EMO ST-O - - - - - -
2CA-0012 2592-1.1 B-03 3 C ACT Check -
MTC-O - -
2-MC-CA3 - - -
2CA-0015A 2592-1.1 D-03 3 B ACT Gate EMO ST-O - - - - - -
2CA-00188 2592-1.1 D-03 3 B ACT Gate EMO ST-O - - - - - -
2CA-0020AB 2592-1.1 1-10 3 AC ACT Control AOV ST-O LT - - - - -
2CA-0022 2592-1.1 1-10 3 C ACT Check -
MTO-O - - - - - -
2CA-0026 2592-1.1 1-04 3 C ACT Check -
MTO-O - - - - - -
2CA-0027A 2592-1.1 J45 3 AC ACT Control AOV ST-O LT - - - - -
2CA-0031 2592-1.1 1-07 3 C ACT Check -
MTO-O - - - - - -
2CA-0032B 2592-1.1 1-08 3 AC ACT Control AOV ST-O LT - - - - -
2CA-0036AB 2592-1.0 L-10 3 B ACT Control AOV ST-O - - - - - -
2CA-0037 2592-1.0 K-14 2 C ACT Check -
MTO.C-Q - -
2 MC-CA1 - - -
2CA-0038B 2592-1.0 J-14 2 B ACT Gate EMO ST-O - - - - - -
11/1/93 CA- 1 of 3 s-
s Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JL*STiF OF TT5T VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYPE TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVE.5 REV AUXILIARY FEEDWATER (CA) 2CA-0040B 2592-1,0 G-14 3 B ACT Controi AOV ST-Q - - - - - -
- 2CA-0041 2592-1.0 H-14 2 C ACT Check - MTO,C-Q - -
2-MC-CA1 - - -
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, 2CA-0042B 2592-1.0 1-14 2 B ACT Gate EMO ST-O - - - - - -
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! 2CA-00448 2592-1.0 C-11 3 B ACT Control AOV ST-Q - - - - - -
l 2CA-0045 2592-1.0 C-09 2 C ACT Check - MTO,C-O - -
2-MC-CA1 - - -
2CA-0046B 2592-1.0 D-08 2 B ACT Gate EMO ST-Q - - - - - -
2CA-0048AB 2592-1.0 K-08 3 B ACT Control AOV ST-O - - - - - -
2CA-0049 2592-1.0 H-08 2 C ACT Check -
MTO.C-Q - -
2-MC-CA1 - - -
2CA-00508 2592-1.0 G-08 2 B ACT Gate EMO ST-O - - - - - -
2CA-0052AB 2592-1,0 K-07 3 B ACT Control AOV ST-Q - - - - - -
j 2CA-0053 2592-1.0 H-07 -2 C ACT Check -
MTO.C-O - -
2-MC-CA1 - - -
l 2CA-0054AC 2592-1.0 G-07 2 B ACT Gate EMO ST-O - - - - - -
1 2CA-0056A 2592-1.0 C-04 3 0 ACT Control AOV ST-O - - - - - -
2CA-0057 2592-1.0 C-06 2 C ACT Check - MTO,C-O - -
2-MC-CA1 - - .
2CA-0058A 2592-1.0 D-07 2 B ACT Gate EMO ST-Q - - - - - -
2CA-0060A 2592-1.0 G-01 3 -B ACT Control AOV ST-Q - - - - - -
2CA-0061 2592-1.0 H-01 2 C ACT Check - MTO,C-O - -
2-MC-CA1 - - -
11/1/93 ' CA - 2 of 3 -
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Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACFUATOR TEST TEST REUEF JLSTIFOF TEST VALVE NUMBER DIAGRAM COCR CLASS CATEGORY PAS TYPE TWE REQ'MT *1 REQ ~MT #2 REQST DEFERRAL REMARKS ' ALTERNATIVES REV AUXIUARY FEEDWATER (CA) 2CA-0062A 2592-1.0 1-01 2 B ACT Gate EMO ST-O - - - - - -
2CA-0064AB 2592-1.0 L-04 3 B ACT Control AOV ST-C - - - - - -
2CA-0065 2592-1.0 K41 2 C ACT Check - MTO,C-Q - - -
2-MC-CA1 - - -
2CA-0066AC '2592-1.0 J-01 2 B ACT Gate EMO ST-O - - - - - -
2CA-0086A 2592-1.1 C-14 3 B ACT Gate EMO ST-O - - - - - -
2CA-0116B 2592-1.1 G-14 3 B ACT Gate EMO ST-O - - - - - -
2CA-0128 2592-1.1 H-13 3 C ACT Relief -
SP - - - -
135 PSIG -
2CA-0165 2592-1.1 C-14 3 C ACT Check -
MTO.C-O - -
2-MC-CA2 - - -
2CA-0166 2592-1,1- G-14 3 C ACT Check - MTO,C-Q - -
2-MC-CA2 - - -
2CA-0167 2592-1.1 H-02 3 C ACT Rehef -
SP - - - -
135 PSIG -
- 2CA-0168 2592-1.1 H-05 3 C ACT Relief -
SP - - - -
135 PSIG -
11/1/93 CA - 3 of 3
Unit 2 - McGuire Nuclect Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ MT #1 REQ'MT 82 REQST DEFERRAL REMARKS ALTERNATIVES REV FEEDWATER (CF) 2CF-0017AB 2591-1.1 K-03 CLASS F A A S O - -
2MCF2 - - -
2CF-0020AB 2591-1.1 K-06 B ACT Globe AOV ST-O - -
2-MC-CF2 - - -
C SS F KE 2CF-0023AB 2591-1.1 K-09 gg B ACT Globe AOV ST-O - -
2-MC-CF2 - - -
C 2CF-0026AB 2591-1.1 H-03 2 B ACT Gate ST-O - -
2-MC-CF1 - - -
2CF-0028AB 2591-1.1 H46 2 B ACT Gate g , ST-O - -
2-MC-CF1 - - -
2CF-0030AB 2591-1.1 H-09 2 B ACT Gate ST-O - -
2-MC-CF1 - - -
2CF-0032AB 2591-1.1 K-13 B ACT Globe AOV ST-O - -
2-MC-CF2 - - -
C SS F E
2CF-0035AB 2591-1.1 H-13 2 B ACT Gate g. ST-O - -
2-MC-CF1 - - -
2CF-0104AB 2591-1.1 K-12 B ACT Control AOV ST-O - -
2-MC-CF4 - - -
C SF 2CF-0105AB 2591-1.1 K-09 C SF A ri A - -
2WCG - - -
2CF-0106AB 2591-1.1 K-05 gg p B ACT Control AOV ST-O - -
2-MC-CF4 - - -
2CF-0107AB 2591-1.1 K-02 B ACT Control AOV ST-O - -
2-MC-CF4 - - -
SF 2CF-0126B 2591-1.1 H-11 2. B ACT Gate EMO ST-O - -
2-MC-CF3 - - -
2CF-0127B 2591-1.1 H48 2 B ACT Gate EMO ST-O - -
2-MC-CF3 - - -
2CF-01288 2591-1.1 H-04 2 B ACT Gate EMO ST-O - -
2-MC-CF3 - - -
2CF-01298 2591-1.1 H-01 2 B ACT Gate EMO ST-Q - -
2-MC-CF3 - - -
2CF-0134A 2591-1,1 H-12 2 B ACT Kerotest EMO ST-O - - - - - -
l 11/1/93 CF - 1 of 2 i-
.q Unit 2 - McGuire Nuclear Station Inservice Testing Program 110W FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TEST VALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ 1tT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVT.S REV FEEDWATER (CF) 2CF-0135A 2591-1.1 G-09 2 B ACT Kerotest EMO ST-O - - - - - -
2CF-0136A 2591-1.1 G-05 2 B ACT Kerotest EMO ST-Q - - - - - -
2CF-0137A 2591-1.1 G-02 2 B ACT Kerotest EMO ST-O - - - - - -
2CF-0151B 2591-1.1 G-12 2 B ACT Gate EMO ST-Q - - - - - -
2CF-0152 2591-1.1 F-12 2 C ACT Check -
MTC-O - -
2-MC-CF5 - - -
2CF-0153B 2591-1.1 G-11 2 B ACT Gate EMO ST-O - - - - - -
2CF-0154 2591-1.1 F-11 2 C ACT Check -
MTC-O - -
2-MC-CF5 - - -
2CF-0155B 2591-1.1 G-11 2 B ACT Gate EMO ST-O - - - - - -
2CF-0156 2591-1.1 F-10 2 C ACT Check -
MTC-Q - -
2-MC-CF5 -- - -
2CF-01578 2591-1.1 G-12 2 B ACT Gate EMO ST-O - - - - - -
2CF-0158 2591-1.1 F-12 2 C ACT Check -
MTC-O - -
2-MC-CF5 - - -
11/1/93 CF - 2 of 2
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Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DLAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ 1tT#1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV DIESEL GENERATOR ENGINE FUEL OIL (FD) 2FD-0005 2609-3.0 E-03 3 C ACT Relief -
SP - - - -
50 PSIG -
2FD-0013 2609-3.0 D-13 3 C ACT Retief -
SP - - - -
50 PS!G -
2FD-0016 2609-3.0 H-14 3 C ACT Check -
MTO C-O - - - - - -
2FD-0018 2609-3.1 1-10 3 C ACT Relief -
SP - - - - '
RESSU E 2FD4028 2609-3.1 E-02 3 C ACT Relief -
SP - - - -
50 PSIG -
2FD-0036 2609-3,1 E-14 3 C ACT Relief -
SP - - - -
50 PSIG -
2FD-0039 2609-3.1 H-14 3 C ACT Check -
MTO.C-O - - - - - -
2FD-0041 2609-3.1 1-10 3 C ACT Relief -
SP - - - - '
RESS E 2FD-0083 2609-3.0 D-02 3 C- ACT Relief -
SP - - - -
10 PSIG -
2FD-0092 2609-3.0 E-13 3 C ACT Check -
MTO.C-O - - - - - -
4 2FD-0093 2609-3.0 J-14 3 C ACT Check - MTO,C-O - - - - - -
2FD-0096 2609-3.1 D-02 3 C ACT Refief -
SP - - - -
10 PSIG -
2FD-0104 2609-3.1 E-13 3 C ACT Check -
MTO.C-O - - - - - -
2FD-0105 2609-3.1 J-14 3 ~C ACT Check - MTO,C-O - - - - - -
11/1/93 FD- 1 of 1
Unit 2 McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUST1F OF TEST VALVE NUMEER UtAGRAM COOR CLASS CATEGORY PAS TYPE TITE REQ'MT al REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV 35UELING WATER (FW) 2FW-0001 A 2571-1.0 E-11 2 B ACT Gate EMO ST-Q - - - - - -
2FW-0004 2571-1.0 D-08 2 A PAS Gate -
LT-RF - - - ' ~
C 2FW-0005 2571-1.0 C-07 2 A PAS Check -
LT.RF - - - - - -
2FW-0011 2571-1.0 C-02 2 A PAS Diaphram -
LT-RF - - - ' ~
C 2FW-0013 2571-1.0 D42 2 A PAS Diaphram -
LT-RF - - -
O 2FW-0027A 2571-1.0 C-12 2 B ACT Gate EMO ST-O - -
2-MC-FW1 - - -
2FW-0028 2571-1.0 B-11 2 C ACT Check -
MTO.C-O - -
2-MC-FW2 - - -
i 2FW-0032B 2571-1.0 E-11 2 B ACT Gate EMO ST-Q - - - -- - -
2FW-0033A 2571-1.0 F-11 2 B ACT Kerotest EMO ST-O - - - - - -
2FW-0049B 2571-1.0 F-10 2 B ACT Kerotest EMO ST-O - - - - - -
2FW-0052 2571-1.0 1-05 ^ ' ' ' ' ' ' ' '
CLASS E 2FW-0063 2571-1.0 C-03 2 A PAS Check -
LT-RF - - - - - -
' 2FW-0074 2571-1.0 J-14 3 C ACT Check -
MTC-Q - - - - - -
11/1/93 FW 1 of 1 l - - , . . . , , , , . . . _ , __ . . .
Unit 2 - McGuiro Nuclear Station bservice Testmg Prograrn FIDW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS T)TE TYPE REQMT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV AIRLOCK (IA) 21A-5080 2499-IA1 N/A 2 A ACT Solenoid SOV ST-O LT-RF - - - - -
- 21 A-5160 2499-IA1 N/A 2 A ACT Solenoid SOV ST-Q LT-RF - - - - -
2tA-5260 2499-1A1 N/A 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-IA1 - - -
21A-5270 2499-IA1 N/A 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-IA1 - - -
2tA-5280 2499-IA1 N/A 2 AC ACT Check -
MTC-O LT-RF -
2-MC-IA1 - - -
21A-5290 2499-IA1 N/A 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-IA1 - - -
2fA-5300 2499IA1 N/A 2 AC ACT Check -
MTC-O LT-RF -
2-MC-IA1 - - -
21A-5310 2499-IA1 N/A 2 AC ACT Check -
MTC-O LT-RF - 2-MC-IA1 - - -
2iA-5320 2499-IA1 N/A 2 AC ACT Check -
MTC-O LT-RF -
2-MC-IA1 -. - -
2M-5330 2499-IA1 N/A 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-!A1 - - -
21A 5340 2499-IA1 N/A' 2 AC ACT Check -
MTC-O LT-RF -
2-MC-IA1 - - -
21A-5350 2499-IA1 N/A 2 AC ACT Check -
MTC-O LT-RF -
2-MC-IA1 - - -
2iA-5360 2499-IA1 N/A ~3 AC ACT Check -
MTC-O LT-RF -
2-MC-IA1 - - -
21A-5370 2499-IA1 N/A 3 AC ACT Check -
MTC-O LT-RF -
2-MC-IA1 - - -
21A-5380 2499-IA1 N/A 3 AC ACT Check -
MTC-O LT-RF -
2-MC-lA1 - - -
21A-5390 2499-1A1 N/A 3 AC ACT Check - MTC-O LT-RF -
2-MC-IA1 - - -
11/1/93 IA 1of1
._- .. - ._ ._x . _ _ , . . _. . . . _ _ _ _ _ ___ m
. s Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REULF JUST1F OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ MT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV COMPONENT COOLING (KC) 2KC-0001 A 2573-1.0 C-07 3 B ACT Butterfly EMO ST-O - - - - - -
2KC-0002B 2573-1.0 C-08 3 B ACT Butterfly EMO ST-O - - - - - -
2KC-0003A 2573-1.0 C-07 3 8 ACT Gate EMO ST-O - - - - - -
2KC-0005 2573-1.0 F-04 3 C ACT Check -
MTO-O - - - - - -
2KC-0008 2573-1.0 F-04 3 C ACT Check -
MTO-O - - - - - -
2KC-0011 2573-1.0 F-11 3 C ACT Check -
MTO-O - - - - - -
2KC-0014 2573-1.0 F-11 3 C ACT Check -
MTO-O - - - - - -
2KC-001BB 2573-1.0 C-08 3 B ACT Gate EMO ST-O - - - - - -
2KC-0047 2573-4.0 L-07 2 AC ACT Check -
MTC-O LT-RF -
2-MC-KC9 -
MT-RF -
2KC-0050A 2573-1.0 K-07 3 8 ACT Butterfly EMO ST-O - - - - - -
2KC-0051 A 2573-1.0 J-05 3 B ACT Gate EMO ST-O - - - - - -
2KC-00538 2573 1.0 K-08 3 8 ACT Butterffy EMO ST-O - - - - - -
2KC-00548 2573-1.0 J-10 3 B ACT Gate EMO ST-O - - - - - -
2KC-0056A 2573-1.1 E-02 3 B ACT Butterfly EMO ST-Q - - - - - -
2KC-0057A 2573-1.1 D-06 3 S ACT Buttert:y AOV ST-O - - - - - -
2KC-0061 2573-1,1 E-05 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0079 2573-1.1 B-05 3 C ACT Relief -
SP - - - -
150 PStG -
2XC-00818 2573-1 1 E-13 3 B ACT Butterfly EMO ST-O - - - - - -
11/1/93 KC 1 of 5
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIACRAM COOR CLASS CATECORY PAS TYPE TYPE REQ'MT #1 REQ'hfT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV ir COMPONENT COOLING (KC) 2KC-0082B 2573-1.1 D-09 3 8 ACT Butterfly AOV ST-O - - - - - -
2KC-0086 2573-1.1 E-10 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0104 2573-1.1 B-10 ' 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0108 2573-1.1 G46 3 C ACT Check -
MTC-Q - - - - - -
2KC-0112 2573-1.1 G-09 3 C ACT Check -
MTC-O - - - - -
2KC-0138 2573-2.0 E-12 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0147 2573-2.0 E-09 3 C ACT Relief -
SP - - - -
150 PSIG --
2KC-0154 2573-2.0 D-06 3 C ACT Relief -
2KC-0161 2573-2.0 F-04 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0187 2573-2.0 H-02 3 C ACT Relief -
SP - - - -
150 PStG -
2KC-0193 2573-2.0 F-02 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0199 2573-2.0 D-02 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0205 2573-2.0 C-13 3 C ACT Relief -
SP - - - -
150 PSIG -
- 2KC-0211 2573-2.0 F-13 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0217 2573-2.0 H-13 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0223 2573-2.0 J-13 3 C ACT Relief -
SP - - - -
150 PSIG -
2XC-0228B 2573-1.0 K-08 3 B ACT- Gate EMO ST-O - - - - - -
2KC-0230A 2573-1.0 K-07 3 B ACT Gate EMO ST-O - - - - - -
11/1/93 KC 2 of 5
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TWE REQMT W1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV'
, COMPONENT COOLING (KC) 2KC-0279 2573-3.1 K-04 2 AC ACT Check -
MTC-O LT-RF -
2-MC-KC7 - MT-RF -
2KC-0280 2573-3.1 D41 2 AC ACT Check -
MTC-O LT-RF - 2-MC-KC5 -
MT-RF -
2KC-0281 2573-3.1 J-02 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0305B 2573-3 1 D-14 2 B ACT Gate EMO ST-O - - - - - -
2KC-0313 2573-3.1 1-13 2 C ACT Relief -
SP - - - -
150 PSIG -
2KC-03158 2573-3.1 L-13 2 B ACT Gate EMO ST-Q - - - - - -
2KC-0320A 2573-3.1 C-10 2 A ACT Diaphram AOV ST-Q LT-RF -
2-MC-KC4 - - -
2KC-0322 2573-3.1 C-09 2 AC ACT Check -
MTC-O LT-RF -
2-MC-KC6 -
MT-RF -
2KC-0330 2573-3.1 C-05 3 C ACT Rehef -
SP - - - -
150 PSIG -
2KC-0332B 2573-3.1 D-01 2 A ACT Diaphram AOV ST-O LT-RF -
2-MC-KC3 - - -
2KC-0333A 2573-3,1 G-01 2 A ACT Diaphram AOV ST-O LT-RF -
2-MC-KC3 - - -
2KC-0338B 2573-3.1 D-12 -2 A ACT Butterfly - EMO ST-O LT-RF -
2-MC-KC2 - - -
2KC-0340 2573-3.1 E-12 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-KC8 -
MT-RF -
2KC-0349 2573-3.0 D49 2 C ACT Relief -
SP - - - -
2485 PSIG -
~ 2KC-0355 2573-3.0 E-14 3 C ACT Relief -
SP - - - -
150 PStG -
2KC-0361 2573-3.0 F-13 3 C ACT Relief - SP - - - -
150 PSIG -
2KC-0368 2573-3.0 1-09 2 C ACT Relief -
2KC-0374 2573-3.0 J-14 3 C ACT. Relief -
SP - - - -
150 PSIG -
11/1/93 KC 3 of 5
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW HOW ASME VALVE ACT VALVE ACTUATOR 1EST TEST RELIEF JUST'J OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYPE TYPE REQ Mr #1 REQMT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV COMPONENT COOLING (KC) 2KC-0380 2573-3.0 K-13 3 C ACT Relief -
SP - - - -
150 PSlG -
2KC-0386 2573-3.0 K-03 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0392 2573-3.0 J-02 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0398 2573-3.0 1-06 2 C ACT Relief -
SP - - - -
2485 PSIG .-
2KC-0404 2573-3.0 G-02 3 C ACT Relief -
SP - - - -
150 PSIG -
l 2KC-0410 2573-3.0 E-02 3 C ACT Relief -
SP - - - -
150 PSIC -
2KC-0417 2573-3.0 C-06 2 C ACT Relief -
SP - - - -
2485 PSIG -
2KC-04248 2573-3.1 L-04 '2 A ACT Butterfly EMO ST-Q LT-RF -
2-MO-KC1 - - -
2KC-0425A 2573-3.1 L-06 2 A ACT Butterfiy EMO ST-O LT-RF -
2-MC-KC1 - - -
2XC-04298 2573-4.0 K-07 2 A ACT Kerotest EMO ST-Q LT-RF .
