ML20063A941
ML20063A941 | |
Person / Time | |
---|---|
Site: | McGuire, Mcguire |
Issue date: | 11/01/1993 |
From: | DUKE POWER CO. |
To: | |
Shared Package | |
ML20063A918 | List: |
References | |
PROC-931101-01, NUDOCS 9401270160 | |
Download: ML20063A941 (200) | |
Text
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ATTACHMENT 2 1
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DUKE POWER COMPANY McGUIRE NUCLEAR STATION UNIT 1 Pump and Valve Inservice Testing Program
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9401270160 940106 PDR G ADOCK 05000369 i PDR ,
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DUKE POWER COMPANY McGUIRE NUCLEAR STATION UNIT 1 PUMP INSERVICE TESTING PROGRAM i-f' l.
g McGuiro UNIT 1 Page 1 of 2 TABLE OF CONTENTS PAGES
!. Pump Inservice Testing Program 1.1 Introduction 1-1 1.2 Data Sheets 1-10 1.3 General Relief Request 1.- 2 1.4 Specific Relief Request _ 1 -11
- 11. Valve Inservice Testing Program 11.1 Introduction 1-1
- 11. 2 Table of Abbreviations 1-1
- 11. 3 Definitions of Testing Requirements and Altematives 1-2
- 11. 4 System Data Sheets:
Nuclear Service Water System Shared.. . .
. . (Shared)RN 1 - 2 Steam Generator Blowdown Recycle . . ... BB 1 - 1 Auxiliary Feedwater.. . . . . . .. . . . . . . . .. .CA1-3 Feedwater .. .. . . . . . . . .. .CF1-2 Diesel Generator Engine Fuel Oil . . . .. . .. . . FD 1 - 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 1 Radiation Monitoring. .. .. .MI1-1 Boron Recycle.. ,. . . . . . . .. .NB1-1 Reactor Coolant. . . . . . . . . . . . . ... . . . . .NC1-2 Residual Heat Removal . . . . . . . . . . . . . . .. . .ND1-1
!ce Condenser Refrigeration.. .. . . . . . . . . . ...NF1-1 Safety injection.. .. . . . . . . . ... NI 1 -.5 )
I Nuclear Sampling.. . . . . .. .. .NM1-2 l
11/1/93
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m McGuira UNIT 1 Page 2 of 2 TABLE OF CONTENTS Containment Spray . . . . ,. . . . . . . . . . . ...NS1-2 Chemical and Volume Control. . . . . ...NV1-4 Fire Protection.. . . . .. .. . .. . . .RF1-1 Nuclear Service Water.. .. . .. . . . . . . . ..RN1-5 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.. . . . . . . . . . . .SV1 2 Breathing Air. . . . . .VB1-1 Control Area Ventilation. .. . . .. .VC1-1 Annulus Ventilation . . . .. . . . . . . . VE 1 - 1 Diesel Generator Starting Air. .. . . .. VG 1 - 3 Instrument Air.. . .VI1-2 Containment Purge Ventilation . . . . . . . VP 1 - 1 Containment Air Release and Addition. . . . ..VO1-1 Station Air.. . . . . . . . VS 1 - 1 Containment Air Return Exchange and Hydrogen Skimmer.. .. . VX 1 - 1 Equipment Decontamination.. . WE1 - 1 Waste Gas. . . .. . .. . . . .. WG1 - 1 Liquid Waste Recycle . . ... . . .. .. .WL1 - 1 Diesel Generator Room Sump Pump. . .. .. . . WN1 - 1 Groundwater Drainage.. . . . . . . . . . WZ1 - 1 Control Area Chilled Water.. . . . . . . - . . .YC1-2 Makeup Demineralized Water . . . . . ..YM1-1
- 11. 5 General Relief Requests 0 11.6 Specific Relief Requests 1-5 ll.7 Justification of Deferral 1 - 95 11/1/93
INSERT TIIE FOLLOWING SECTION UNDER TAB:
I.1 UNIT 1
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McGuire Unit 1 DUKE POWER COMPANY McGUIRE NUCLEAR STATION - UNIT 1 PUMP lNSERVICE TESTING PROGRAM ASME OM CODE-1987, OM Part 6 (OMa-1988 Addenda)
JNTRODUCTION 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-1988, of the ASME Code for Operation and Maintenance of Nuclear Power Plants, as referenced in 10CFR50.55a (January 1,1993 Edition), except where specific written reDef has 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 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 inhials of the person or persons responsible for conducting 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.