(-
l 2KC-0430A 2573-4.0 K-08 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
l 2KC-0490 2573-3.1 E-09 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0491 2573-3.1- - F-09 3 C ACT. Relief -
SP - - - -
150 PSIG -
l 2KC-0492 2573-3.1 H-09 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0493 2573-3.1 J-09 3 C ACT Relief -
SP - - - -
150 PSIG -
2KC-0495 2573-1.1 G-05 3 C ACT Check -
MTO-O - - - - - -
l 2KC-0498 2573-1.1 ' G-10 3. C ACT Chec. -
MTO-O - - - - - -
t 2KC-0800 2573-1.1 1-11 3 C ACT Relief -
SP' - - - -
10 PSIG -
1-11/1/93 KC 4 of 5 l
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMUER DIAGRAM COOR CLASS CATEGORY PAS TIT'E TYPE REQ'MT #1 REQ M T#2 REQ 5'T DETER'RAL REMARKS ALTERNATIVES PLY COMPONENT COOLING (KC) 2KC-0897 2573-1.0 K-02 3 C ACT Check -
MTC-O - - - - - -
2KC-0903 2573-1.0 K-13 3 C ACT Check -
MTC-O - - - - - -
2KC-0958 2573-1.0 H-01 3 C ACT Check -
MTC-O - - - - - -
2KC-0972 2573-1.1 K-08 3 C ACT Relief -
SP - - - -
15 PSIG -
11/1/03 KC 5 of 5
Unit 2 - McGuire Nuclect Station Inservice Testing Program FLOW ASME VALVE ACT VALVE ACTUATOR 1EST TEST REIJEF JU5UF 0F TEST FLOW DTE DEFERRAL REMARKS ALTERNATIVES REV VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE REQ Mr #1 REUMT #2 REQST DIESEL GENERATOR COOLING WATER (KD) 2KD-0009 2609-1.0 E-14 3 B ACT Control AOV FS-O - - - - -
2KD-0016 2609-1.0 C-07 3 C ACT Check -
MTO,C-O - - - - - -
2KD-0018 2609-1.0 G-06 3 C ACT Check - MTC-Q - - - - - -
2KD-0029 2609-1.1 E-14 3 B ACT Control AOV FS-O - - - - -
2KD-0036 2609-1.1 C-07 3 C ACT Check -
MTO.C-O - - - -
2KD-0038 2609-1.1 G-06 3 C ACT Check -
MTC-O - - - - -
11/1/03 KD 1 of 1
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REllEF JUSTIF 0F TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TTTE TITE REQ'MT #1 REQMr #2 REQST DEFERRAL REMARKS ALTERNATIVES REV SPENT FUEL COOLING SYSTEM (KF) 2KF-0020 2570-1.0 K-05 3 C ACT Relief -
SP - - - -
.150 PSIG -
2KF-0031 2570-1.0 1-05 3 C ACT Relief -
SP - - - -
150 PSIG -
l i
l 1
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l I
l 11/1/93 KF 1 of1 l
i-i Unit 2 - McGuire Nuclear Station i inservice Testing Program FL OW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST COOR CLASS CATEGORY PAS TWE TYPE REQ'MT #2 REQTT DEFERRAL REMARKS ALTERNATIVES REV VALVE NUMBER DIAGRAM REQ'MT 81 DIESEL LUBE OIL (LD) 2LD-0001 2609-2 0 E-10 3 C ACT Relief -
2LD-0002 2609-2.0 J-12 3 C ACT Check -
MTO-O - - - -
2LD-0004 2609-2.0 H-13 3 C ACT Relief -
SP - - - -
75 PSIG -
2LD-0005 2609-2.0 G-13 3 C ACT Check -
MTC-Q - - - - -
2LD-0009 2609-2.0 F-09 3 C ACT Rehef - SP - - - - 45 PSIG -
2LD-0011 2609-2,0 G-06 3 C ACT Relief -
2609-2.0 H43 3 C ACT Relief SP - - - - 50 PSIG 2LD-0013 -
2LD-0031 2609-2.1 K-10 3 C ACT Relief -
2LD@32 2609-2.1 K-12 3 C ACT Check -
MT O-O - - - -
H-12 3 C ACT Relief SP - - -
75 PSIG -
2LD4034 2609-2.1 - -
2LD-0035 2609-2.1 1-13 3 C ACT Check -
MTC-O - - - -
2609-2.1 H-09 3 C ACT Relief SP - - - -
45 PSIG -
2LD-0039 -
2LD-0041 2609-2.1 G-06 3 C ACT Relief -
2609-2.1 J-03 3 C ACT Rehef -
2LD-0043 2LD-0108A 2609-2.0 E-12 3 D ACT Gate EMO ST-Q - - - - -
2LD-0113B 2609-2.1 G-12 3 B ACT Gate EMO ST-O - - - - -
11/1/93 LD 1 of 1 i
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW AShfE VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYPE TYPE RFQ'hTT #1 REQ'MT #2 REQST DETERRAL REMARKS ALTERNATIVES REV RADIATION MONITORING (MI) 2MI-5580 2499-M17 N'A 2 A ACT Soleniod EMO ST-O LT-RF - - - - -
2MI-5581 2499-Ml7 N/A 2 A ACT Soleniod EMO ST-O LT-RF - - - - -
2MI-5582 2499-Ml7 N/A 2 A ACT Soteniod EMO ST-O LT-RF - - - - -
2Mi-5583 2499-M17 N/A 2 A ACT Soleniod EMO ST-Q LT-RF - - - - -
11/1/93 MI - 1 of 1
Unit 2 - McGuire Nuclear Station Inservice Testing Program ASME VALVE ACT VALVE < TH ATOR TEST TEST RELIEF JLSTIF 0F TEST FUJW FLOW DEFERRAL REMARKS ALTERNATIVES REV VALVE NL'MBER DIAGRAM COOR CLASS CATEGORY PAS TYPE PE REQ'MT #1 REQ MT #2 REQ 5~f BORON RECYCLE (NB) 2NB-0260B 2556-3.0 G-05 2 A ACT Kerotest EMO ST-O LT-RF - - - -
AC ACT Chec6 MTC-O LT-RF -
2-MC-NB1 - MT-RF . -
2NS-0262 2556-3.0 G-03 2 -
2NB-0438 2556-3_0 1-02 3 C ACT Chect -
MTC-O - - - -
11/1/93 NB - 1 of 1
_ - . _ ___a_ _ _ _ _ - _ _ . _ . -
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ - _ _ . - _ _ _ _ _ _ _ _ . . - _ _ - - _ _ _ - _ _ _ _ _ ___________u _m._ -__ -___k w ' -__ *w-u %-
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQMT #2 RFQST DEFERRAL REMARKS ALTERNATI\TS REV REACTOR COOLANT (NC) 2NC-0001 2553-2.0 K-03 1 C ACT Relief -
SP - - - -
2485 PSIG -
2NC-0002 2553-2.0 K-04 1 C ACT Relief -
SP - - - -
2485 PSIG -
2NC-0003 2553-2.0 K-05 1 C ACT Relief -
SP - - - -
2485 PSIG -
2NC-0031B 2553-2.0 F-05 1 B ACT Gate EMO ST-O - - - - - -
2NC-0032B 2553-2.0 G-05 1 B ACT Control AOV ST-O - -
2-MC-NC1 - - -
2NC-0033A 2553-2.0 F-03 1 B ACT Gate EMO ST-O - - - - - -
2NC-0034A 2553-2.0 G-03 i B ACT Control AOV ST-O - -
2-MC-NC1 - - -
2NC-0035B 2553-2.0 F-02 1 B ACT Gate EMO ST4 - - - - - -
2NC-0036B 2553-2.0 G-02 1 B ACT Control AOV ST-O - -
2-MC-NC1 - - -
2NC-0053B 2553-2.1 H-10 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NC-0054A 2553-2.1 H-09 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NC-0056B 2553-2.1 D-14 2 A ACT Gate AOV ST-O LT-PF - - - - -
2NC-0057 2553-2.1 F-13 2 A PAS Check -
LT-RF - - - - - -
2NC-0059 2553-2.1 K-09 2 C ACT Check -
MTO-O - - - - - -
2NC-0141 2553-4.0 C-07 2 A PAS Diaphrarn -
LT-RF - - - - -
2NC-0142 2553-4.0 B-06 2 A PAS Diaphram -
LT-RF - - -
g 11/1/93 NC - 1 of 2
__.______ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- _ . _ _ _ _ ~ _ . . . _ . - - .
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FtJOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIP OF TEST VALVE NUMBER DIAGRAM COOR CLASS CAlTGORY PAS TWE TYPE REQMr #1 1 REQ MT #2 REQST DETERRAL REMARKS ALTERNATIVES REV REACTOR COOLANT (NC)
Isolated &
) 2NC-01950 2553-4.0 1-08 2 A PAS Globe EMO LT-RF - - -
Tagged - -
CLOSED isolated &
2NC-0196A 2553-4.0 H48 2 A PAS Globe EMO LT-RF - - -
Tagged - -
CLOSED 2NC-0259 2553-4.0 H-08 2 AC ACT Check -
MTC-O LT-RF -
2-MC-NC3 -
MT-RF* -
2NC-0261 2553-4 0 C-08 2 AC ACT Check -
MTC-O LT-RF -
2-MC-NC3 -
MT-RF* -
2NC-0272AC 2553-2.1 J49 1 B ACT Globe Solenoid ST-O - -
2-MC-NC2 - - -
2NC-0273AC 2553-2.1 J-10 1 B ACT Globe Solenoid ST-O - -
2-MC-NC2 - - -
2NC-02748 2553-2.1 1-09 1 B ACT Globe Solenoid ST-O - -
2-MC-NC2 - - -
2NC-0275B 2553-2.1 1-10 i B ACT Globe So!anoid ST-O - -
2-MC-NC2 - - -
11/1/93 NC - 2 of 2
- . . . . .. . ... . . . - ~ . . _ _ _ _ _ _ . .=
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUST1F OF TEST VALVE NUMBER DIAGit%1 COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQ'MT #2 REQ'iT DEFERRAL REMARKS ALTERNATIVES . REV ICE CONDENSER REFRIGERATION (NF) 2NF-0228A 2558-4.0 K-13 2 A ACT Diaphram AOV ST-O LT-RF - -
LT per TS - -
2NF-0229 2558-4.0 F-13 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-NF1 - MT RF* -
2NF-0233B 2558-4.0 K-12 2 A ACT Diaphram AOV ST-Q LT-RF - -
LT per TS - -
2NF-0234A 2558-4.0 K 13 2 A ACT Diaphram AOV ST-Q LT-RF - -
LT per TS - -
11/1/93 NF - 1 of 1
_ - - _ _ . _ - .__ . _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ . _ - - _ _ - - - - - _ . _ _ _ _ - = _ _ - - - - _ - _ . ___ _ - __ _ ___-____ _-- _-_ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - - - _ - - _ - - - _ _ - - _ _ _ - - _ _ _ _ - _
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYPE T)PE REQ MT #1 REQMT #2 REQST DETERRAL RENLARKS ALTERNATIVES ' REV RESIDUAL HEAT REMOVAL (ND) 2ND-0001B 2561-1.0 1-13 1 A ACT Gate EMO ST-O LT-TS -
2-MC-ND1 - PlV -
2ND-0002AC 2561-1.0 H-13 1 A ACT Gate EMO ST-O LT-TS -
2-MC-ND1 - PlV -
2ND-0003 2561-1.0 F-14 2 C ACT Relief -
SP - - - -
450 PSIG -
2ND-0004B 2561-1.0 E-12 2 B ACT Gate EMO ST-O . - - - - - -
2ND-0008 2561-1.0 D-08 2 C ACT Check - MTO,C-O - -
2-MC-ND6 - - -
2ND-0014 2561-1.0 D-03 2 B ACT Butterffy AOV ST-O - - - - - -
2ND-0015B 2561-1 0 E-03 2 B ACT Gate EMO ST-O - -
2-MC-ND3 - - -
2ND-0019A 2561-1.0 H-12 2 B ACT Gate EMO ST-O - - - - - -
2ND-0023 2561-1.0 J-08 2 C ACT Check - MTO,C-O - -
2-MC-ND6 - - -
2ND-0029A 2561-1.0 J-03 2 B ACT Butterfly AOV ST-O - - - - - -
2ND-0030A 2561-1.0 1-03 2 B ACT Gate EMO ST-O - -
2-MC-ND3 - - -
2ND-0056 2561-1.0 J-02 2 C ACT Relief -
2ND-0058A 2561-1.0 K-03 2 B ACT Gate EMO ST-O - -
2-MC-NC2 - - -
2ND-0061 2561-1.0 F-02 2 C ACT Relief - SP - - - -
600 PSIG -
2ND-0064 2561-1.0 E-02 2 C ACT Relief -
2ND-0067B 2561-1.0 B-09 2 B ACT Kerotest EMO ST-O - - - - - -
2ND-0068A 2561-1.0 L-09 2 B ACT Kerotest EMO ST-O - - - - - -
2ND-0070 2561-1.0 K-03 2 C ACT Check - MTO,C-O - -
2-MC-ND4 - - -
2ND-0071 2561-1.0 C-04 2 C ACT Check - MTO,C-O - -
2-MC-ND5 - - -
11/1/93 ND - 1 of 1
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW AShtE VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS DTE TYPE REQ MT #1 REQ hfr #2 REQST DEFERRAL REMARKS ALTERNAT!VES REV REACTOR COOLANT (NC) 2NI-0009A 2562-1.0 H-12 2 B ACT Gate EMO ST-O - -
2-MC-N11 - - -
2NI-00108 2562-1.0 G-12 2 B ACT Gate EMO ST-O - -
2-MC-Ni1 - - -
2N14012 2562-1.0 G-09 2 C ACT Check -
MTO-O - -
2-MC-N113 - - -
2NI0015 2562-1.0 K-07 1 C ACT Check -
MTO-O - -
2-MC-NI12 - - -
2Ni-0017 2562-1.0 1-04 1 C ACT Check -
MTO-O - -
2-MC-N112 - - -
2Nf-0019 2562-1.0 F-04 1 C ACT Check -
MTO-O - -
2-MC-N112 - - -
2NI-0021 2562-1.0 C-07 1 C ACT Check -
MTO-O - -
2-MC-N112 - - -
2NI-0047A 2562-2.0 K-05 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NI-0048 2562-2.0 K-03 2 AC ACT Check -
MTC-O LT-RF -
2-MC-N!21 -
MT-RF* -
2NI-0052 2562-2.0 E-05 2 C ACT Relief -
SP - - - -
700 PSIG -
. 2NI-0059 2562-2.0 D-13 1 AC ACT Check -
MTO.C-O LT-TS -
2-MC-N!22 -
PlV -
2NI-0060 2562-2.0 D-14 1 AC ACT Check -
MTO C-O LT-TS -
2-MC-N124 ' -
PlV -
2NI-0063 2562-2.0 1-05 2 C ACT Relief -
SP - - - -
700 PSIG -
2Ni-0070 2562-2.0 H-13 1 AC ACT Check -
MTO,C-O LT-TS -
2-MC-Ni22 -
PlV -
2NI-0071 2562-2.0 H-14 1 AC ACT Check -
MTO,C-O LT-TS -
2-MC-N!24 -
PlV -
2Ni-0074 2562-2.1 J-05 2 C ACT Relief -
SP - - - --
700 PSIG -
! 2N1-0081 2562-2.1 C-03 1 AC ACT Check MTO C-C LT-TS 2-MC-N!22
- - .- PlV -
11/1/93 NI- 1of5
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACll!ATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLAS5 CATEGORY PAS TYPE TYPE REQ 1fT *1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV REACTOR COOLANT (NC) 2NI-0082 2562-2.1 C-03 1 AC ACT Check -
MTO.C-O LT-TS -
2-MC-N124 -
PlV -
2NI-0086 2562-2.1 J-09 2 C ACT Relief -
SP - - - -
700 PSIG -
2N1-0093 2562-2.1 C-08 1 AC ACT Check - MTO,C-O LT-TS -
2-MC-N122 -
PfV -
2NI-0094 2562-2.1 C-08 1 AC ACT Check - MTO,C-O LT-TS -
2-MC-N124 -
PlV -
2NI-0095A 2562-2.1 F-11 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NI-00968 2562-2.1 E-13 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NI-01008 2562-3.0 F-13 2 B ACT Gate EMO ST-Q - -
2-MC-N12 - - -
2N1-0101 2562-3.0 F-13 2 C ACT Check -
MTO.C-O - -
2-MC-N114 - - -
2NI-0102 2562-3.0 1-13 2 C ACT Relief -
SP - - - -
240 PSIG '-
2Ni-0103A 2562-3.0 1-14 2 B ACT Gate EMO ST-O - -
2-MC-N16 - - -
2NI-0114 2562-3.0 1-09 2 C ACT Check -
MTO-O - - - - - -
2N!-0115B 2562-3.0 H-09 2 B ACT Kerotest EMO ST-O - -
2-MC-Nf3 - - -
2NI-0116 2562-3.0 J-09 2 C ACT Check -
MTO.C - -
2-MC-N115 - - -
2NI-0118A 2562-3 0 . H-07 2 B ACT Gate EMO ST-O - - - - - -
2NI-0119 2562-3.0 K-07 '2 C ACT Relief -
SP - - - -
1740 PSIG -
2Ni-0120B 2562-3.0 J-07 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NI-0121 A 2562-3.0 J-06 2 B ACT Gate EMO ST-O - -
2-MC-NI4 - - -
11/1/93 NI - 2 of 5
_ _ _ . ___ . ._ _ _ ~ - - _ _ _ - _ . _ _ _ _ _ . ._ __ , . _ _ _
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLA5C CATECORY PAS Til'E TYl'E REQ'MT #1 REQ MT 82 REQST DEFERRAL REMARKS ALTERN ATIVES RLV REACTOR COOLANT (NC) 2NI4124 2562-3.0 J-03 1 AC ACT Check -
MTO,C-O LT-TS 2-MC-Ni16 PlV -
2N14125 2562-3.0 1-03 1 AC ACT Check -
MTO C-O LT-TS 2-MC-N119 -
PlV -
2NI-0126 2562-3.0 J-02 1 AC ACT Check -
MTO.C-O LT-TS -
2-MC-N119 -
PlV -
2N1-0128 2562-3.0 l-04 1 AC ACT Check MTO C-O LT-TS 2-NC-N116 PlV -
2NI-0129 2562-3.0 1-03 1 AC ACT Check -
MTO.C-Q LT-TS 2-MC-N119 PlV -
2N!-0134 2562-3.0 H-04 1 AC ACT Check MTO.C-O LT-TS -
2-MC-N119 -
PiV -
2NI-0135B 2562-3.0 E-14 2 B ACT Gate EMO ST-O - - - - - -
2NI-01368 2562-3 0 C-14 2 B ACT Gate EMO ST-Q - -
2-MC-Nf20 - - -
2NI-0143 2562-3.0 F-09 2 C ACT Check -
MTO,C-O - - - - - -
2NI-0144B 2562-3.0 G-09 2 B ACT Kerotest EMO ST-Q - - - - - -
2NI-0147A 2562-3.0 G-11 2 B ACT Kerotest EMO ST-O - -
2-MC-N13 - - -
2Ni-0148 2562-3.0 D-09 2 C ACT Check -
MTO,C - -
2-MC-N115 - - -
2NI-01508 2562-3.0 E-07 2 B ACT Gate EMO ST-Q - - - - - -
2Ni-0151 2562-3.0 C-07 2 C ACT Relief -
SP - - - -
1740 PS!G -
2NI-0152B 2562-3.0 D-06 2 B ACT Gate EMO ST-O - -
2-MC-N14 - - -
2Ni-0156 2562-3.0 D-03 1 AC ACT Check - MTO,C-O LT-TS -
2-MC-N116 -
PlV -
2Nf4157 2562-3.0 D-02 1 AC ACT Check -
MTO.C-O LT-TS -
2-MC-N116 -
PlV -
11/1/93 NI - 3 of 5 m
Unit 2 - McGuire Nuclear Station Inservice Testing Progrom FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUML2E R DLAGRAM COOR CLASS CATIGORY PAS TYPE TYPE REQ'MT #1 REQ MT #2 E EQST DEFERRAL REMARKS ALTERNATIVFS REV REACTOR COOLANT (NC) 2NI-0159 2562-3.0 B-04 1 AC ACT Check -
MTO.C-Q LT-TS -
2-MC-N116 - PlV -
2Ni-0160 2562-3.0 B43 1 AC ACT Check - MTO,C-O LT-TS -
2-MC-N116 -
P!V -
2NI-0161 2562:3.1 J-12 2 C ACT Relief -
2NI-0162A 2562-3 1 K-11 2 B ACT Gate EMO ST-O - -
2-MC-N15 - - -
2NI-0165 2562-3.1 J-03 1 AC ACT Check - MTO,C-O LT-TS -
2-MC-N117 - PlV -
2NI-0167 2562-3.1 J-05 1 AC ACT Check -
MTO.C-Q LT-TS -
2-MC-N117 - PlV -
2N1-0169 2562-3.1 J-06 1 AC ACT Check -
MTO.C-Q LT-TS -
2-MC-N117 - P!V -
2N1-0171 2562-3.1 J-07 1 AC ACT Check -
MTO,C-Q LT-TS -
2-MC-N117 -
P!V -
2NI-0173A 2562-3.1 1-1; 2 B ACT Gate EMO ST-Q - -
2-MC-N17 - - -
2NI-0175 2562-3.1 l-J8 1 AC ACT Check -
MTO.C-Q LT-TS -
2-MC-N118 - PiV -
2NI-0176 2562-3.1 H-08 1 AC ACT Check - MTO,C-Q LT-TS -
2-MCON118 -. PlV -
2NI-01788 2562-3.1 F-12 2 B ACT Gate EMO ST-Q - -
2-MC-N17 - - -
2Ni-0180 2562-3.1 F-07 1 AC ACT Check -
MTO.C-O LT-TS -
2-MC-Nil 8 - P!V -
2NI-0181 2562-3.1 D-08 1 AC ACT Check - MTO,C-Q LT-TS -
2-MC-N118 - PlV -
2NI-01838 2562-3.0 G-03 2 B ACT Gate EMO ST-O - -
2-MC-N!9 - - -
2NI-0184B 2562-3.1 D-12 2 B ACT Gate EMO ST-O - -
2-MC-NI10 - - -
2N1-0185A 2562-3.1 B-12 2 B ACT Gate EMO ST-O - -
2-MC-N110 - - -
11/1/93 NI- 4 of 5
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VAINE ACT VALVE ACIVATOR TEST TEST RELIEF JUSTIF OF TEST
. VALVE NUMBER DIAGRut COOR CLASS CATEGORY PAS TYl'E TYPE REQ'MT #1 REQMT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV REACTOR COOLANT (NC) 2Nt-0332A 2562-3.0 L-14 2 B ACT Gate EMO ST-Q - -
2-MC-N111 - - -
2NI-0333B 2562-3.0 L-12 2 B ACT Gate EMO ST-O - -
2-MC-N111 - - -
2NI-0334B 2562-3.0 L-11 2 B ACT Gate EMO ST-O - -
2MC-NI8 - - -
2N1-0347 2562-1.0 1-04 1 C ACT Check -
MTO-O - -
2-MC-N112 - - -
2NI4348 2562-1.0 F-05 1 C ACT Check -
MTO-O - - 2-MC-N112 - - -
2NI-0349 2562-1.0 C-07 1 C AC'. Check -
MTO-Q - - 2-MC-N112 - - -
2N14354 2562-1.0 K-07 1 C ACT Check -
MTO4 - -
2-MC-N112 - - -
2N1-0430A 2562-2.0 F-04 2 B ACT Kerotest EMO ST-O - - - - - -
2Ni-04310 2562-2.0 J-04 2 B ACT Kerotest EMO ST-O - - - - - -
2NI-0436 2562-2.1 G-11 2 AC ACT Check -
MTC-O LT-RF -
2-MC-N123 -
MT-R F* -
11/1FJ3 NI- 5 of 5
Unit 2 - McGuire Nuclear Station inservice Testing Program FLOW FLOW ASME val.YE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAh! COOR CLASS CATFGORY PAS TYPE TYPE REQ MT #1 REQ MT #2 RFQ57 DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SAMPLING (NM) 2NM-0003AC 2572-1.0 K-03 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0006AC 2572-1.0 J-03 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0007B 2572-1.0 K-06 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0022AC 2572-1.0 J-12 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0025AC 2572-1.0 K-12 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0026B 2572-1.0 K-09 2 A ACT Kerotest EMO ST-Q LT-RF - - - - -
2NM-0069 2572-1.1 G-09 2 A ACT Relief -
SP LT-RF - - -
700 PS!G -
2NM-00728 2572-1.1 1-06 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0075B 2572-1.1 1-08 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0078B 2572-1.1 1-10 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0081B 2572-1.1 1-11 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0082A 2572-1.1 E-09 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2NM-0187A 2572-3.0 K-01 2 B ACT Kerotest EMO ST-O - - - - - -
2NM-0190A 2572-3.0 K-02 2 B ACT Kerotest EMO ST-O - - - - - -
2NM-0191B 2572-3.0 l-02 2 B ACT Kerotest EMO ST-O - - - - - -
2NM-0197B 2572-3.0 K-05 2 B ACT Kerotest EMO ST-O - - - - - -
2NM-02008 2572-3.0 K-06 2 B ACT Kerotest EMO ST-O - - - - - -
11/1/93 NM - 1 of 2
Unit 2 - McGuire Nuclear Statio7 Inservice Testing Program FLOW FLOSi ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 RFQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SAMPLING (NM) t 2NM-0201 A 2572-3 0 1-06 2 B ACT Kerotest EMO ST-O - - - - - -
2NM-0207A 2572-3.0 K-08 2 B ACT Kerotest EMO ST-O - - - - - -
2NM-0210A 2572-3.0 K-09 2 B ACT Kerotest EMO ST-O - - - - - -
l 2NM4211B 2572-3.0 1-09 2 B ACT Kerotest EMO ST-O - - - - - -
2NM-0217B 2572-3.0 K-11 2 B ACT Kerotest EMO ST-O - - - - - -
2NM-02208 2572-3.0 K-12 2 B ACT Kerotest EMO ST-O - - - - - -
2NM-0221 A 2572-3.0 1-12 2 B ACT Kerotest EMO ST-Q - - - - - -
2NM-0420 2572-1.0 J-03 2 AC ACT Check -
MTC-O LT-RF -
2-MC-NM1 -
MT-R F* -
2NM-0421 2572-1.0 J-12 2 AC ACT Check -
MTC-O LT-RF -
2-MC-NM1 -
MT-RF' -
I 11/1/03 NM - 2 of 2
Unit 2 - McGuire Nuclear Station Inservice Testing Progrom FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TWE TYPE REQ'MT #1 REQ'MT 82 REQST DEFERRAL REMARKS ALTERNATIVES REY CONTAINMENT SPRAY (NS) 2NS-0001 B 2563-1.0 C-13 2 B ACT Gate EMO ST-O - - - - - -
2NS-0002 2563-1.0 D-12 2 C ACT Relief -
SP - - - -
220 PSIG -
2NS4003B 2563-1.0 B-13 2 B ACT Gate EMO ST-O - - - - - -
2NS-0004 2563-1.0 C-12 2 C ACT Check - MTO,C-O - -
2-MC-NS3 -
RF# -
2NS-00128 2563-1.0 C-04 2 B ACT Gate EMO ST-O - - - - - -
2W 2NS-0013 2563-1.0 B-02 2 C ACT Check -
MTO-O -
~ 2-MC-NS2 -
RF# -
N 2NS-0015B 2563-1.0 D-04 2 B ACT Gate EMO ST-O - - - - - -
2 RR-2NS-0016 2563-1.0 D-02 2 C ACT Check -
MTO-O -
2-MC-NS2 -
RF# -
2NS-0018A 2563-1.0 G-13 2 B ACT Gate EMO ST-Q - - - - - -
2NS-0019 2563-1.0 H-12 2 C ACT Relief -
SP - - - -
220 PSIG -
2NS-0020A 2563-1.0 F-13 2 B ACT Gate EMO ST-Q - - - - - -
2NS-0021 2563-1.0 F-12 2 C ACT Check -
MTO,C-Q - -
2-MC-NS3 -
RF# -
2NS-0029A 2563-1.0 F-04 2 B ACT Gate EMO ST-O - - - - - -
F-02 C ACT Check 2 C R-2NS-0030 2563-1.0 2 -
MTO-O -
2-MC-NS2 - RF# -
2NS-0032A 2563-1.0 H-04 2 B ACT Gate EMO ST-O - - - - - -
2- RR-2NS-0033 2563-1.0 H-02 2 C ACT Check -
MTO-O -
2-MC-NS2 -
RF# -
2NS-0038B 2563-1.0 J-05 2 B ACT Gate EMO ST-O - -
2-MC-NS1 - - -
11/1/93 NS - 1 of 2
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTLF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQ MT #2 REQ $7 DEFERRAL REMARKS ALTERNATIVES REV .
CONTAINMENT SPRAY (NS) 2NS-0041 2563-1.0 J-03 2 C ACT Check -
MTO-O -
2-MC-NS2 -
RF# -
NS 2NS-0043A 2563-1.0 K-05 2 B ACT Gate EMO ST-O - -
2-MC-NS1 - - -
C ACT Check MTO-O 2M 2-MC-NS2 2NS 0046 2563-1.0 K-03 2 - - -
RF# -
NS RF#
2NS-0140 2563-1.0 G-05 2 AC ACT Check - MTO,C-O LT -
2-MC-NS4 - ,
RF#
2NS-0141 2563-1.0 C-05 2 AC ACT Check -
MTO C-O LT -
2-MC-NS4 - ,
2NS-5550B 2499-NS8 N/A 2 A ACT Solenoid SOV ST-O LT-RF - - - - -
2NS-5551 A 2499-NS8 N/A 2 A ACT Solenoid SOV ST-O LT-RF - - - - -
11/1/93 NS -- 2 of 2
q l
l 1
Unit 2 - McGuire Nuclear Station i inservice Testing Program FLOW FLOW AS\tE VALVE ACT VALVE ACTUATOR TEST VALVE NatDG DIACHAM COOR TEST RELIEF JUST!FOF TEST CLASS CATEGORY PA5 TYPE TiPE REQ MT #1 REQ MT *2 REQST DEFERRAL REMARKS ALTERNATIVES REV CHEMICAL AND VOLUME CONTROL (NV) 2NV-0006 2554-1.2 K-08 2 C ACT Relief -
SP - - - -
600 PSIG -
2NV-0007D 2554-1.2 J-11 2 B ACT Globe EMO ST-O - -
2-MC-NV2 - - -
2NV-0020 2554-1.2 E-02 2 C Spring ACT Check -
SP - - -
Loaded Ck 200 PSIG -
Valve 2NV-0021 A 2554-1.2 E-33 B 1 ACT Control AOV ST-O 2-MC-NV3 2NV-0029 2554-1.0 C-02 2 C ACT Check MTO-O -
2NV-0031 2554-1.0 D-02 C 1 ACT Check -
MTO-O - - - - - -
2NV-0035A 2554-1.2 K-07 2 B ACT Gate AOV ST-O - - - - - -
2NV-0045 2554-1.0 C-08 2 C ACT Check -
MTO-O - -
2NV-0047 2554-1.0 D-08 1 C ACT Check -
MTO-O - - - - - -
2NV-0061 2554-1.1 C-02 2 C ACT Check -
MTO-O - - - - - -
2NV-0063 2554-1.1 D42 C 1 ACT Check -
MTO-O -
2NV-0077 2554-1.1 C-08 2 C ACT Check -
MTO-O -
2NV-0079 2554-1.1 T'-08 C 1 ACT Check -
MTO-O - - - - - -
! 2NV-0093 2554-1.1 K-12 2 C l ACT Relief -
SP -
150 PSIG 2NV-0094AC 2554-1.1 J-13 2 B
! ACT Gate EMO ST-O -
l 2-MC-NV1 - - -
2NV-0095B 2554-1.1 H-13 2 l B ACT Gate EMO ST-O -
i 2-MC-NV1 - - -
l 2NV-0141 A 2554-2.0 B-08 2 B ACT Gate EMO ST-O l
2-MC-NV4 - - -
l l
11/1/93 NV - 1 of 4
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST val.VE NUMitER DIAGRA* f COOR CLASS CATEGORY PAS TYPE TYPE REQ MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV-CHEMICAL AND VOLUME CONTROL (NV) 2NV-0142B 2554-2.0 B-07 2 B ACT Gate EMO ST-O - -
2-MC-NV4 - - -
2NV4143 2554-2.0 B-06 2 C ACT Check -
MTC-O - -
2-MC-NV15 - - --
2NV-0150B 2554-2.0 F-02 2 B ACT Kerotest EMO ST-O - -
2-MC-NVB - - -
2NV-0151 A 2554-2.0 G-02 2 B ACT Kerotest EMO ST-O - -
2-MC-NV8 - - -
2NV 0155 2554-2.0 1-06 2 C ACT Relief - SP - - - -
150 PSIG -
2NV-0156 2554-2.0 J-09 2 C ACT Relief -
SP - - - -
255 PSIG -
2NV-0164 2554-2.0 E-09 2 C ACT Check -
MTC-O - - - - - -
2NV-0170 2554-2.0 C-08 2 C ACT Relief -
SP - - - -
75 PSIG -
2NV-0218 2554-3.0 J-05 2 C ACT Check -
MTC-O - - - - - -
2NV-0221 A 2554-3.1 H-01 2 B ACT Gate EMO ST-O - -
2-MC-NV6 - - -
2NV-02220 2554 3.1 1-01 2 B ACT Gate EMO ST-O - -
2-MC-NV6 - - -
2NV-0223 2554-3.1 1-02 2 C ACT Check -
MTO.C-O - -
2-MC-NV11 - - -
2NV-0225 2554-3 1 F-05 2 C ACT Check -
MTO C-O - -
2-MC-NV10 - - -
2NV-0227 2554-3.1 E-06 2 C ACT Check -
MTO C-O - - - - - -
2NV-0229 2554-3.1 1-12 2 C ACT Relief -
SP - - - -
220 PSIG -
2NV-0231 2554-3.1 F-10 2 C ACT Check -
MTO.C-O - -
2-MC-NV10 - - -
2NV-0233 2554-3.1 E-10 2 C ACT Check - MTO,C-O - - - - - -
11/1/93 NV $ 2 of 4
Unit 2 - McGuire Nuclear Stofion Inservice Testing Program FLOW FLOW ASME VALVE ACT val.VE ACTUATOR HST TEST REUEF JUST1F OF TEST CLAS5 CATEGORY PAS TYPE DEFERRAL REMARKS ALTERNATIVES REV VALVE NUMBER DIAGRAM COOR TYPE REQMT #1 REQ MT #2 REQST CHEMICAL AND VOLUME CONTROL (NV) 2NV-0238 2554-3.1 G-04 2 B ACT Control AOV FS-O - - - -
2NV-0244A 2554-3.0 K-08 2 B ACT Gate EMO ST-O - -
2-MC-NV5 - - -
2NV-0245B 2554-3.0 K-09 2 B ACT Gate EMO ST-O - -
2-MC-NV5 - - -
2NV-0261 2554-3.1 J-03 2 C ACT Check -
MTC-O - -
2-MC-NV13 - - -
2NV-0263 2554-3.1 J-11 2 C ACT Check -
MTC-Q - -
2-MC-NV13 - - -
2NV-0264 2554-3.1 J-10 2 C ACT Check -
MTO.C-O - -
2-MC-NV7 - - -
2NV-02659 2554-3.1 J-09 2 B ACT Globe EMO ST-Q - - 2-MC-NV9 - - -
2NV-0383 2554-5.0 F-06 3 C ACT Check -
MTO.C-O - - - -
2NV-0386 2554-5.0 D-06 3 C ACT Check - MTO,C-Q - - - - - -
2NV-0457A 2554-1.2 1-07 2 B ACT Control AOV ST-O - - - -
2NV-0458A 2554-1.2 J-07 2 B ACT Control AOV ST-O - - - - -
2NV-0482 2554-2.0 D-07 2 C ACT Re!ief - SP - - - -
150 PSIG -
2NV-0483 2554-2.0 D-11 2 C ACT Relief -
2NV-0486 2554-3.1 J-09 2 C ACT Relief - SP - - - - 150 PSIG - -
2554-3.1 J-10 2 C ACT Relief SP - - - -
150 PSIG -
2NV-0487 -
2NV-0810 2554-1.0 D-03 1 C ACT Check -
MTO-O - - - - -
2NV-0811 2554-1 0 D-10 1 C ACT ' Check -
MTO-O - - - - -
11/1/93 NV - 3 of 4
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUST1F OF TEST VALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS TYPE TWE REQMF #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV CHEMICAL AND VOLUME CONTROL (NV) 2NV-0812 2554-1.1 D-03 1 C ACT Check -
MTO-O - - - - - -
2NV-0813 2554-1.1 D-10 1 C ACT Check -
MTO-O - - - - - -
2NV-0849AC 2554-1.3 F-08 2 A ACT Kerotest EMO ST-Q LT-RF - - - - -
2NV-1002 2554-1.3 F-10 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-NV14 -
MT-RF -
2NV-1007 2554-1.3 F-13 2 C ACT Check -
MTC-Q - - - - - -
2NV-1008 2554-1.3 F-13 2 C ACT Check -
MTC-Q - - - - - -
2NV-1009 2554-1.3 F-13 2 C ACT Check -
MTC-Q - - - - - -
2NV-1010 2554-1.3 F-13 2 C ACT Check -
MTC-Q - - - - - -
2NV-1034 2554-2.0 C-07 3 C ACT Check -
MTC-Q - - - - - -
2NV-1046 2554-3.0 H-12 2 C ACT Check -
MTC-Q - -
2-MC-NV12 - - -
11/1/93 NV - 4 of 4
. ~ . _ . . _ . -
Unit 2 - McGelre Nuclear Stofion Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST ITST RELIEF JUST1F OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYl'E TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SERVICE WATER (RN) 2RN-0016A 2574-1.1 J-03 3 B ACT Butterfly EMO ST-O - - - - - -
2RN-0018B 2574-1.1 E-02 3 8 ACT Butterfly EMO ST-O - - - - - -
2RN-0021 A 2574-1.1 J-02 3 B ACT Gate AOV ST-O - - - - - -
2RN-0022A 2574-1.1 H-05 3 8 ACT Gate AOV ST-O - - - - - -
2RN4025B 2574-1.1 C-04 3 8 ACT Gate AOV ST-O - - - - - -
2RN-0026B 2574-1.1 G-05 3 B ACT Gate AOV ST-O - - - - - -
j 2RN-0028 2574-1.1 ' J-09 3 C ACT Check -
MTO-O - - - - - -
2RN-0030 2574-1.1 E-09 3 C ACT Check -
MTO-O - - - - - -
2RN-0040A 2574-1.1 l 12 3 B ACT Butterfly EMO ST-O - - - - - -
U2 & U1 2RN@41B 2574-1.1 F-12 3 8 ACT Butterf!y EMO ST-O - - -
SIGNAL - -
2RN-0042A 2574-4.0 B-09 3 B ACT Butterfty EMO ST-Q - -
2-MC-RN3 - - -
U2 & U1 2RN-0043A 2574-1.1 F-12 3 B ACT Butterfly EMO ST-O - - -
SIGNAL - -
2RN-00638 2574-4.0 L-10 3 B ACT Butterfly EMO ST-O - -
2-MC-RN4 - - -
2RN 0064A 2574-4.0 L-11 3 B ACT Butterf!y EMO ST-O - -
2-MC-RN4 -- - -
2RN406BA 2574-1.1 L-12 3 B ACT Control AOV ST-O - - - - - -
2RN-0069A 2574-2.0 K-07 3 B ACT Gate EMO ST-O - - - - -
2RN4070A 2574-2.0 E-06 3 B ACT Butterfly EMO ST-O - - - - - -
11/1/93 RN - 1 of 4
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELF.F JUSTIF OF TEST VALVE NUM13ER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #t REQ MT #2 REQiT DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SERVICE WATER (RN) 2RN-0073A 2574-2.0 1-06 3 B ACT Butterfly EMO ST-O - - - - - -
2RN-0077 2574-2.0 1-06 3 C ACT Relief .