i 11/1/93 SECTION 1.1 l 1 of 1 l l
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INSERT THE FOLLOWING SECTION UNDER TAB:
I.2 '
UNIT 1
l UNIT 1 - McGUIRE NUCLEAR STATION Pump Inservice Testing General Data Code Pump 10. Number Description Class Flow Diagram Applicable Relief Requests Test Frequency Remarks ICAPU0001 Motor Driven Auxiliary 3 MC-1592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump 1 A 1CAPU0002 Motor Driven Auxiliary 3 MC-1592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump 1B ICAPU0003 Turbine Driven Auxiliary 3 MC-1592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump #1 1FDPUOO54 DieselGenerator Fuel 3 MC-1609-3.0 RR-1.3.1, RR-i.4.2 Quarterly NONE Oil Transfer Pump 1 A 1FDPU0055 DieselGenerator Fuel 3 MC-1609-3.1 RR-l.3.1, RR-l.4.2 Quarterly NONE Oil Transfer Pump 1B 1KCPU0001 Component Cooling 3 MC-1573-1.0 RR-l.3.1, RR-!.4.3 Quarterly NONE Water Pump 1 A1 1KCPU0002 Component Cooling 3 MC-1573-1.0 RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 1 A2 1KCPUC003 Component Cooling 3 -MC-1573-1.0 RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 1B1 SECT!oN I 2 11/1/93 1 oF 10
UNIT 1 - McGUIRE NUCLEAR STATION Fump Inservice Testing Specific Data Differentiot Reference Pump ID. Number speed inlet Pressure Discharge Pressure Pressure Vibration Flow Rate Pump Type Revision ICAPU0001 Not Required RR-l.4.1 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 1CAPU0002 Not Required RR-l 4.1 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements
- 1CAPU0003 Meets Code RR-1.4.1 Meets Code Meets Code RR-1.3.1 Meets Code Centrifugal Requirements Requirements Requirements Requirements 1FDPU0054 Not Required RR-l.4.2 RR-l.4.2 RR-l.4.2 RR-l.3.1 RR-I.4.2 Gear Positive Displacenent
, 1FDPUOO55 Not Required . RR-l.4.2 RR-l.4.2 RR-1.4.2 RR-l.3.1 RR-l.4.2 Gear Positive Displacement 1KCPU0001 Not Required RR-l.4.3 Meets Code Meets Code RR-1.3.1 Meets Code Centrifugal Requirements Requirements Requirements IKCPU0002 Not Required RR-1.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 1KCPU0003 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 - Meets Code Centrifugal Requirements Requirements Requirements SECTioN !.2 11/1/93 2 oF 10
q UNIT 1 - McGUIRE NUCLEAR STATION Pump inservice Testing General Data Code Pump 1D. Number Description Class Flow Diagram Applicable Relief Requests Test Frequency Remarks IKCPU0004 Component Cooling 3 MC-1573-1.0 RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 1B2 1NDPU0001 Residual Heat Removal 2 MC-1561-1.0 RR-l.3.1, RR-l.4.4 Quarterly- The ND Testing Plan Pump 1 A Miniflow; meets other code Refueling- requirements unless Full Flow otherwise specified.
(RR-l.4.4)
INDPU0002 Residual Heat Removal 2 MC-1561-1.0 RR-1.3.1, RR-l.4.4 Quarterly- The ND Testing Plan Pump 1B Miniflow; meets other code Refueling- requirements unless Full Flow otherwise specified.
(RR-1.4.4)
INIPU0009 Safety injection Pump 2 MC-1562-3.0 ' RR-l.3.1, RR-l.4.5 Quorterly- The NI Testing Plan 1A Miniflow; meets other code Refueling- requirements unless Full Flow otherwise specified.
(RR-l.4.5)
INIPU0010 Safety injection Pump 2 MC-1562-3.0 RR-l.3.1, RR-l.4.5 Quarterly- . The N1 Testing Plan 1B Miniflow; meets other code
- Refueling- requirements unless Full Flow otherwise specified.
(RR-l.4.5)
INSPU0001 Containment Spray 2 MC-1563-1.0 RR-l.3.1 Quorterly NONE Pump 1 A SECTION 1.2 11/1/93 3 oF 10
UNIT 1 - 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 1KCPU0004 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal l Requirements Requirements Requirements l
INDPU0001 Not Required RR-l.4.4 Meets Code Meets Code RR-1.3.1 RR-l.4.4 Vertical Une i Requirements Requirements Shaft Centrifugal INDPU0002 Not Required RR-l.4.4 Meets Code Meets Code RR-l.3.1 RR-l.4.4 Vertical Une -
Requirements Requirements Shaft Centrifugal INIPUOOO9 Not Required RR-l.4.5 Meets Code Meets Code RR-1.3.1 RR-l.4.5 Centrifugal Requirements Requirements 1NIPU0010 Not Required RR-l.4.5 Meets Code Meets Code RR-1.3.1 RR-l.4.5 Centrifugo!
Requirements Requirements -
INSPU0001 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Vertical Une Requirements Requirements Requirements Requirements Shoft Centrifugal SECTION 1.2 11/1/93 4 0F 10
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UNIT 1 - McGUIRE NUCLEAR STATION Pump inservice Testing General Data Code Pump !D. Number Description Class Flow Diagram Applicable Relief Requests Test Frequency Remarks INSPU0002 Containment Spray 2 MC-1563-1.0 W-l.3.1 Quarterly NONE Pump 18 1NVPU0015 Centrifugal Charging 2 MC-1554-1.0 RR-l.3.1, RR-l.4.6 Quarterly- The NV Testing Plan Pump 1 A Miniflow; meets other code Refueting- requirements unless Full Flow otherwise specified.
(RR-l.4.6) 1NVPU0016 Centrifugal Charging 2 MC-1554-1.0 RR-l.3.1, RR-l.4.6 Quorterly- The NV Testing Plan Pump 1B Miniflow; meets other code Refueling- requirements unless Full Flow otherwise specified.
(RR-l.4.6) 1NVPUOO27 Boric Acid Transfer 3 MC-1554-5.0 RR-l.3.1 Quarterly NONE Pump 1 A 1NVPU0028 Boric Acid Transfer 3 MC-1554-5.0 RR-l.3.1 Quarterly NONE Pump 1B 1RNPU0003 Nuclear Service Water 3 MC-1574-1.1 RR-l.3.1, RR-l.4.7 Quarterly NONE Pump 1 A SECTION 1.2 11/1/93 5 OF 10 n -~ _. ,
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UNIT 1 - McGUIRE NUCLEAR STATION Pump Insenrice Testing Specific Data Differential Reference Pump ID. Number speed Inlet Pressure D!scharge Pressure Pressure Vibration Flow Rote Pump Type Revision 1NSPU0002 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Vertical Une Requirements Requirements Requirements Requirements Shaft Centrifugal 1NVPU0015 Not Required RR-l.4.6 Meets Code Meets Code RR-l.3.1 RR-l.4.6 Centrifugal Requirements Requirements 1NVPU0016 Not Required RR-l.4.6 Meets Code Meets Code RR-l.3.1 RR-l.4.6 Centrifugal Requirements Requirements 1NVPU0027 Not Required Meets Code Meets Code Meets Code RR-1.3.1 Meets Code Centrifugal Requirements ' Requirements Requirements Requirements i
INVPUOO28 .Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements Requirements 4
1RNPU0003 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements RR-l.4.7 Requirements SECTioN I.2 11/1/93 6 oF 10
UNIT 1 - McGUIRE NUCLEAR STAT!ON Pump Inservice Testing General Data Code Pump ID. Number Description Closs Flow Diagram Applicable Relief Requests Test Frequency Remarks 1RNPU0004 Nuclear Service Water 3 MC-1574-1.1 RR-1.3.1, RR-1.4.7 Quarterly NONE Pump 1B 1WNPUOO94 Diesel Generator Sump 3 MC-1609-7.0 RR-l.3.1 Two Year Two year frequency Pump 1 A2 for dry sump pumps per OMa-1988, Part 6 section 5.5.
1WNPU0096 Diesel Generator Sump 3 MC-1609-7.0 RR-l.3.1 Two Year Two year frequency Pump 1 A3 for dry sump pumps per OMa-1988, Port 6 section 5.5.
l 1WNPUOO95 Diesei Generator Sump 3 MC-1609-7.0 RR-l.3.1 Two Year Two year frequency Pump 182 for dry sump pumps per OMa-1988, Part 6 section 5.5.
1WNPUOO97 Diesel Generator Sump 3 MC-1609-7.0 RR-l.3.1 Two Year Two year frequency Pump 1B3 for dry sump pumps per OMa-1988, Part 6 section 5.5.
0YCPU0001 Control Area Chi!!ed 3 MC-1618-1 RR-l.3.1 Quarterly NONE.