SP - - - -
135 PSIG -
2RN-008E.*. 2574-2.0 D-12 3 B ACT Butterfly EMO ST-O - - - - - -
2RN-0089A 2574-2.0 J-12 3 B ACT Butterfly AOV ST-O - - - - - -
2RN-0103A 2574-2.1 C-06 3 B ACT Diaphram AOV ST-Q - - - - - -
2RN-0112A 2574-2.0 1-08 3 B ACT Control AOV ST-O - - - - - -
2RN-0113 2574-2.0 D-13 3 C ACT Check -
MTO-O - -
2-MC-RN5 - - -
2RN-0114A 2574-2.1 B-11 3 B ACT Diaphrarn AOV ST-Q - - - - - -
2RN-0117A 2574-2.0 1-10 3 8 ACT Control AOV ST-O - - - - - -
2RN-0126A 2574-2.1 D-10 3 B ACT Globe AOV ST-O - - - - - -
2RN-0130A 2574-2.1 C-10 3 B ACT Globe AOV ST-O - - - - - -
2RN-0134A 2574-2.1 C-07 3 B ACT Butterfly EMO ST-O - - - - - -
2RN-0137A 2574-2.1 H-07 3 B ACT Butterfly EMO ST-Q - - - - - -
2RN-0138 2574-2.1- H-00 3 C ACT Relief -
SP - - - -
135 PSIG -
2RN-0140A 2574-2.0 E-14 3 B ACT Globe AOV ST-O - - - - - -
2RN-0161B 2574-1.1 B-12 3 B ACT Control AOV ST-Q - - - - - -
2RN-0162B 2574-3.0 J-07 3 B ACT Gate EMO ST-Q - - - - - -
11/1/93 RN - 2 of 4
Unit 2 - McGuire Nuclear Staffort inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUST!F OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYPE T)PE REQ'MT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SERVICE WATER (RN) 2RN-0166A 2574-2.0 1-01 3 B ACT Diaphram AOV ST-Q - - - - - -
2RN-01708 2574-3.0 1-01 3 8 ACT Diaphram AOV ST-O - - - - - -
2RN-0171B 2574-3.0 F-07 3 B ACT Butterfly EMO ST-O - - - - - -
2RN-0174B 2574-3.0 1-07 3 B ACT Butterfly EMO ST-Q - - - - - -
2RN-0178 2574-3.0 1-06 3 C ACT Relief -
SP - - - -
135 PSIG -
2RN-0187B 2574-3.0 F-12 3 B ACT Butterfly EMO ST-O - - - - - --
2RN-0190B 2574-3.0 J-12 3 B ACT Butterfly AOV ST-O - - - - - -
2RN-0204B 2574-3.1 C-05 3 B ACT Diaphram AOV ST-O - - - - - -
2RN-02138 2574-3.0 J-08 3 B ACT Control AOV ST-O - - - - - -
2RN4215B 2574-3.1 B-11 3 B ACT Diaphram AOV ST-O - - - - - -
2RN-0218B 2574-3.0 1-10 3 B ACT Control AOV ST-O - - - - - -
2RN-0227B 2574-3.1 E-10 3 B ACT Globe AOV ST-O - - - - - --
2RN-0231B 2574-3.1 C-10 3 B ACT Globe AOV ST-O - - - - - -
2RN-0235B 2574-3.1 E-07 3 B ACT Butterfly EMO ST-O - - - - - -
2RN-0238B 2574-3.1 1-07 3 B ACT Butterfty EMO ST-Q - - - - - -
2RN-02408 2574-3.0 - F-13 3 B ACT Globe AOV ST-O - - - - - -
2RN-0252B 2574-4.0 - E 2 A ACT Diaphram AOV ST-O LT-RF -
2-MC-RN1 - - -
11/1/93 RN - 3 of 4
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW n.OW ASME VALVE ACT VALVE ACTUATOR TEST TEST RFLlEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SERVICE WATER (RN) 2RN-0253A 2574-4.0 C-02 2 A ACT Diaphram EMO ST-O LT-RF -
2-MC-RN1 - - -
2RN-0276A 2574-4.0 J-02 2 A ACT Diaphram EMO ST-O LT-RF -
2-MC-RN2 - - -
2RN-02778 2592-4.0 H-02 2 A ACT Diaphram AOV ST-O LT-RF -
2-MC-RN2 - - -
2RN-0279B 1574-1.0 C-02 3 8 ACT Butterfly EMO ST-O - - - - - -
2RN-0293 2574-3.1 1-05 3 C ACT Relief -
SP - - - -
135 PSIG -
2RN-0294 2574-3.0 F-12 3 C ACT Reliet -
SP - - - -
135 PSIG -
2RN-0295 2574-2.0 H-11 3 C ACT Relief -
SP - - - -
135 PSIG -
2RN-0296A 2574-1.1 L-13 3 B ACT Butterfly EMO ST-Q - - - - - -
2RN-0297B 2574-3.0 L-05 3 B ACT Butterfly EMO ST-O - - - - - -
2RN4299A 1574-1.0 C-02 3 B ACT Butterfly EMO ST-O - - - - - -
2RN-0891 2574-2.0 1-04 3 C ACT Check - MTO,C-O - -
2-MC-RN6 - - -
2RN-0892 2574-3.0 1-04 3 C ACT Check - MTO,C-O - -
2-MC-RN6 - - -
2-MC-RR-RN1 2RN-0994 2574-3.1 C-07 3 C ACT Check -
MTC-O - , , , ,
2-MC-RR-2RN-1006 2574-2.1 C-08 3 C ACT Check -
MTC-O - RN1 , _ . ,
11/1/93 RN - 4 of 4
IJrat 2 - McGutte liuc%ct Stafs:m intervice Tottng Prograrn FL OW I L OW A5ME VALVE ACT VALVE ACTUATOR TEST TIST REUEF JUSTIF OF TEST VALYf. Nt Mtil k t il ACKAkt COOK Ct%S CATELORY PAS nit TY1T REQMisi RIOMi t2 REOST DEFERRAL REMARKS ALTERNATIVES REV t
CONTAINMENT VENTILATION COOLING WATER (RV) 2RV4032A 2004-3 0 K-10 2 A ACT Butterfly EMO ST-O LT-RF -
2-MC-RV1 - - -
2RV-0033B 2604-3.0 K-12 2 A ACT Butterffy EMO ST-Q LT-RF -
2-MC-RV1 - - -
2RV-0076A 2604-3.0 C-12 2 A ACT Butterfly EMO ST-O LT-RF -
2-MC-RV1 - - -
2RV-0077B 2604-3.0 C-10 2 A ACT Butterfly EMO ST-O LT-RF -
2-MC-RV1 - - -
2RV-0079A 2604-3.0 K-07 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
2RV-0080B 2604-3.0 K-06 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
2RV-0101 A 2604-3.0 C-05 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
2RV-0102B 2604-3.0 C-07 2 A ACT Diaphram AOV ST-O - - - - - -
2RV-0445 2604-3.0 J-12 2 AC ACT Relief -
2RV-0446 2604 4 0 B-12 2 AC ACT Relief -
11/1/93 RV - ' 1 of 1 A
Unit 2 - McGuire h _ lear Station inservice Testing Program rLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYPE TYPE REQMr #1 REQ'MT *2 REQST DEFERRAL REMARKS ALTERNATIVES REV MAIN STEAM (SM) 2SMEK)1AB 2593-1.3 K-13 2 B ACT Globe AOV ST-O - -
2-MC-SM1 - - -
2SM-0003AB 2593-1.3 H-13 2 B ACT Globe AOV ST-O - -
2-MC-SM1 - - -
2SM-0005AB 2593-1.0 1-14 2 B ACT Globe AOV ST-O - -
2-MC-SM1 - - -
2SM-0007AB 2593-1.0 C-14 2 B ACT Globe AOV ST-O - -
2-MC-SM1 - - -
2SM-0009AB 2593-1.3 J-13 2 B ACT Control AOV ST-O - - - - - -
2SM-0010AB 2593-1.3- G-13 i B ACT Control AOV ST-O - - - - - -
2SM@11 AB 2593-1.0 1-13 2 B ACT Control AOV ST-O - - - - - -
2SM-0012AB 2593-1.0 C-13 2 B ACT Control AOV ST-O - - - - - -
11/1/93 SM - 1 of 1
Unit 2 - McGuire Nuclear Station Inservice Testing Prograrn FLOW FILW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS . CATEGORY PAS TYPE TYPE REQ ~hrT el REQ MT #2 REQST DEFERRAL REh! ARKS ALTERNATIVES REV MAIN STEAM VENT TO ATMOSPHEF1E (SV) 2SV-0001 AB 2593-1.3 L-0-5 2 B ACT Control AOV ST-Q - - - - - -
2SV-0002 2593-1.3 K-06 2 C ACT Relief -
SP - - - -
1170 PSIG -
2SV-0003 2593-1.3 K-07 2 C ACT Relief -
SP - - - -
1190 PSIG -
2SV-0004 2593-1.3 K-09 2 C ACT Relief -
SP - - - -
1205 PSIG -
2SV-0005 2593-1.3 K-11 2 C ACT Relief -
SP - - - -
1220 PSIG -
2SV-0006 2593-1.3 K-12 2 C ACT Relief -
2SV-0007ABC 2593-1.3 G-05 2 B ACT Control AOV ST-O - - - - - -
2SV-0008 2593-1.3 E-06 2 C ACT Relief -
SP - - - -
1170 PSIG -
2SV-0009 2593-1.3 E-07 2 C ACT Relief -
SP - - - -
1190 PSIG -
2SV-0010 2593-1.3 E-09 2 C ACT Relief -
SP - - - -
1205 PSIG -
2SV-0011 2593-1.3 E 2 C ACT Relief -
SP - - - -
1220 PSIG '-
2SV-0012 2593-1.3 E-12 2 C ACT Relief -
SP - - - -
1225 PSIG -
2SV-0013AB 2593-1.0 L-04 2 B ACT Control AOV ST-Q - - - - - -
2SV-0014 2593-1.0 K-05 3 C ACT Relief -
SP - - - -
1170 PSIG -
2SV-0015 2593-1.0 K-07 2 C ACT Relief -
SP - - - -
1190 PSIG -
2SV-0016 2593-1.0 K-09 2 C ACT Relief - SP - - - -
1205 PSIG -
2SV-0017 2593-1.0 K-10 2 C ACT Relief -
SP - - - -
1220 PSIG -
11/1/93 SV - 1 of 2
Unit 2 - McGuire Nuclect Station inservice Testing Program ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST FIDW - FLOW ASME VALVE DEFERRAL REMARKS ALTERNATIVES REV VALVE NUMBER DIACRAh! COOR CLASS CATEGORY PAS TWE TYPE REQ'hfT #1 REQ'MT #2 REQST MAIN STEAM VENT TO ATMOSPHERE (SV) 2593-1.0 K-12 2 C ACT Rehef - SP - - - - 1225 PSIG -
2SV-0018 -
2SV4019AB 2593-1.0 G-05 2 B ACT Control AOV ST-Q - - - -
E-05 2 C ACT Retief SP - - - - 1170 PSIG -
2SV-0020 2593-1.0 -
E-07 2 C ACT Relief SP - - - - 1190 PSIG -
2SV-0021 2593-1.0 -
E-09 2 C ACT Rehef SP - - - -
1205 PSIG -
2SV-0022 2593-1.0 -
E-10 2 C ACT Relief SP - - - 1220 PSIG -
2SV-0023 2593-1.0 - -
E-12 2 C ACT Relief SP - - - - 1225 PSIG -
2SV-0024 2593-1.0 -
11/1/93 SV - 2 of 2
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF 0F TEST VALVE NL'MBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV l
BREATHING AIR (VB) 2VB-0049B 2605-3.1 F-02 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2VB @ 50 2605-3.1 E-04 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-VB1 -
MT-RF* -
11/1/93 VB - 1 of 1 I
.w . -. e - - - -,
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW 110W ASME VALVE ACT VALVE ACTUA10R TEST TEST RELIEF JUSTIF OF TEST VALVE NUMitER DIAGRAh! COOR CLASS CATECORY PAS TYPE TYPE REQ?,fT #1 REQ'MT #2 REQST DEFERRAL REMARKS . ALTERNATIVES REV ,
ANNULUS VENTILATION (VE) 2VE-0005A ' 2564-1 G-04 2 A ACT Gate EMO ST-O LT-RF - - - - -
2VE-0006B 2564-1 G-04 2 A ACT Gate EMO ST-O LT-RF - - - - -
2VE-0008A 2564-1 J-02 2 B ACT Gate EMO ST-O - - - - - -
2VE-0010A 2564-1 H-03 2 A ACT Diaphram EMO ST-O LT-RF - - - - -
2VE-0011 2564-1 H-03 2 A PAS Check -
LT-RF - - - - - -
i 11/1/93 VE - 1 of 1
Unit 2 - McGuire Nuclear Station inservice Testing Program T LOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF 0F 111ST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TiPE TYPE REQ 1tT W1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATWES REV DIESEL GENERATOR STARTING AIR (VG) 2VG-0003 2609-4.0- J-12 3 C ACT Check -
MTO-O - - - - - -
' 2VG-0004 2609-4.0 E-12 3 C ACT Check -
MTO-O - - - - - -
2VG-0017 2609-4.0 J-06 3 C ACT Check MTO-O - -
2-MC-VG1 - - -
2VG-0018 2609-4.0 1-06 3 C ACT Check -
MTO-O - -
2-MC-VG1 - - -
2VG-0019 2609-4.0 E-06 3 C ACT Check -
MTO-O - -
2-MC-VG1 - - -
2VG-0020 2609-4.0 D-06 3 C ACT Check -
MTO-O - -
2-MC-VG1 - - -
^ * ' ' ' ' ' '
2VG-0022 2609-4.0 1-13 A ReHet - - - - -
5 PSIG -
C SG
' 2VG-0023 2609-4.0 F-13 C SS G
^ * ' ' ' ' ' ' '
2VG-0024 2609-4.0 C-13 ^ *"*' ' ' ' ' ' '
C SS G 2VG-0033 2609-4.0 L-07 3 C ACT Relief -
SP - - - -
250 PSIG -
2VG-0034 2609-4.0 1-07 3 C ACT Relief -
SP - - - -
250 PSIG -
2VG-0035 2609-4.0 G-07 3 C ACT Relief -
SP - - - -
250 PSIG -
2VG-0036 2609-4 0 C-07 3 C ACT Relief -
SP - - - --
250 PSIG 2VG-0061 2609-4.0 K-02 3 B ACT Solenoid SOV ST-O - - - - - -
2VG-0062 2609-4.0 K-02 3 8 ACT Solenoid SOV ST-Q - - - - - -
2VG-0063 2609-4.0 1-02 3 B ACT Solenoid SOV ST-Q - - - - - -
VG - 1 of 3 11/1/93
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TWE TWE REQ MT 4i REQMI #2 REQST DEFERRAL REA1 ARKS ALTERNATIVES REV DIESEL GENERATOR STARTING AIR (VG) 2VG-0064 2609-4.0 H-02 3 B ACT Solenoid SOV ST-O - - - - - -
2VG-0065 2609-4.0 F-02 3 8 ACT Solenoid SOV ST-O - - - - - -
2VG-0066 2609-4.0 E-02 3 B ACT Solenoid SOV ST-O - - - - - -
2VG-0067 2609-4:0 C-02 3 B ACT Solenoid SOV ST-Q - - - - - -
2VG-0068 2609-4.0 C-02 3 8 ACT Solenoid SOV ST-O - - - - - -
2VG-0079 2609-4.0 1-11 3 C ACT Relief -
SP - - - -
139 PSIG -
2VG-0080 2609-4.0 C-11 3 C ACT Relief -
SP - - - -
139 PSIG -
12VG-0083 26044.0 J-10 3 C ACT Relief -
SP - - - -
139 PSIG -
2VG-0084 2609-4.0 D-10 3 C ACT Relief -
SP - - - -
139 PSIG -
2VG-0115 2609-4.0 K-09 3 C ACT Check -
MTO-O - - - - - -
?VG-0116 2609-4.0 H-09 3 C ACT Check -
MTO-O - - - - - -
2VG-O s 17 2609-4.0 F-09 3 C ACT Check -
MTO-O - - - - - -
2VG-0118 2609-4.0 C-09 3 C ACT Check -
MTO-O - - - - - -
-MC-RR-2VG-5160 2499-VG3 N/A '3 B ACT Solenoid SOV ST-O -
g 2- C~"
2VG-5161 2499-VG3 N/A 3 B ACT Solenoid . SOV ST-O - ~ ^ - ~
G1 2W R-2VG-5162 2499-VG3 N/A 3 0 ACT Solenoid SOV ST-O - , , , ,
2 C-R R-2VG-5163 2499-VG3 N/A 3 B ACT Solenoid SOV- ST-O - , , , ,
11/1/93 VG - 2 of 3
. - _ _ _ - - _ _ _ _ _ _ . __-__ ___-___ ____-_ _ _ _-___ _ __ - __ _ .. _ _ - -- _ . _ _ _ . . _ _ . . _ _ _ _ . ~
Unit 2 - McGuiro Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATCC TEST TEST RELIEF JUSTIFOF- TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS DTE TYPE REQMT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES - REV DIESEL GENERATOR STARTING AIR (VG) 2VG-5170 2499-VG3 N/A 3 B ACT Solenoid SOV ST-O -
y 2MC^ '
2VG-5171 2499-VG3 N/A 3 B ACT Solenoid SOV ST-O -
G B ACT- ST-O
~
2VG-5172 2499-VG3 N/A 3 Solenoid SOV - ' ' '
G 2 C ACT SOV ,
2VG-5173 2499-VG3 N/A 3 B solenoid ST-O -
g 11/1/93 VG - 3 of 3 >
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW 110W ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF IL"ST1F OF TEST DIAGRAM COOR CLASS CATEGORY PAS TYPE TWE REQ'MT 81 REQ'MT 82 REQST DFJERRAL ?EMARKS ALTERNATIVES REV VALVE NUMBER INSTRUMENT AIR (VI) 2VI-0040 2605-1.3 J-13 2 AC ACT Check - MTC-Q LT-RF -
2-MC-Vl3 - MT-RF* -
2VI-0113 2605-1.13 H-13 3- C ACT Relief -
SP - - - -
120 PSIG .-
2VI-0114 ' 2605-1.13 H-14 3 C ACT Relief -
2V14115 2605-1.13 L-01 3 C ACT Relief -
2VI-0116 2605-1.13 L-02 3 C ACT Relief - SP - - - - 120 PSIG -
2VI-0117 2605-1.13 1-07 3 C ACT Retief -
2VI-0118 2605-1.13 1-06 3 C ACT Relief -
SP - - - -
120 PS!G ' -
2VI-0119 2605-1.13 K-08 3 C .ACT Relief -
SP - - - -
120 PSIG -
2VI-0120 2605-1.13 K-08 3 C ACT Relief . SP - - - - 120 PSIG -
2VI-0124 2605-12 B-04 2 AC ACT Check -
MTC-O LT-RF -
2-MC-V12 - MT-RF* -
2VI-0129B 2605-1.3 J-11 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2VI-01488 2605-1.2 E-03 2 A ACT Kerotest EMO ST-O LT-RF - - - -
2VI-0149 2605-1.2 E-05 2 AC 'ACT Check -
MTC-O LT-RF -
2-MC-V12 - MT-RF* -
2VI-0150B 2605-1 2 - C-02 2 A ACT Kerotest .EMO ST-O LT-RF - - - - -
2VI-0160B 2605-1.3 D-11 2 A ACT Kerotest EMO ST-Q LT-RF - - - - -
2VI-0161 2605-1.3 D-13 2 AC ACT Check -
MTC-O LT-RF -
2-MC-V13 - MT-RF* -
2VI-0362A 2605-1.2 D-04 2 A ACT Kerotest EMO ST-O L M1F - -
+ '
11/1/93 VI - 1 of 2
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ . _ _ _ _ _ _ _ _ _ - . _____z______________________ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ ___.