Water Pump Train A SECTioN l.2 11/1/93 7 oF 10
_ - _ - _ . .-.._---_.__m__ ________________-_____s. a 4 _mi re m .e M W1 w r,n- r W W PN w-d7^ 4 8'F*ed9' h rw ,- g y --g- g- e.g <,y..- 9 ,,
m UNIT 1 - 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 IRNPU0004 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements RR-l.4.7 Requirements lWNPUOO94 Not Required Meets Code Meets Code Meets Code RR-1.3.1 Meets Code Vertico! Une Requirements Requirements Requirements Requirements Shoft Centrifugal IWNPUOO96 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Verticot Une Requirements Requirements Requirements Requirements Shoft Centrifugal 1WNPUOO95 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Vertico! Line Requirements Requirements Requirements Requirements Shott Centrifugal i
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1WNPUOO97 Not Required Meets Code Meets Code Meets Code RR-1.3.1 Meets Code Vertical Une l
Requirements . Requirements Requirements Requirements Shoft Centrifugal .
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! OYCPU0001 Not Required Meets Code Meets Code Meets Code RR-i.3.1 Meets Code Centrifugal l Requirements Requirements Requirements Requirements i
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SECTioN 1.2 ~-
11/1/93 8 oF 10 gy.v- p g- -
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UNIT 1 - McGUIRE NUCLEAR STATION Pump Inservice Testing General Data Code Pump ID. Number Description Cicss Flow Diagrcm Applicable Relief Requests Test Frequency Remarks OYCPU0002 Control Area Chilled 3 MC-1618-1 RR-l.3.1 Quarterly NONE
- Water Pump Train B l
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SECTION 12 11/1/93' 9 OF 10
UNIT 1 - McGUIRE NUCLEAR STATION Pump Inservice Testing Specific Data Differentici Reference Pump ID. Number speed inlet Pressure Discharge Pressure Pressure Vibration Flow Rote Pump Type Revision OYCPU0002 Not Required Meets Code Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements Requirements SECTION 1.2 11/1f93 10 0F 10
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INSERT TIIE FOLLOWING SECTION UNDER TAB:
I.3 i
l UNIT 1
McGuire Unit 1 General Relief Request RELIEF REQUEST: 1.3.1 PUMPS: All pumps in the inservice Test Program TEST REQUIREMENTS: 1) OMa 1988 Part 6 Section 6.1. (Table 3a) specifies the allowable range for acceptable operation of vibration measurements.
- 2) OMa-1988 Part 6 Section 4.6.1.1 (Table 1) requires the accuracy of vibration amplitude measurements to be +/- 5 % of full scale.
BASIS FOR RELIEF: 1) Experience has shown that smooth operating pumps (Vr s 0.075 husec) often fallin 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.
- 2) Vibration measurement instrumentation currently in use is digital instrumentation. Using our present instrumentation and accounting for all instrumentation uncertainties in the calibration process, the requirement 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 vibration standards (vibration severity charts).
Acceptable Alert Required Range Range Action Range 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 intomal gear positive s 2.5
- Vr > 2.5
- Vr to 6
- Vr > 6
- Vr displacement pumps, 11/1/93 SECTION l.3 1OF2 L'
3 McGuire Unit 1 General Relief Reauest ,
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 l.3 2OF2
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INSERT TIIE FOLLOWING SECTION UNDER TAB:
I.4 5
9 5
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e 9
P UNIT I
McGuire Unit 1 Specific Relief Flequest RELIEF REQUEST: 1.4.1 PUMPS: 1CAPU0001,1 A CA Pump 1CAPU0002,18 CA Pump 1CAPUOOOS, Unit 1 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; Uerefcre, 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 1for pressure instrument accuracy (2 %). The actual reading error at test pressure due to the process instrument accuracy is 2.5 % (0.5
- 100/20).
If a 0-G0 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 1 A CA,1B CA and Unit 1 Turbine Driven CA pump tests.
11/1/93 SECTION 1.4 1 OF 11
McGuire Unit 1 Specl[i.cl Relief ReqM RELIEF REQUEST: 1.4.2 PUMPS: 1FDPU0054,1 A D/G Fuel Oil Transfer Pump 1FDPU0055,1B 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 intemal 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*Or to 1.07*Or Low Alert Range: 0.90*Or to 0.94*Or High Alert Range 1.07*Or to 1.10*Or Low Required Action Range: < 0.90*Or High Required Action Range: > 1.10*Or 11/1/93 SECTION 1.4 2 OF 11
McGuire Unit 1 Specific Relief Requesj i
RELIEF REQUEST: 1.4.2 (Continued)
These pumps are designed to produc, 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 I.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 ccn 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 Sto; age Tank is the suction source for the Fuel Oil Transfer pumps anri is monitored to maintain level as required by McGuire Technica! 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 1.4 3 OF 11 I
McGuire Unit 1 Specific Relief Request RELIEF REQUEST: 1.4.3 PUMPS: 1KCPU0001,1 A1 Component Cooling Water Pump 1KCPU0002,1 A2 Component Cooling Water Pump 1KCPU0003,1B1 Component Cooling Water Pump 1KCPU0004,1B2 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.