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Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TTST TEST REUEF JUSTIF OF TEST.
VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV INSTRUMENT AIR (VI) 2vi4368 2 sos-1.3 1-07 C ACT Check -
MTO-O - -
2-MC-V11 - - -
C SS F 2VI-o372 260s-1.3 1-08 C. ACT Check -
MTC-Q - -
2-MC-V11 - - -
C SS F 2vi-0373 2 sos-1.3 C-o7 C ACT Check -
MTO-O - -
2-MC-V11 - - -
CLASS F 2vi-0374 2scs-1.3 C-o8 A eck -
M C-Q - -
2WCW - - -
CLASS F 1
11/1/93 VI - 2 of 2
Unit 2 - McGuire Nuclear Station '
Inservice Testing Program FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST FID W TWE DEFERRAL REMARKS ALTERNATIVES REV VALVE NUMBER DIAGRAM 'COOR CLASS CATEGORY P.AS TYPE REQ 3fr #1 REQ 31T #2 REQST CONTAINMENT PURGE VENTILATION (VP) 2VP-0001B - 2576-1 l-06 2 A ACT Butterfly AOV LT-TS - - - -
2VP-0002A 2576-1 1-07 2 A ACT Butterfty AOV LT-TS - - - -
2VP-0003B 2576-1 K-06 2 A ACT Butterffy .AOV - LT-TS - - - - -
2VP-0004A 2576-1 K-07 2 A ACT Butterf!y AOV LT-TS - - - -
2VP-0006B 2576-1 E-06 2 A ACT Butterf'y AOV LT-TS - - - - -
2VP-0007A 2576-1 E-07 2 A ACT Buttenty AOV LT-TS - - - -
2VP-0008B 2576-1 D-06 2 A ACT Butterfly AOV LT-TS - - - -
2VP-0009A - 2576-1 D-07 2 A ACT Butterfly AOV LT-TS - - - - -
2VP-0010A 2576-1 J-08 2 A ACT Butterfly AOV LT-TS - - - - -
2VP-00118 2576-1 J-09 2 A ACT Butterfly ADV LT-TS - - - -
2VP-0012A 2576-1 1-08 2 A ACT Butterfly AOV LT-TS - - - - -
2VP-0013B 2576-1 1-09 2. A ACT Butterf!y AOV LT-TS - - - -
2VP-0015A 2576-1 F-08 2 A ACT Butterfly AOV LT-TS - - - - -
2VP-0016B 2576-1 F-09 2~ A ACT Butterfly AOV LT-TS - - - -
2VP-0017A 2576-1 B-07 2 A ACT Butterfly AOV LT-TS - - - -
2VP-0018B 2576-1 B-06 2 A ACT Butterfly AOV LT-TS - - - - -
2VP-0019A 2576-1 B-08 2 A ACT Butterfly AOV LT-TS - - - -
2VP-00208 2576-1 B-09 2 A ACT Butterfly AOV LT-TS - - - - -
11/1/93- VP - 1 of 1
- _ _ _ _ _ - _ _ - _ - ____ _ _- __-_-____-____.____-______=_---___________-__-_____
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RFUEF JUSTIF CF TEST VALVE N'JMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE tit'E REQ 3tT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV CONTAINMENT AIR RELEASE AND ADDITION (VQ) 2VO4001A 2585-1.0 J-04 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
2VO-0002B 2585-1.0 J-06 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
2VO-0005B 2585-1.0 E-06 2 A ACT Diaphram AOV ST-Q LT-RF - - - - -
2VO-0006A 2585-1.0 E-03 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
11/1/93 VQ - 1 of 1
Unit 2 - McGuire Nuclear Station Inservice Testing Program FLOW FIDW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ MT W1 REQ'MT #2 REQST DEEERRAL REMARKS ALTERNATIVES REV STATION AIR (VS) 2VS-0012B 2605-2.2 F-08 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
, 2VS-0013 2605-22 H48 2 AC ACT Check -
MTC-O LT-RF -
2-MC-VS1 -
MT-RF* -
11/1/93 .
VS - 1 of 1
Unit 2 - McGuire Nuclect Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF 0F TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TiPE TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REY CONTAINMENT AIR RETURN EXCHANGE AND HYDROGEN SKIMMER (VX) 2VX-0001A 2557-1 l-03 2 B ACT Butterfly EMO ST-O - - - - - -
2VX-0002B 2557-1 1-12 2 B ACT Butterfly EMO ST-O - - - - - -
2VX-0030 2557-1 J-03 2 AC ACT Check -
MT C-O LT-RF -
2-MC-VX1 -
MT-RF -
. 2VX-0031 A 2557-1 J-13 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
2VX-0033B 2557-1 J-12 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
2VX-0034 2557-1 K 12 2 A PAS Diaphram -
LT-RF - - - - -
2VX-0040 2557-1 K-03 2. A PAS Diaphram -
LT-RF - - - ~ ~
O 11/1/93- VX - 1 of 1
.. . -- :a
Unit 2 - McGuire Nuclear Station Inservice Test!ng Program FLOW FLOW. ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TFST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYI"E IYPE REQ'htT #1 IEQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV LIQUID WASTE RECYCLE (WL) 2WL-0001 B 2565-1.1 L-11 2 A ACT diaphragm EMO ST-O LT-RF - - - - -
2WL-0002A 2565-1.1 K-13 2 A ACT diaphragm EMO ST-Q LT-RF - - - - -
2WL-0024 2565-1.1 J-14 2 AC ACT Check -
MTC-O LT-RF -
2-MC-WL1 -
MT-RP -
2WL-0039A 2565-1.1 J-05 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2WL-0041B 2565-1.1 K-05 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
I- 2WL-0064A 2565-1.0 J-03 2 A ACT diaphragm EMO ST-Q LT-RF - - - - -
2WL-0065B 2565-1.0 K-05 2 A ACT diaphragm EMO ST-O LT-RF - - - - -
2WL-0264 2565-1.0 J-02 2 AC ACT Relief -
i ~ 2WL-0321 A 2565-7.0 1-05 2 A ACT Butterfly EMO ST-Q LT-RF - - - '- -
2WL-03228 2565-7.0 H-04 2 A ACT Butterfly EMO ST-O LT-RF - - .
2WL-0385 2565-7.0 J-05 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-WL2 -
MT-RP -
j 2WL-13018 2565-1.0 G-03 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
2WL-1302A 2565-1.0 E-04 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
i 11/1/93 WL - 1 of 1
Unit 2 - McGuire Nuclect Sfction Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JU5TIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQMT #1 REQ'MT #2 REQS'T DEFERRAL REMARKS ALTERNATIVES , REV DIESEL GENERATOR ROOM SUMP PUMP (WN) 2 R-2WN-0003 2609-7.0 L-11 3 C ACT Check - MTO,C-Q - , , , ,
2WN-0005 2609-7.0 K-11 3 C ACT CW -
MTO.C-Q -
2 R, , , , ,
2M R-2WN-0007 2609-7.0 J-11 3 c ACT Check -
MTC-O - , , , ,
3 C ACT Check MTO,C-O 2 C R-2WN-0011 2609-7.0 F-11 - - , , , ,
2WC 2WN-0013 2609-7.0 E-11 3 C ACT Check -
MTO.C-O - , , , ,
w 24 C -
2WN-0015 2609-7.0 D-11 3 C ACT Check -
MTC-O - , , , ,
11/1/03 WN - 1 of 1
Unit 2 - McGuire Nuclear Station Inservice Testing Progrom FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TTSI TEST RELIEF JIJSTIF OF TEST VALVE NUMBER DLACRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ %tT #1 REQ'hri #2 REQsT DEFERRAL REMARKS ALTERNATIVES REV a
MAKEUP DEMINERAltZED WATER (YM) 2YM-0115B 1601-2.4 C-09 2- A ACT Kerotest EMO ST-Q LT-RF - - - - -
2YM-0116 1601-2.4 C-04 2 AC ACT Check -
MTC-Q LT-RF -
2-MC-YM1 -
MT-RF* -
11/1/93 YM - 1 of 1
n.
r INSERT TIIE FOLLOWING SECTION UNDER TAB:
II.5 6
.N
)
l UNIT 2 !
.._ ____ _ _____.____ ______,__. _ J d
INSERT TIIE FOLLOWING SECTION UNDER TAB:
II.6 UNIT 2
McGuire Unit 2 Specific Relief Request item Number: 2-MC-RR-NS1 Volve: 2NS-13. 2NS-16, 2NS-30, 2NS-33, 2NS-41, 2NS-46 Flow Diagrom: MC-2563-1.0 Code Category: C ASME Class: 2 Function: Open on flow from containment spray pumps.
Test Requirement: Verify proper volve movement once per three months os required by OMo-1988 Part 10,4.3.2.1.
Basis for Relief: This volve population is verified to full stroke open by sample disassembly (refer to Justification of Deferral 2-MC-NS2.) There are currently two separate subgroups within this population of volves. Group 1 contains the 2 volves associated with RHR discharge flow and group 2 contains the 4 volves associated with NS pump discharge flow. The present disassembly schedule inspects one volve from each group every refueling outage. During the four year history of disassembly, there have been no indications of wear, corrosion or degradotion to the internal components.
This is attributed to the fact that this population of valves is not subjected to flow, unless containment spray is initiated through the spray nozzles. Except for the spray nozzles, there is no flow loop downstream of these check volves.
Due to the restricted access of this volve population, disos-sembly of any volve requires scaffolding to be erected on top of the polar crone. Tools, equipment, parts, electrical power and airlines must also be transported to the work location. Requirements of 29CFR 1910.28,29CFR 1926.452, ANSI A10.8-1977 and Duke Power's scaffolding program place workers at risk during the erection of scaffolding, and to a lesser degree, during the disassembly / reassembly execution.
11/1/93 SECTION 11.6 1OF5
McGuire Unit 2 Specific Relief Request item Number: 2-MC-RR-NSI (cont.)
This concern for personnel safety is also coupled with the fact that these check valves are cover hung, swing check valves.
This type of valve does not allow the technicion to visually or physically verify exact seat reafignment during reassembly, it is therefore possible, though unlikely, to degrade the condition of these volves by excessive disassemblies.
Test Alternative & Frequency: These valves will be re-grouped as all six volves in the group and will be disassembled every four refueling outages. This frequency will meet the present disassembly rate for the four valves in group 2 and extend the disassembly rate for the two volves in group 1. After disassembly, o partial stroke fest will be performed with air flow through the volves. The partial stroke test will not be performed each outage os scaffolding and polar crane use time is required for it also. This schedule of disassembly is to begin during EOC9. All six valves will be disassembled and inspected. A cartial stroke will be performed after reassembly. The valves will not be disassembled again until EOC13.
11/1/93 SECTION 11.6 20F5 ,
i
l McGuire Unit 2 i
Specific Relief Reauest item Number: 2-MC-RR-RN 1 Valve: 2RN-994, 2RN-1006 INSTRUMENT DETAIL: MC-2574-2.1 Code Category: C ASME Class: 3 Function: Provide closure to RN system integrity during a seismic event in the event the non-code piping fails.
Test Requirement: Check valves shall be exercised in accordance with OMa-1988, Port 10. Section 4.3.2.1 and 4.3.2.2.
Basis for Relief: Testing these volves for closure requires passing the design flow through the containment spray heat exchanger.
These heat exchangers are placed in wet lay-up to ,
maintain the heat exchanger integrity. Nuclear service water cools these heat exchangers and they have experienced corrosion from this raw water. Under wet lay-up conditions, the chemistry of the water on the raw water side of the heat exchanger is controlled and maintained for longer life of the heat exchangers. Testing these check volves would severely change the chemistry in the wet lay .
up state which would result in higher corrosion risk and major cost impact.
Test Alternative & FreqJency: These check valves will be closed tested during the RN system flow balance. This test is to be performed on a yearly frequency, which exceeds the refueling outage frequency, but will not be performed during cold shutdowns.
11/1/93 SECTION ll.6 3 OF 5 l
I
McGuire Unit 2 i
Specific Relief Request ,
a item Number: 2-MC-RR-VG1 Valve: 2VGSV5160, 2VGSV5161, 2VGSV5162, 2VGSVS163, 2VGSV5170, 2VGSV5171, 2VGSV5172, 2VGSV5173 INSTRUMENT DETAIL: MC-2499-VG3 Code Category: B ASME Class: 3 Function: Supply control air to the Diesel Generator air / oil booster cylinder, the intercooler temperature controller, and the run/ shutdown cylinder.
Test Requirement: Stroke time test in accordance with OMa - 1988, Part 10, 4.2.
Basis for Relief: Direct observoiion of these valves is impossible. These vot/9s are automatically opened when the diesel generat9 started. Similar valves (the starting air solenoid volves) are tested with acoustic emission monitoring. Umitations on -
available acoustic equipment prevents its use on these valves. Additionally, these valves are scheduled to be '
modified in function during refueling outage 2EOC9. Their new function will not be within the scope of the IST program.
To comply with the requirements of OMa - 1988, Part 10,4.2 would impose a cost burden of additional acoustic moni- !
foring equipment for the quarterly timing. Due to the short time before these valves are modified, no adverse trends could be developed from the quarterly testing.
Test Alternative & Frequency: Design Bases Document MCS-1609,VG-00-0001 paragraph 20.4.3.1 states that these valves shall be tested by the diesel start tests. These tests are performed monthly, and a failure of any one of these valves would result in a failure of the diesel start test. The monthly diesel start test will continue to be performed, and during the refueling outages mentioned above, the function of these volves will be changed such that they are no longer subject to OMa - '
1988, Part 10,4.2 requirements. l f
11/1/93 SECTION 11.6 ;
4OF5 i
^
McGuire Unit 2 Specific Relief Request item Number: 2-MC-RR-WN1 Valve: 2WN-3, 2WN-5, 2WN-7, 2WN-11, 2WN-13, 2WN-15 Flow Diagram: MC-2609-7.0 Code Category: C ASME Class: 3 Function: Pump discharge check valves. All valves isolate parallel pump flow losses. 2WN-3,2WN-5,2WN-11 and 2WN-13 open to allow pump flow and close to isolate opposite pump flow losses. 2WN-7 and 2WN-15 close to isolate non safety related pump from safety related pumps.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Relief: lhese valves are tested with pump operation. The pumps are considered to be dry sump pumps (reference OMa-1988 Part 6,5.5) and are tested on a two year frequency.
Test Alternative & Frequency: Valves will be verified to fully cycle with the pump tests every two years.
6 11/1/93 SECTION ll.6 5OF5 ,
1
INSERT THE FOLLOWING SECTION UNDER Tall:
II.7 i
.1 UNIT 2 ,
, l McGuire Unit 2 Justification of Deferral i
'l item Number: 2 -MC-CA1 j l
Valve: 2CA-37, 2CA-41, 2CA-45, 2CA-49, 2CA-53, 2CA-57, 2CA-61, '
2CA-65 Flow Diagram: MC-2592-1.0 Code Category: C ASME Class: 2 Function: Check flow from the steam generators to Auxiliary )
Feedwater. Open to allow Auxiliary Feedwater supply to j the Steam Generators.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1. ,
l Basis for Deferral: Full stroke testing these valves during power operations would unnecessarily thermal shock the steam generators ,
and feedwater piping. l Test Alternative & Frequency: Valves will be full stroke exercised at cold shutdown.
Closure will be verified quarterly.
11/1/93 SECTION 11.7 1 OF 95
McGuire Unit 2 dystification of Deferral item Number: 2-MC-CA2 Valve: 2CA-165. 2CA-166 Flow Diagram: MC-2592-1.1 Code Category: C ASME Class: 3 Function: Prevents backflow from Auxiliary Feedwater System to Nuclear service Water System until the associated EMOs are closed. EMOs are powered from the same train they serve. Must open to allow assured makeup flow to CA from RN system.
Test Requirement: Verify proper valve movement once per three months as required by OMa 1988 Part 10,4.3.2.1.
Basis for Deferral: Neither full nor partial flow can be put through these valves without contaminating the Auxiliary Feedwater System with raw water, No means exist for alternate testing techniques using air or any other medium. No means exist to test for proper closure without contaminating the Auxiliary Feedwater System with raw water. These volves will not be tested during cold shutdown because sample disassembly is required.
Test Alternative & Frequency: At least one of these two valves will be disassembled and full stroked during each refueling outage, and both valves will have been disassembled and full stroked after two consecutive refueling outages. Failure of one valve to properly full stroke during a refueling outage will result in the remairling valves being disassembled and full stroked during that outage. Sample disassemble will also be used 1 to verify proper closure of valves.
11/1/93 SECTION 11.7 2 OF 95
g . _ . . a=. -
McGuire Unit 2 Justification of Deferral i
l Item Number: 2-MC-CA3 Valve: 2CA-8, 2CA-10, 2CA-12 Flow Diagram: MC-2592-1.1 Code Category: C ASME Class: 3 Function: Auxiliary Feodwater Pump Suction Check volves to prevent diversion of assured auxiliary feedwater source.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Deferral: These volves cannot be tested to close without contaminating the Auxiliary Feedwater System with row water. These valves will not be tested during cold shutdown because sample disassembly is required.
Test Alternative & Frequency: Valves will be sample disassembled during refueling outages to verify volve closure capability. 2CA-8 Is disassembled overy refueling outage, 2CA-10 and 2CA-12 every other refueling outage on a staggered basis.
.i 11/1/93 SECTION II.7 3 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-CFl Valve: 2CF-26AB, 2CF-28AB, 2CF-30AB, 2CF-35AB Flow Diagram: MC-2591-1.1 Code Category: B ASP r Class: 2 Function: Provide feedwater and containment isolation.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Closure of these valves would isolate the Steam Generator feedwater which could result in a severe transient in the Steam Generator, resulting in a Unit trip.
Test Alternative & Frequency: Valve will be cycled and tirned during cold shutdown.
11/1/93 SECTION ll.7 4 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-CF2 Valve: 2CF-17AB. 2CF-20AB, 2CF-23AB. 2CF-32AB Flow Diagram: MC-2591-1.1 Code Category: B ASME Class:. ANSI B31.1.0 (1967)
Function: Feedwater control.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Closure of these valves would isolate the Steam Generator feedwater which could result in a severe transient in the Steam Generator, resulting in a Unit trip.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
i I
11/1/93 SECTION 11.7 5 OF 95 t
McGuire Unit 2 Justificathn of Deferral 1
Item Number: 2-MC-CF3 Valve: 2CF-126B, 2CF- 127B, 2CF-128B, 2CF-129B Flow Diagram: MC-2591-1.1 l
Code Category: B ASME Class: 2 Function: Opens to provide startup feedwater supply to the steam generators.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, A2.1.1.
Basis for Deferral: Cycling valves during power operation could induce unwanted transients in the steam generators. This would result in an increase in flow to the main feedwater nozzles cousing vibrations in the preheater section of the steam generators.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION 11.7 6 OF 95
k McGuire Unit 2 i
Justification of Deferral 1
i ltem Number: 2-MC-CF4 Valve: 2CF-104AB. 2CF-105AB, 2CF-106AB, 2CF-107AB Flow Diagram: MC-2591-1.1 Code Category: B ASME Class: ANSI B31.1.0 (1967)
Function: Provides tempering flow to the steam generators. ;
Test Requirement: Stroke time test in accordance with OMa-1988 Port 10, 4.2.1.1, Basis for Deferrol: Closing this volve during operation could result in loss of Steam Generator level control and result in a Unit trip.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
i 11/1/93 SECTION II.7 7 OF 95 l
McGuire Unit 2 1
Lustification of Deferral i
ltem Number: 2-MC-CFS Valve: 2CF-152, 2CF-154, 2CF-156, 2CF-158 Flow Diagram: MC-2591-1.1 Code Category: C ASME Class: 2 Function: Opens to allow tempering flow to the Steam Generator auxiliary feedwater nozzles. Closes to form pressure boundary for auxiliary feedwater.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Deferral: During normal operation, there is constant flow through these valves to keep the auxiliary feedwater nozzJes tempered. Testing these va!ves would require supplying the Steam Generators with cold water and thus thermally shocking these nozzles. .
Test Alternative & Frequency: Valve will be fu!I stroke exercised at cold shutdown.
j 11/1/93 SECTION ll.7 ,
8 0F 95 I l
McGuire Unit 2 Justification of Deferral ;
item Number: 2-MC-FW1 Valve: 2FW-27A i
~
Flow Diagram: MC-2571-1.0 Code Category: B ASME Class: 2 Function: Isolates low pressure Injection from the Refueling Water Stor-age Tank.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferrol: Closure of this valve during normal power operation would render o!! low pressure !njection inoperable. This valve is opened and power removed above Mode 4 per Tech Spec 4.5.2.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION 11.7 9 OF 95
McGuire Unit 2 ,
Justification of Deferr_a_1 -
Item Number: 2-MC-FW2 Valve: 2FW-28 Flow Diagram: MC-2571-1.0 Code Category: C ASME Class: 2 Function: Opens to allow low pressure injection flow. Closes to prevents reverse flow to the Refueling Water Storage Tank, thereby preventing pressurization of the tank.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Deferral: Valve cannot be full stroked during power operation since the only full flow path is into the RCS by the Residual Heat Removal pumps. These pumps cannot overcome RCS system pressure.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
11/1/93 SECTION 11.7 10 OF 95
l McGuire Unit 2 Justification of Deferral item Number: 2-MC-lAl Valve; 2l A-5260, 2l A-5270, 21A-5280, 21A-5290, 2lA-5300, 2lA-5310, 2lA-5320, 2lA-5330, 21A-5340, 21A-5350, 2l A-5360, 2i A-5370, 21A-5380, 2lA-5390 Flow Diagram: MC-2499-!Al Code Category: A,C ASME Class: 2&3 Function: 2l A-5260, 5270, 5280, 5290, 5300, 5310, 5320 and 5330 prevent loss of air from receiver tank on each personnel airlock door in the event of loss of instrument air supply to door seals. These check volves form a pressure boundary for the inflatable seals.
21A-5340 and 5350 provide the inside containment isolation barrier in the event of a break on the flexible hose connection on the air supply to the door seals. The outside isolation volves are 21A-5080 and 5160. These check valves are on the auxiliary building side of the airlocks. ;
21A-5360, 5370, 5380 and 5390 provide double isolation on the reactor building side of the airlocks for the pressure relief line.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10, 4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10, 4.2.2.2.
- 3) Leak test in accordance with Technical Specification 4.6.1.3.d.
Basis for DeferTal: These valves cannot be practically tested during operation due to the design of the system.
Test Alternative & Frequency: Valves will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at a six month frequency per Tech Spec 4.6.1.3.d.
11/1/93 SECTION 11.7 11 OF 95
McGuire Unit 2 1
Justification of Deferral item Number: 2-MC-kcl Valve: 2KC-424B, 2KC-425A Flow Diagram: MC-2573-3.1 Code Category: A ASME Class- 2 Function: Provide containment isolation for penetration M-320.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1. ,
Basis for Deferral: Failure of either of these valves in the closed position during testing would inhibit the normal flow path from the reactor coolant pump motor coolers. This action could result in damage to the pumps.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION 11.7 12 OF 95
.i l
-l 1
McGuire Unit 2 l
Justification of Deferral Item Number: 2-MC-KC2 Volve: 2KC-338B Flow Diagram: MC-2573-3.1 Code Category: A ASME Class: 2 Function: Provide containment isolation for penetration M-327.
Test Requirement: Stroke time test in accordonce with OMo-1988 Port 10, 4.2.1.1.
Basis for Deferrol: Failure of this volve in the closed position during testing would inhibit flow to the reactor vessel support coolers. This action could result in domoge to the reactor vessel, Test Alternative & Frequency: Volve will be cycled and timed during cold shutdown.
J 11/1/93 SECTION 11.7 13 OF 95
y McGuire Unit 2 Justification of Deferral item Number: 2-MC-KC3 Valve: 2KC-332B, 2KC-333A Flow Diagram: MC-2573-3.1 Code Category: A ASME Class: 2 Function: Provide containment isolation for penetration M-355.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Failure of one of these valves in the closed position during testing would inhibit flow through the reactor coolant drain tank heat exchanger. No alternate flowpath for cooling water to the heat exchanger exists. Without flow to the heat exchanger, the drain tank would become over pressurized and steam would be released.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
4 11/1/93 SECTION 11.7 14 OF 95
McGuire Unit 2 Justification of Deferral-item Number: 2-MC-KC4 Volve: 2KC-320A Flow Diagram: MC-2573-3.1 Code Category: A ASME Class: 2 Function: Provide containment isolation for penetration M-376.
Test Requirement: Stroke time test in accordance with OMo-1988 Port 10,
'4.2.1.1.
Basis for Deferrol: Failure of this volve in the closed position during te ;.ing would inhibit flow through the reactor coolant drain tank heat exchanger. No alternate flowpath for cooling water to the heat exchanger exists. Without flow to the heat l exchanger, the drain tank would become over pressurized i and steam would be released.
Test Alternative & Frequency: Volve wl!I be cycled and timed during cold shutdown.
l 1
i 11/1/93 SECTION 11.7 15 OF 95
e McGuire Unit 2 Lustification of Deferral item Number: 2-MC-KC5 Valve: 2KC-280 Flow Diagram: MC-2573-3.1 Code Category: AC ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection of line between 2KC-332B and 2KC-333A on penetration M-355.
Test Requirement: 1) Verify proper volve movement once per three months as
. required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: This valve cannot be practically tested during operation due to the design of the system.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
l I
11/1/93 SECTION 11.7 16 OF 95 i
I
McGuire Unit 2 Justification of Deferral item Number: 2-MC-KC6 Valve: 2KC-322 Flow Diagram: MC-2573-3.1 Code Category: AC ASME Class: 2 Function: Provides containment isolation on penetration M-376.
Test Requirement: 1) Verify proper volve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Port 10,4.2.2.2.
Basis for Deferrol: This valve cannot be practically tested during operation due to the design of the system.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION 11.7 17 OF 95
I t
p McGuire Unit 2.
Justification of Deferral Item Number: 2-MC-KC7 Valve: 2KC-279 Flow Diagram: MC-2573-3.1 Code Category: AC ASME Class: 2 Function: Provides containment isolation and thermal over t pressurization protection of line between 2KC-424B and 2KC-425A on penetration M-320.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal. t Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION ll.7 18 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-KC8 Valve: 2KC-340 Flow Diagram: MC-2573-3.1 Code Category: AC ASME Class: 2 Function: Provides containment isolation on penetration M-327.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferrol: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak iest performed in i accordance with 10CFR50 Appendix J at refueling outage frequency.
f 11/1/93 SECTION l1.7 19 OF 95
McGuire Unit 2 f
Justification of Deferral item Number: 2-MC-KC9 Valve: 2KC-47 Flow Diagram: MC-2573-4.0 Code Category: AC ASME Class: 2 Function: Provides containment isolation on penetration M-322. ,
Test Requirement: 1) Verify proper volve movement once per three months as required by OMa-1988 Part 10.-4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Port 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying volve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage '
frequency.
11/1/93 SECTION 11.7 20 OF 95
McGuire Unit 2 Justification of Deferral Item Number: 2-MC-NBl Valve: 2NB-262 Flow Diagram: MC-2556-3.0 Code Category: A,C ASME Class: 2 Function: Provides containment isolation on penetration M-259.
Test Requirement: 1) Verify proper volve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak fest once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying volve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
l 11/1/93 SECTION 11.7 21 OF 95
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McGuire Unit 2 l
l Justification of Deferral item Number: 2-MC-NCl Valve: 2NC-32B, 2NC-34A, 2NC-36B Flow Diagram: MC-2553-2.0 Code Category: B ASME Class: 1 Function: Reactor Coolant System PORV. Opens to relieve pressure for the primary system.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis fcr Deferral: PORVs do not serve a safety function when unit is at operating temperature and pressure. PORVs protect the Reactor Coolant System from over pressurization during LTOP conditions.
Test Alternative & Frequency: Stroke time testing will be performed at cold shutdown and in all cases prior to entering LTOP conditions in accordance with Generic Letter 90-06. Testing will not be required more often than once per quarter as defined in OMa-1988 Part 10,4.2.1.1.
11/1/93 SECTION 11.7 22 OF 95
t McGuire Unit 2 Justification of Deferral .
Item Number: 2-MC-NC2 Valve: 2NC-272AC, 2NC-273AC, 2NC-274B, 2NC-275B Flow Diagram: MC-2553-2.1 Code Category: B ASME Class: 1 Function: Reactor vessel head vent.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Opening these valves at full pressure could cause damage to the valve seating surfaces. A reactor coolant leak could be caused.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
1111/93 SECTION ll.7 23 OF 95
McGuire Unit 2 l
Justification of Deferral i
Item Number: 2-MC-NC3 ,
Valve: 2NC-259, 2NC-261 Flow Diagram: MC-2553-4.0 Code Category: AC ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection of line between 2NC-195B and 2NC-196A on penetration M-361, and line between 2NC-141 and 2NC-142 on penetration M-326 respectively.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10. 4.2.2.2.
1 Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION 11.7 24 OF 95
_. McGuire Unit 2 Justification of Deferral item Number: 2-MC-ND1 Valve: 2ND-18, 2ND-2AC Flow Diagram: rL-2561-1.0 Code Category: A f
ASME Class: 1 Function: Provides suction for Residual Heat Removal pumps during normal cool down.
Test Requirement: 1) Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.3.
Basis for Deferral: These valves have on interlock which prevents their opening when the Reactor Coolant System pressure is greater than 38.5psig. :
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
Valve will be leak tested in accordance with Tech Spec 4.4.6.2.2.
11/1/93 SECTION l1.7 25 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-ND2 Valve: 2ND-58A Flow Diagram: MC-2561-1.0 Code Category: B ASME Class: 2 Function: Provides suction to the Centrifugal Charging Pumps and Safety injection Pumps from the Residual Heat Removal system.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10.
4.2.1.1.
Basis for Deferrol: Opening this volve during operation would render both trains of Residual Heat Removal inoperable.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION 11.7 26 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-ND3 Valve: 2ND-15B, 2ND-30A Flow Diagram: MC-2561-1.0 Code Category: B ASME Class: 2 Function: ND Heat Exchanger Outlet Crossover Block Valves.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: One of the ECCS safety analysis assumptions is that each train of ND can supply flow to all four cold legs. If either of these valves failed closed during testing then only two cold legs could be supplied by each train of ND. This would make both trains of ND inoperable.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION 11.7 27 OF 95
McGuire Unit 2 r
Justification of Deferral Item Number: 2-MC-ND4 Valve: 2ND-70 Flow Diagram: MC-2561-1.0 Code Category: C ASME Class: 2 Function: Opens to provides suction to the Centrifugal Charging Pumps and Safety injection Pumps from the Residual Heat Removal system. Closes to provide suction pressure boundary for the Centrifugal Charging Pumps and Safety injection Pumps Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10, 4.3.2.1.
Basis for Deferral: Valve cannot be full stroked during power operation since 2ND-58A would have to be opened, rendering both trains of ND inoperable. Additionally, the flow requirements to full stroke this volve cannot be achieved with the Reactor Coolant System pressurized.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
r 11/1/93 SECTION 11.7 28 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-NDS Valve: 2ND-71 Flow Diagram: MC-2561-1.0 4 Code Category: C ASME Class: 2 Function: Opens to provides suction to the Centrifugal Charging Pumps and Safety Injection Purnps from the Residual, Heat Removal system. Closes to provide suction pressure boundary for the Centrifugal Charging Pumps and Safety injectiori Pumps Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Port 10,4.3.2.1, Basis for Deferral: Valve cannot be full stroked during power operation since 2NI-136B would have to be opened, rendering both trains of ND inoperable. Additionally, the flow requirements to full stroke this valve cannot be achieved with the Reactor Coolant System pressurized.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
11/1/93 SECTION 11.7 29 OF 95
McGuire Unit 2 dystificatiollof Deferral item Number: 2-MC-ND6 Valve: 2ND-8. 2ND-23 Flow Diagram: MC-2561-1.0 Code Category: C ASME Class: 2 Function: Residual Heat Removal pump discharge check valve.
Test Requirement: Verify proper volve movement once per three months as required by OMa-1988 Part 10,4.3.2.1. ,
Basis for Deferral: Valves cannot be full stroke exercised during power operation since the only full flow path is into the Reactor Coolant System and the ND pumps cannot overcome RCS pressure.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown. Valves will be partially stroked quarterly. The opposite train volves ,
will be tested closed quarterly except when the opposite train of ND is in service.
11/1/93 SECTION 11.7 30 OF 95
L McGuire Unit 2 Justification of Deferral item Number: 2-MC-NF1 Valve: 2NF-229 Flow Diagram: MC-2558-4.0 Code Category: A,C ASME Class: 2 Function: Provides containment isolation on penetration M-373.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.10CFR50 Appendix J requires measurement of local leak rate using air or nitrogen.
Basis for Deferrol: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: 1) Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
- 2) Leak Rate testing of the valve will be performed per Tech Spec 4.6.1.2.d.4).
11/1/93 SECTION ll.7 31 OF 95
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.i McGuire Unit 2 Justification of Deferral Item Number: 2-MC-Nil Valve: 2NI-9A, 2NI-10B Flow Diagram: MC-2562-1.0 Code Category: B ,
ASME Class: 2 !
Function: Flowpath for Centrifugal Charging Pumps to Reactor Coolant System Cold Legs.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, l 4.2.1.1.
Basis for Deferral: Opening either of these valves during operation would increase the charging flow into the Reactor Coolant i System resulting in on increase of pressure and a rapid - ,
change in the primary system boron concentration. This A could create a transient and possible unit shutdown. ;
1 Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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i 11/1/93 SECTION 11.7 -
32 OF 95
i McGuire Unit 2 Justification of Deferral l Item Number: 2-MC-N12 Valve: 2N1-100B f Flow Diagram: " .-2562-3.0 Code Category: B
^ SME Class: 2 Function: Flowpath from the Refueling Water Storage Tank the Safety injection Pump suction. l Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Closing this valve during operation would render both trains of Safety injection inoperable. This volve is opened and power removed above Mode 4 per Tech Spec 4.5.2. ,
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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I 11/1/93 SECTION 11.7 .
33 0F 95 ,
i T
McGuire Unit 2 i
Justification of Deferral item Number: 2-MC-N13 Valve: 2NI-147A, 2N1115B Flow Diagram: MC-2562-3.0 Code Category: B ASME Class: 2 Function: 2NI-147A provides flowpath for both trains of Safety injection recirculation line to the Refueling Water Storage !
Tank. 2NI-115B provides flowpath for A train of Safety Injection recirculation line to the Refueling Water Storage ,
Tank.
e Test Requirement: Stroke time test in accordance with OMa-1988 Part 10.
4.2.1.1, ;
Basis for Deferral: Closing either of these volve during power operation renders both trains of Safety injection inoperable. 2NI-147A is open with power removed above Mode 4 per Tech Spec t 4.5.2. t Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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o 11/1/93 SECTION 11.7 34 OF 95
McGuire Unit 2 u
J_u_s_tification of Deferral item Number: 2-MC-N14 Valve: 2NI-121 A. 2NI-152B Flow Diagram: MC-2562-3.0 Code Category: B ASME Class: 2 Function: Isolaies Safety injection flow to the hot legs.
Test Requirement: Stroke time test in accordance with OMa-1988 Port 10, 4.2.1.1.
Basis for Deferrol: These valves are closed with power removed above Modo 4 per Tech Spec 4.5.2.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 35 OF 95
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McGuire Unit 2 ;
lustification of Delerral item Number: 2-MC-N15 Valve: 2NI-162A flow Diagram: MC-2562-3.1 Code Category: B A3ME Class: 2 Function: Isolates Safety Injection flow to the cold legs.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: This valve is opened and power removed above Mode 4 per Tech Spec 4.5.2.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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1 11/1/93 SECTION 11.7 36 OF 95
McGuire Unit 2 i Justification of Deferra_1 Item Number: 2-MC-NI6 Valve: 2NI-103A Flow Diagram: MC-2562-3,0 Code Category: B ASME Class: 2 Function: Provides A Train Safety Injection Pump suction flow from the Refueling Water Storage Tank. Also provides a flowpath for B Train Residual Heat Removal pump discharge to B Train Chemical and Volume Control pump suction.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Closing this valve during power operations degrades both trains of Chemical and Volume Control.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION ll.7 37 OF 95
l McGuire Unit 2 Justification of Deferral item Number: 2-MC-NI7 Valve: 2NI-173A, 2NI-178B Flow Diagram: MC-2562-3.1 Code Category: B ASME Class: 2 Function: Provides flowpath for Residual Heat Removal to the cold legs.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10,
! 4.2.1.1.
Basis for Deferral: These valves are opened and power removed above Mode 4 per Tech Spec 4.5.2.
Test Alternative & Frequency: Valve wiil be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 38 0F 95 ,
McGuire Unit 2 Justification of Deferral item Number: 2-MC-N18 Valve: 2NI-334B Flow Diagram: MC-2562-3.0 Code Category: B ASME Class: 2 Function: Provides flowpath from B Train of Residual Heat Removal to B Train of Chemical and Volume Control, and from A Train of Residual Heat Removal to A Train of Safety injection.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Closing this valve during power operation degrades both trains of Safety injection.
Test Alternative & Frequency: Valve will be cycled and timed during coid shutdown.
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11/1/93 SECTION 11.7 39 OF 95 l
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McGuire Unit 2 Justification of De.tertal item Number: 2-MC-N19 Valve; 2Nt-183B Flow Diagram: MC-2562-3.1 Code Category: B ASME Class: 2 Function: Isolates Residual Heat Removal flow to the hot legs.
Terr Requirement: Stroke time test in accordance with OMa-1988 Part 10.
4.2.1.1.
Basis for Deferral- This valve is closed and power removed above Mode 4 per Tech Spec 4.5.2.
Test Alternative & Frequency: Valve will be cycled and limed during cold shutdown.
11/1/93 SECTION 11.7 40 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-N110 Valve: 2Ni-1848, 2NI-185A Floa Diagrom: MC-2562-3.0 Code Category'. B ASME Class: 2 Function: Provides flowpath from the Containment Sump to the Residual Heat Removal Pump and the Containment Spray Pump suction.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Opening these valves during power operation would allow water to enter lower containment. To prevent this.1FW-27A would have to be closed, rendering both trains of Residual Heat Removalinoperable. Volds in suction piping would be created requiring fill and vent operations to pre-vent ECCS pump damage.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
b 11/1/93 SECTION 11.7 410F 95 '
McGuire Unit 2 dus_tification of Deferral item Number: 2-MC-NI11 Valve: 2N1-332A, 2NI-333B Flow Diagram: MC-2562-3.0 Code Category: B ASME Class: 2 -u Function: Provides flowpath to Centrifugal Charging Pumps and Safety injection Pumps from Residual Heat Removal Pumps '
during recirculation phase.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Opening these valves during power operations requires 2NI-334B to be closed to prevent aligning FWST to the suc-tion of the Centrifugal Charging Pumps. Injecting FWST bo- '
ron concentrated water into the Reactor Coolant System would induce a transient. Closing 2NI-334B degrades both trains of Safety injection.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION ll.7 42 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-Nil 2 Valve: 2NI-15, 2NI-17, 2NI-19, 2NI-21, 2NI-347, 2NI-348, 2NI-349, 2NI-354 Flow Diagram: MC-2562-1.0 Code Category: C ASME Class: 1 Function: Opens to allow flow to the cold legs from the Centrifugal Charging Pumps.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10, 4.3.2.1.
Basis for Deferral: Injecting flow through these volves from the Centrifugal Charging Pumps during power operations could result in unnecessary thermal shock to the injection nozzles.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown, e
11/1/93 SECTION 11.7 43 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-Nil 3 Valve: 2NI-12 Flow Dlogram: MC-2562-1.0 Code Category: C ASME Class: 2 Function: Flowpath for Centrifugal Charging Pumps to Reactor Coolant System cold legs.
Test Requirement: Verify proper volve movement once per three months as required by OMa-1988 Port 10,4.3.2.1.
Basis for Deferral: Injecting flow through this volve from the Centrifugal -
Charging Pumps during power operations could result in unnecessary thermal shock to the injection nozzles.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown, 11/1/93 SECTION 11.7 44 OF 95 I
McGuire Unit 2 dlystification of De.Lerral item Numbei: 2-MC-Nil 4 Valve: 2N1-101 Flow Diagram: MC-2562-3.0 Code Category: C ASME Clqss: 2 Function: Opens to allow flow from the Refueling Water Storage Tank to the Safety injection Pumps. Closes to provide suction prwsure boundary for these pumps from the Residual Heat Removal Pump discharge.
Test Requirement: Verify proper valve movement once per ihree months as required by OMa-1988 Part 10, 4.3.2.1.
Basis for Deferrol: Valve cannot be full stroke tested during power operation since the Safety injection Pumps cannot overcome Reactor Coolant System pressure. Closure cannot be verified quarterly since both trains of Residual Heat Removal would be rendered inoperable.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown. Valve will be partial stroked quarterly.
11/1/93 SECTION 11.7 45 OF 95
i McGuire Unit 2 Justification of Deferral item Number: 2-MC-Nil 5 Valve: 2NI-116, 2NI-148 Flow Diagram: MC-2562-3.0 Code Category: C ASME Class: 1 Function: Pump discharge check valve, opens to allow Safety injection Flow. Closes to prevent opposite train flow losses. -
Test Requirement: Verify proper valve movement once per three months as required by.OMa-1988 Part 10,4.3.2.1.
Basis for Deferral: Valve cannot be full or partial stroke tested during power operation since the Safety injection Pumps cannot over-come Reactor Coolant System pressure.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown. Valve will be verified closed quarterly.
i 11/1/93 SECTION 11.7 46 OF 95 l
McGuire Unit 2 Justifica_ tion of Deferral item Number: 2-MC-Nil 6 Volve: 2NI- t 24, 2NI-128, 2Ni-156, 2NI-157, 2NI-159, 2Ni-160 .
^
Flow Diagram: MC-2562-3.0 Code Category: AC ASME Class: 2 Function: 1) Opens on flow from the Safety injection Pumps to the hot legs.
- 2) Reactor Coolant System pressure boundary.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMo-1988 Port 10,4.3.2.1,
- 2) Leck test once per two years in accordance with OMa-1988 Part 10,4.2.2.3.
Basis for Deferral: Valves cannot be full or partial stroke tested during power operation since the Safety injection Pumps cannot over-come Reactor Coolant System pressure.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown. Leak test in accordance with Tech Spec 4.4.6.2.2.
11/1/93 SECTION 11.7 47 OF 95
L McGuire Unit 2 4
dp_stification of Deferral i
Item Number: 2-MC-Nll7 Valve: 2NI-165, 2Ni-167, 2NI-169, 2NI-171 ,
Flow Diagram: MC-2562-3.1 Code Category: AC ASME Class: 1 Function: 1) Opens on flow from the Safety injection Pumps to the cold legs,
- 2) Reactor Coolant System pressure boundary.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.3.
Basis for Deferral: Valves cannot be full or partial stroke tested during power operations since the Safety injection Pumps cannot overcome Reactor Coolant System pressure.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown. Leak test in accordance with Tech Spec 4.4.6.2.2.
I 11/1/93 SECTION l1.7 48 OF 95 i
L McGuire Unit 2 Justification of Deferra_l item Number; 2-MC-Nil 8 Valve: 2Ni-175, 2N1-176, 2Ni-180, 2NI-181 Flow Diagram: MC-2562-3.1 Code Category: AC ASME Class: 1 Function: 1) Opens on flow from the Residual Heat Removo! Pumps to the cold legs.
- 2) Reactor Coolant System pressure boundary.
Test Requirement: 1) Verify prdper volve movement once per three months as required by OMa-1988 Port 10,4.3.2.1.
- 2) Leak test once per two years in accordance with OMa-1988 Part 10,4.2.2.3.
Basis for Deferral: Valves cannot be full or partial stroke tested during power operation since the Residual Heat Removal pumps cannot overcome Reactor Coolant System pressure.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown. Leak test in accordance with Tech Spec 4.4.6.2.2.
11/1/93 SECTION 11.7 49 OF 95 l
I McGuire Unit 2 i
Justification of Deferral ,
l Item Number: 2-MC-Nil 9 Valve: 2NI-125, 2NI-126, 2NI-129, 2N!-134 Flow Diagram: MC-2562-3.0 Code Category: AC ASME Class: 1 Function: 1) Opens on flow from the Residual Heat Removal Pumps to the hot legs.
- 2) Reactor Coolant System pressure boundary.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per two years in accordance with OMa-1988 Part 10,4.2.2.3. ,
Basis for Deferral: Valves cannot be full or partial stroke tested during power operation since the Residual Heat Removal pumps cannot overcome Reactor Coolant System pressure.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown. Leak test in accordance with Tech Spec 4.4.6.2.2.
11/1/93 SECTION 11.7 50 OF 95
McGuire Unit 2 dpstification of Deferral item Number: 2-MC-NI20 Valve: 2Ni-136B Flow Diagram: MC-2562-3.0 Code Category: B ASME Class: 2 Function: Provides suction to the Centrifugal Charging Pumps and Safety injection Pumps from the Residual Heat Removal System.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1, Basis for Deferral: Opening this volve during power operation renders both trains of Residual Heat Removalinoperable.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 .
510F 95
McGuire Unit 2 Justification of Deferral Item Number: 2-MC-NI21 Valve: 2NI-48 Flow Diagram: MC-2562-2.0 Code Category: A,C -
ASME Class: 2 Function: Provides containment isolation on penetration M-330.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1,
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION 11.7 52 OF 95.
A
McGuire Unit 2 Justification of Deferral item Number: 2-MC-N122 Valve: 2NI-59, 2Ni-70, 2NI-81, 2NI-93 Flow Diagram: MC-2562-2.0, MC-2562-2.1 Code Category: AC ASME Class: 1 Function: Opens on flow from the NI cold leg occumulator to the Reactor Coolant System. Reactor Coolant Boundary volve.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Port 10,4.2.2.3.
- 3) Leak test in accordance with Tech Spec 4.4.6.2.2.
Basis for Deferral: Valves cannot be full or partial stroked during power operation since the accumulator pressure is ~600 psig and cannot overcome RCS pressure. Volves will not be tested during cold shutdown since disassembly is required.
Disassembly would render one train of RHR inoperable for on extended period of time.
Test Alternative & Frequency: Valves will be full stroked at refueling by disassembly on a sompte basis. All volves will be partial stroked at. refueling.
Partial stroke will not be performed at cold shutdown since Tech Spec 4.4.6.2.2 requires leak testing offer initiating flow -
through these va'ves and does not require leak testing more often than (coce per nine months. Valves will be verified closed by I ?ak test performed in accordance with Tech Spec A.4.6.23.
11/1/93 SECTION 11.7 53 OF 95
g McGuire Unit 2 Justification of Deferral item Number: 2-MC-N123 Valve: 2NI-436 '
Flow Diagram: MC-2562-2.1 Code Category: A,C ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection for penetration M-321.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in
- accordance with 10CFR50 Appendix J of refueling outage frequency. ,
11/1/93 SECTION 11.7 54 OF 95
McGuire Unit 2 L
Lustification of Deferral item Number: 2-MC-NI24 Valve: 2NI-60. 2NI-71, 2NI-82, 2NI-94 Flow Diagram: MC-2562-2.0, MC-2562-2.1 Code Category: AC ASME Class: 1 Function: Opens on flow from the Ni cold leg accumulator to the Reactor Coolant System. Reactor Coolant Boundary valve.
Test Requirement: 1) Verify proper volve movement once per three months as required by OMa-1988 Port 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Port 10,4.2.2.3.
- 3) Leak test in accordance with Tech Spec 4.4.6.2.2.
Basis for Deferral: Valves cannot be full or partial stroked during power operation since a driving head which can overcome RCS pressure does not exist. Instrumentation is not present to-measure the flow through the individual valves. Valves will not be tested during cold shutdown since disassembly is required. Disassembly would render one train of RHR inoperable for on extended period of time.
Test Alternative & Frequency: Valves will be full stroked at refueling by disassembly on a sample basis. All valves will be partial stroked at refueling.
Partial stroke will not be performed at cold shutdown since Tech Spec 4.4.6.2.2 requires leak testing offer initiating flow through these valves and does not require leak testing more often than once per nine months. Valves will be verified closed by leak test performed in accordance with Tech Spec 4.4.6.2.2.
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11/1/93 ' SECTION 11.7 55 OF 95 l
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McGuire Unit 2 Justification of Deferral item Number: 2-MC-NM1 Valve: 2NM-420, 2NM-421 Flow Diagram: MC-2572-1.0 Code Category: AC ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection for penetrations M-235 and M-309 respectively.
Test Requiremertt: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10, 4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve wii! be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION 11.7 I
56 0F 95
McGuire Unit 2 Lustification of Deferral item Number: 2-MC-NS1 Valve: 2NS-388, 2NS-43A Flow Diagram: MC-2563-1.0 Code Category: B ASME Class: 2 Function: Auxiliary Spray Nozzle header isolation.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Opening either of these valves during power operation renders both trains on Residual Heat Removal Inoperable.
Test Alternative & Frequency; Valve will be cycled and timed during cold shutdown.-
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f 11/1/93 SECTION 11.7 57 OF 95
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McGuire Unit 2 JMs.tllication of Deferral
. Item Number: 2-MC-NS2 Valve: 2NS-13, 2NS-16, 2NS-30, 2NS-33, 2NS-41, 2NS-46 Flow Diagram: MC-2563-1.0 Code Category: C ASME Class: 2 Function: Open on flow from contalnment spray pumps.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10, 4.3.2.1.
Basis for Deferral: Full stroke exercising of these check volves is not practical since there is no external Indication of disk movement, Full stroke exercising would require for the pumps and spray nozzles to be activated which would require a large scale cleanup effort Valves will not be tested during cold shutdown since sample disassembly is required.
Test Alternative & Frequency: These volves will be verified to fully cycle by sample disas-sembly at refueling outage frequencies.
Mole Relief is being requested on these valves. Refer to relief re-quest 2-MC-RR-NS1, When relief is granted, this Justification Of Deferral will be deleted.
11/1/93 SECTION ll.7 58 OF 95
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McGuire Unit 2 slustificatLon oLDeferraj ltem Number: 2-MC-NS3 Valve: 2NS-4, 2NS-21 Flow Diagram: MC-2563-1.0 Code Category: C ASME Class: .2 Function: Opens to allow flow from the Refueling Water Storage Tank to the Containment Spray Pump suction. Closes to prevent flow from the Containment Recirculation Sump to the Refueling Water Storage Tank.
Test Requirement: Verify proper volve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Deferral: Full stroke exercising with flow would require for the pumps and spray nozzles to be activated which would require a large scale cleanup effort. The system design does not pro-vide any indication for verifying closure upon flow reversal.
Test Alternative & Frequency: Full stroke testing will be achieved by sample disassembly.
At least one of these valves will be disassembled during _
each refueling outage, and both valves will have been disassembled and full stroked after two consecutive outages. Sample disassembly will also verify closure. Fail-ute of one of volve to properly full stroke during a refueling outage will result in the remaining valve being disassem-blod and full stroked during that outage. Valves will be partlal stroked quarterly.
11/1/93 SECTION 11.7 59 OF 95
McGuire Unit 2 t
JustlHgallon of Delegaj Item Number: 2-MC-NS4 Valve: 2NS-140, 2NS-141 ;
flow Diagram: MC-2563-1.0 Code Category: A,C ASME Class: 2 t
function: Must open to allow Containment Spray to the spray ring headers. Must close to prevent column separation of water in the header after initial building spraydown and '
pump shutdown. During this time, the column of water in the vertical piping up to the spray rings could separate, i creating a vold in the system at sub-atmospheric pressure.
Upon purnp restart,1he collapse of this vold would damage ;
the piping system.
Test Requirement: 1) Verify proper valve movement once per three months os required by OMo-1988 Part 10,4.3.2.1. i
- 2) Look test once per 2 years in accordance with OMa-1988 Port 10, 4.2.2.3.
Basis for Deferrol: Full stroke exercising of these check valves is not practical )
since there is no exteri.alindication of disk movement. Full stroke exercising would require for the pumps and spray nozzles to be activated which would require a large scale cleanup effort, Volves will not be tested during cold shutdown since sample disassembly is required, >
Test Alternative & Frequency: Valves will be verified to full stroke open using sample disos-sembly every other refueling outage on a staggered basis.
Valves will be partial stroked quarterly. Valves will be leak tested at refueling outages eak testing will also verify closure of 1he>c valves.
11/1/93 SECTION ll.7 GO OF 95 ,
McGuire Unit 2 -
Justification of Defertal i
Item Number: 2-MC-NV1 Valve: 2NV-94AC, 2NV-95B Flow Diagram: MC-2554-1.1 Code Category: B ASME Class: 2 Function: 1) Provides flowpath for Reactor Coolant Pump seal water discharge line.
- 2) Provides containment isolation for penetration M-256 Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferrol: Closure of one of these valves during power operation would inhibit normal seal water flow across the reactor coolant pump number 1 seal. This action could result in damage to the reactor coolant pump seals or the pump itself.
Test Alternative & Frequency: Valve will be cycled and timed during coid hidown.
11/1/93 SECTION 11.7 61 OF 95
McGuire Unit 2 dp_stification of Deferral item Number: 2-MC-NV2 Valve: 2NV-7B Flow Diagram: MC-2554-1.2 Code Category: B ASME Class: 2 Function: 1) Provides flowpath for normal letdown.
- 2) Provides containment isolation for penetration M-347.
Test Requirement: Stroke time test Iri accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Failure of this valve in a closed position could result in loss of pressurizer level control and result in unit shutdown.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 62 OF 95 I
McGuire Unit 2 ;
Jnstification of Deferral item Number: 2-MC-NV3 Valve: 2NV-21 A :
Flow Diagram: MC-2554-1.2 Code Category: B ASME Class: 1 Function: Provides isolation for Pressurizer Auxiliary spray.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferrai: Opening this valve during power operations could result in ,
a reactor low pressure trip.
Test Alternative & Frequency: Valve will be cycled and timed dunng cold shutdown.
11/1/93 SECTION 11.7 63 OF 95
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-l McGuiro Unit 2 i
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Justification of Deferral item Number: 2-MC-NV4 Valve: 2NV-141 A 2NV-142B Flow Diagram: MC-2554-2.0 Code Category: B ASME Class: 2 Function: Provides isolation for Volume Control Tank upon Safety injection Signal.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Closure of one of inese valves during power operation would isolate the suction for the Centrifugal Charging Pumps. This action could result in damage to the pumps.
Seal water to the Reactor Coolant pumps would be interrupted cousing damage to the seals.
e Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION l1.7 64 OF 95
McGuire Unit 2 J_ustification of Deferral Item Number: 2-MC-NVS t
Valve: 2NV-244A, 2NV-245B Flow Diagram: MC-2554-3.0 Code Category: B ASME Class: 2 Function: Isolates charging to the Reactor Coolant System upon Safety injection.
Test Requirement: Stroke time test in accord 4nce with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferrol: If one of these valves were to failin the closed position while testing during power operation, normal and alternate charging would be lost. This could result in a loss of pressurizer level control and result in unit shutdown.
- Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION l1.7 65 OF 95
McGuire Unit 2 Lustification of Deferral item Number: 2-MC-NV6 Valve: 2NV-221 A, 2NV-222B Flow Diagram: MC-2554-3.1 Code Category: B ASME Class: 2 Function: Flowpath for Refueling Water Storage Tank to the sut. ion of the Centrifugal Charging Pumps.
Stroke time test in accordance with OMc-1988 Part 10, Test Requirement:
4.2.1.1.
Basis for Deferrol: Opening these valves during power operation allows the Charging Pumps to inject highly borated water into the Reactor coolant System which could result in a unit shutdown.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 66 OF 95
I McGuire Unit 2 Justification of Deferral 1
Item Number: 2-MC-NV7 Valve: 2NV-264 Flow Diagram: MC-2554-3.1 Code Category: C ASME Class: 2 Function: Provides flowpath from the Boric Acid Tank to the Centrifugal Charging Pump suction. Closes to provide pump suction pressure boundary.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Deferral: To full stroke exercise this valve during power operations would inject more than 30 gpm of boric acid into the Reactor Coolant System creating a transient. To verify clo-sure, residual boric acid would be injected causing a transient.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
l 11/1/93 SECTION 11.7 67 OF 95
McGuire Unit 2 '
Jus 1Lfication of Deferral item Number: 2-MC-NV8 Valve: 2NV-150B, 2NV-151 A Flow Diagram: MC-2554-2.0 Code Category: B ASME Class: 2 Function: Provides isolation for Centrifugal Charging Pump miniflow line to Volume Control Tank.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferra!: If either valve were to fail closed while testing, the Charging Pump miniflow protection line is isolated possibly cousing damage to the pump.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION 11.7 '
. 68 OF 95
McGuire Unit 2 Lust!fication of Deferral i
item Number: 2-MC-NV9 Valve: 2NV-265B 4
Flow Diagram: MC-2554-3.1 Code Category: B ASME Class: 2 Function: Isolates the Boric Acid Tank from the suction of the Charging Pumps.
Test Requirement: Stroke time test in accordanc) with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: If valve is opened during power operations. boric acid could be injected into the Reactor Coolant System causing a transient.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION ll.7 69 OF 95
1 McGuire Unit 2 Justification of Deferral Itern Number: 2-MC-NV10 Valve: 2NV-225, 2NV-231 Flow Diagram: MC-2554-3.1 Code Category: C ASME Class: 3 -
Function: Pump discharge check valve, Opens to provide flowpath for Centrifugal Charging Pump. Closes to prevent opposite train flow losses.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Deferral: Valve cannot be full stroke exercised during power operation since this would require on increase in Reactor Coolant System boron concentration which could result in unit shutdown, Normalletdown is not sufficient to verify full stroke, this must be done when aligned to the FWST for suction.
Test Alternative & Frequency: Valve will be full stroke exercised during cold shutdown, partial stroked with normal use.
11/1/93 SECTION l1.7 70 OF 95 j l
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McGuire Unit 2 i
Lustification of Deferraj ltem Number: 2-MC-NV11 Valve: 2NV-223 Flow Diagram: MC-2554-3.1 Code Category: C ASME Class: 2 Function: Provides open flowpath from the FWST. Provides closed pump suction pressure boundary when suction is from the Residual Heat Removal pumps.
Test Requirement: Verify proper volve movement once per three months as required by OMa-1988 Part 10,4.3.2.1, Basis for Deferral: Testing this valve during power operations would require opening of either 2NV-221 A or 2NV-2228. Opening these valves during power operation could result in a unit trip, See Justification # MC-NV6.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
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11/1/93 SECTION l1.7 i 71 OF 95
McGuire Unit 2 JuJ11fication of Deferral item Number: 2-MC-NV12 Valve: 2NV-1046 Flow Diagram: MC-2554-3.0 Code Category: C ASME Class: 2 L
l Function: Closes to provide pump suction pressure boundary for l Centrifugal Charging Pumps. Open function is to protect the Positive Displacement Pump from over pressurization.
This is not a safety related function.
Test Requirement: Verify proper volve movement once per three months as required by OMa-1988 Port 10,4.3.2.1.
Basis for Deferral: Testing this volve during power operation would result in the addition of highly borated water into the Reactor Coolant System causing a transient.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
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McGuire Unit 2 Justification of Deferral item Number: 2-MC-NV13 Valve: 2NV-261, 2NV-263 Flow Diagram: MC-2554-3.1 Code Category: C ASME Class: 2 Function: These valves shall close to provide pump suction pressure isolation for the Centrifugal Charging Pumps by preventing backtiow to the Chemical Mixing Tank or the RMWST respectively.
Test Requirement: Verify proper volve movement once per three months as required by OMa-1988 Port 10,4.3.2.1, Basis for Deferral: Testing these valves requires 2NI-121 A to be opened. This valve is closed with power removed above mode 4 per Tech Spec 4.5.2.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
11/1/93 SECTION 11.7 73 OF 95
McGuire Unit 2 i cation of Deferral Jus 1!f item Number: 2-MC-NV14 Valve: 2NV-1002 Flow Diagram: MC-2554-1,3 Code Category: A.C ASME Class: 2 Function: Provides containment isolation on penetration M-342.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10, 4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valvo closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage j frequency, 11/1/93 SECTION 11.7 74 OF 95
McGuire Unit 2 JyStification of Deferral item Number: 2-MC-NV15 Valvo: 2NV-143 ,
Flow Diagram: MC-2554-2.0 C ode Category: C rSME Class: 2 :
Function: This valve shall close to provide Centrifugal Charging Pump suction pressure boundary during Recirculation alignment from RHR Pump discharge.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Port 10,4.3.2.1, Basis for Deferral: This valve is in the flowpath from the Volume Control Tank -
to the Charging pumps. During normal system operation, this valve is open. To verify this valve closes properly requires the alignment from the RHR pumps, and would interrupt normal charging activities.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
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11/1/93 SECTION 11.7 75 OF 95
McGuire Unit 2 s!pstification of Deferral llem Number: 2-MC-RFl Valve: 1RF-834 Flow Diagram: MC-1599 2.2 Code Category: A,C i ASME Class:
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Function: Provides containment isolation on penetration M-353.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferrol:
The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J of refueling outage frequency.
11/1/93 SECTION 11.7 76 OF 95
McGuire Unit 2 P
Justification of Deferral s
item Number: 2-MC-RN1 Valve: 2RN-252B, 2RN-253A Flow Diagram: MC-2574-4.0 Code Category: A ASME Class: 2 Function: 1) Provides containment isolation for penetration M-307.
- 2) Provides flowpath for cooling water to the Reactor Coolant Pump Motor Air Cooler Test Requirement: Stroke time test in accordance with OMa-1988 Port 10, 4.2.1,1.
Basis for Deferral: If one of these valves were to fail closed during testing, isolation of cooling water to the motor coolers could result in damage to the pumps.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown. ..
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11/1/93 SECTION 11.7 77 OF 95 I
McGuire Unit 2 Justificajion of Deferral Item Number: 2-MC-RN2 Valve: 2RN 276A 2RN-277B Flow Diagram: MC-2574-4.0 Code Category: A ASME Class: 2 Function: 1) Provides containment isolation for penetration M-315.
- 2) Provides flowpath for cooling water to the Reactor Coolant Pump Motor Air Cooler.
Test Requiroment: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1..
Basis for Deferral: If one of these valves were to fall closed during testing, isolation of cooling water to the motor coolers could result in damage to the pumps.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION l1.7 78 OF 95
McGuire Unit 2 Lustification of Deferral item Number: 2-MC-RN3 Valve: 2RN-42A Flow Diagram: MC-2574-4.0 Code Category: B ASME Class: 3 Function: Provides isolation to the Nuclear Service Water Non Essential header upon Safety injection.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10.
4.2.1.1.
Basis for Deferral: Closing this volve during power operation isolates cooling water flow to the Steam Generator Blowdown Heat Exchanger. Failure in the closed position could result in damage to the heat exchanger.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION ll.7 79 OF 95
McGuire Unit 2 l
Justification of Deferral Item Number: 2-MC-RN4 Valve: 2RN-638. 2RN-64A ,
Flow Diagram: MC-2574-4.0 Code Category: B ASME Class: 3 Function: Provides isolation to the Nuclear Service Water Non Essential header upon Safety injection.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Closing either of these valves during power operation s isolates cooling water flow to the Steam Generator - l Blowdown Heat Exchanger.' Failure in the closed pc : tion l could result in damage to the heat exchanger.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown. ,
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11/1/93 SECTION 11.7 80 OF 95
McGuire Unit 2 Lustification of Deferraj llem Number: 2-MC-RN5 Valve: 2RN-ll3 Flow Diagram: MC-2574-2.0 Code Category: C ASME Class: 3 Function: Must open to allow assured makeup supply from the Nuclear Service Water System to the Spent Fuel Pool. The closed function of this volve was eliminated by modification MGMM-3776. This volve is scheduled to be deleted from the system during 2EOC9 refueling outage.
Until it is deleted, it will be included in the test program and tested as outlined below.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1, Basis for Deferr~' Valves cannot be full stroked at any time without putting raw water into the Spent Fuel Pool.
Test Alternative & Frequency: This valve will be disassembled and full stroked during each refueling outage untilit is deleted from the system. The volve will be partial stroked quarterly.
11/1/93 SECTION 11.7 81 OF 95
McGuire Unit 2 Justification of Deferral item Number: 2-MC-RN6 Valve: 2RN-891,2RN-892 Flow Diagram: MC-2574-2.0, MC-2574-3.0 Code Category: C ASME Class: 3 t Function: Check flow from the RN return line (from the KD heat exchanger i to the RN essential header) to maintain RN system integrity, during a seismic event. Open to allow Nuclear Service Water retum from the VG coolers.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.
Basis for Deferral: The system does not permit teverse flow testing as there is not sufficient pressure down stream of these check valves to verify closure. These check valves discharge into the main RN Discharge header and piping that large has little back pressure .
Test Altemative & Frequency: These valves will be tested for closure via sample disassembly at a refueling outage frequency (as specified per GL 89-04).
The open function will be verified with proper Diesel Generator operation as " Valves in Regular Use" and done on a monthly frequency.
11/1/93 SECTION 11.7 82 OF 95
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McGuire Unit 2 Justification of Deferral Item Number: 2-MC-RV1 Valve: 2RV-32A 2RV-33B,2RV-76A 2RV-778 Flow Diagram: MC-2604-3.0 Code Category: A ASME Class: 2 Function: Provide containment isolation for penetration M-240 and M-279 respectively.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1, Basis for Deferral: Failure of one of these valves in the closed position during testing would isolate cooling flow to the Lower Containment Ventilation Unlis causing an increase in lower containment temperature which could exceed Tech Spec limits.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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. McGuire Unit 2 Justification of Deferral item Number: 2-MC-SA1 Valve: 2SA-5, 2SA-6 Flow Diagram: MC-2593-1.2 Code Category: C ASME Class: 2 Function: Opens to allow steam supply to the turbine driven Auxiliary Feedwater Pump. Closes to prevent cross connecting steam generators IB and IC. i Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10. 4,3.2.1, ,
Basis for Deferral: System configuration and design do not provide a suitable means to prove the valve prevents reversal of flow. To test the close function of this valve on line would risk personnel safety since high energy steam would be involved.
Test Alternative & Frequency: At least one of these two valves will be disassembled and full stroked during each refueling outage, and both volves will have been disassembled and full stroked after two consecutive outages. Sample disassembly will verify closure. Failure of one of valve to properly full stroke during a refueling outage will result in the remaining volve being disassembled and full stroked during that outage. Valves will be full stroked open quarterly.
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11/1/93 SECTION 11.7 84 OF 95
i McGuire Unit 2 Justification of Deferral l
item Number: 2-MC-SM1 Valve: 2SM-1 AB. 2SM-3AB, 2SM-5AB, 2SM-7AB Flow Diagram: MC-2593-1.0, MC-2593-1.3 Code Category: B ASME Class: 2 Function: Main Steam isolation Valves Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: These valves cannot be fully cycled closed during power operation since a unit shutdown would result.
Test Alternative & Frequency: These volves will be partially cycled closed while in Modes 1,2 and 3. These valves will be cycled and timed during cold shutdown.
11/1/93 SECTION 11.7 85 OF 95
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i McGuire Unit 2 Lustification of Dpferral
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Item Number: 2-MC-VB1 Valve: 2VB-50 Flow Diagram: MC-2605-3.1 Code Category: A,C ASME Class: 2 Function: Provides containment isolation on penetration M-215.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa 1988 Part 10,4.3.2.1,
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2. ,
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION 11.7 86 OF 95
McGuire Unit 2 k
dasllfication of Deferral item Number: 2-MC-VG1 Valve: 2VG-17, 2VG-18. 2VG-19, 2VG-20 Flow Diagram: MC-2609-4.0 Code Category: C ASME Class: 3 Function: Provides flowpath for Diesel Generator control air from individual starting air banks.
Test Requirement: Verify proper volve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Deferral: Testing these valves requires the Diesel Generator to be started on a single bank of control air which is considered a degraded condition. This is notjustified for quarterly starts.
This test is required to be done on an 18 month frequency as comrnitted to in our response to SOER 80-1.
Test Alternative & Frequency: Valve will be full stroke exercised with the diesel generator start on a single bank of control air and performed at refueling outage frequency.
Note: A separate relief request has been submitted for these valves. This relief request was submitted on August 24,1993 as Docket No. 50-370, Relief Request 92-01, 11/1/93 SECTION 11.7 87 OF 95
McGuire Unit 2 Justification of Deferral 1
Item Number: 2-MC-Vil Valve: 2VI-368, 2VI-372, 2VI-373, 2VI-374 Flow Diagram: MC-2605-1.3 !
Code Category: C ASME Class: ANSI B31.1.0 (1967)
Function: 2VI-368 and 2VI-373 must sper, to allow nitrogen to the PORV actuator.
2VI-372, 2VI-374 must close to prevent loss of Nitrogen pres-sure if instrument air is lost.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Deferral: All four valves are tested with PORV stroke timing. PORVs are tested on a cold shutdown frequency. Refer to Justification # 2-MC-NCl !
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
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11/1/93 SECTION ll.7 88 0F 95 ,
McGuire Unit 2 Justification of Delerral
, Item Number: 2-MC-V12 Valve: 2VI-124, 2VI-149 Flow Diagram: MC-2605-1.2 Code Category: AC ASME Class: 2 Function: Provides containment isolation on penetrations M-317 and M-386 respectively.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
l Test Alternative & Frequency: Valve will be verified closed by leak test performed ir, accordance with 10CFR50 Appendix J of refueling outage frequency.
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' 89 0F 95 l
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McGuire Unit 2 J_ustificatiortof Deferral 4
ltem Number: 2-MC-Vl3 Valve: 2VI-40, 2VI-161 Flow Diagram: MC-2605-1.3 Code Category: A.C ASME Class: 2 Function: Provides containment isolation on penetrations M-220 and M-359 respectively.
Test Requirement: 1) Verify proper volve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Port 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in ,
accordance with 10CFR50 Appendix J at refueling outage -
freauency.
11/1/93 SECTION 11.7 90 OF 95
i McGuire Unit 2 Justification of Deferral item Number: 2-MC-VS1 Valve: 2VS-13 Flow Diagram: MC-2605-2.2 Code Category: AC ASME Class: 2 Function: Provides containment isolation on penetration M-219.
Test Requirement; 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1,
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 S. . lON 11.7 91 OF 95 .
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McGuire Unit 2 Justification of Deferral item Nurnber: 2-MC-VX1 Valve: 2VX-30 Flow Diagram: MC-2557-1 Code Category: AC ASME Class: 2 Function: Provides containrnent isolation on penetration M-325.
Test Requirement: 1) Verify proper volve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The systern design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION 11.7 92 OF 95 i
~..J
McGuire Unit 2 i
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Justification of Deferral item Number: 2-MC-WL1 Valve: 2WL-24 Flow Diagram: MC-2565-1.1 Code Category: AC ASME Class: 2 Function: Provides containment isolation and therrnal over pressurization protection of line between 2WL-1B and 2WL-2A on penetration M-375. .
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10, 4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal. l Test Alternative & Frequency: Valve will be verified closed by leak test performed in ,
accordance with 10CFR50 Appendix J at refueling outage frequency.
I 11/1/93 SECTION 11.7 93 0F 95 1
McGuire Unit 2 k
Justification of Deferral item Number: 2-MC-WL2 Valve: 2WL-385 Flow Diagram: MC-2565-7.0 Code Category: A,C ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection of line between 2WL-3228 and 2WL-321 A on penetration M-221.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMa-1988 Part 10,4.2.2.2.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION li.7 94 OF 95
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McGuire Unit 2 al' Justif_ication of Deferral item Number: 2-MC-YM1 Valve: 2YM-116 Flow Diagram: MC-2601-2.4 Code Category: A.C ASME Class: 2 Function: Provides containment isolation on penetration M-337.
Test Requirement: 1) Verify proper valve movement once per three months as required by OMa-1988 Port 10,4.3.2.1.
- 2) Leak fest once per 2 years in accordance with OMa-1988 Part 10, 4.2.2.2.
e Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION 11.7 95 OF 95