BASIS FOR RELIEF: 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 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). If 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, Sectior. 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 % 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 KC ,
suction pressure for the 1 A1,1 A2,181, and 1B2 KC pump tests. >
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I 11/1/93 SECTION l.4 4 OF 11 ,
i McGuire Unit 1 Specific Relief Request !
RELIEF REQUEST: 1.4.4 PUMPS: 1NDPU0001,1 A Residual Heat Removal Pump 1 1NDPU0002,1B 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 va!ue.
- 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 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 reotsaments 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.
QU.M12I!Y 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 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
-l 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 used in the test has a flow measuring orifice installed, however, the system resistance cannot be adiusted 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 l.4 5 OF 11
McGuire Unit 1 Specific Relief Request RELIEF REQUEST: 1.4.4 (Continued)
Refueling Outage 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 datd 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 tne 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 aquirements and Generic Letter 89-04.
t 11/1/93 SECTION 1.4 6 OF 11
McGuire Unit 1 Specific Relief Request j RELIEF REQUEST: 1.4.5 PUMPS: 1NIPU0009,1 A Safety injection Pump 1NIPU0010,1B Safety injection Pump t
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. ;
Quarterly The Safety injection Pumps will be tested quarterly to verify 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 meesure 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 precsure.
Therefore, flow through this loop will be recorded for information only.
11/1/93 SECTION 1.4 7 OF 11
McGuire Unit 1 Specific Relief Reaues!
RELIEF REQUEST: 1.4.5 (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 applicab!c 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 vibratiori data varies significantly over the pump head curve, vibration accepts ice criteria will be developed for flow regions of the head curve.
The test method selected will depend on plant refxsng conditions, maintenance performed on the pump, and the quaniity 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 test methodology is consistent with the intent of Code requirements and Generic Letter 89-04.
11/1/93 SECTION 1.4 8 0F 11
McGuire Unit 1 Specific Relief Reauest RELIEF REQUEST: 1.4.6 PUMPS: 1NVPU0015,1 A Centrifugal Charging Pump 1NVPU0016,1B 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.
BASIS FOR RELIEF: 1) When testing these pumps on lin . s only flow path available is through a combination of the normal cnarging litie and the miniflow line to the Volume Control Tank. This test yields c 16::t point back on the head curve. As stated in Generic Letter 89-C4, the test point for monitoring pump performance for degradation shauld 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 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 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 l Technical Specifications are met. The test measures differentiai i pressure and velocity vibration data. The differential pressure and velocity vibration data will be trended. The instrumentation range ]
requirements of0Ma 1988 Part 6, Section 4.6.1.2.a will be waived. The 1 instrumentation used to measure suction and discharge pressure will l meet applicable accuracy requirements for the determination of l operability per Technical Specifications. The instrument used to measure j vibrations will meet the requirements specified in relief request 1.3.1. The flow through the miniflow line to the Volume Control Tank will be assumed to be constant at the orifice design conditions (60 gpm).
11/1/93 SECTION l.4 9 OF 11 i
McGuire Unit 1 Specific Relief Request 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 wi!! ;
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 1.4 10 OF 11
McGuire Unit 1 Sp_qgific Relief Request RELIEF REQUEST: 1.4.7 PUMPS: 1 RNPU0003,1 A Nuclear Service Water Pump 1RNPU0004,18 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 soeed to at least 1000 Hz.
BASIS FOR RELIEF: The Nuclear Service Water pumps are designed to opu ste at 1185 rpm.
This speed yields a f aquency of 19.75 Hz (1185/60). The vibration instrumentation used cannot be calibrated to the 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 11/1/93 SECTION 1.4 11 OF 11
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DUKE POWER COMPANY i
F McGUIRE NUCLEAR STATION UNIT 1 VALVE INSERVICE TESTING PROGRAM i
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Unit 1 - McGuire Nuclect Station Inservice Testing Program ,
FWW FLOW ASME VALVE ACT VAL \ E ACTUATOR TEST TESr RELIEF JUSrIFOF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYT'S TWE REQ'MT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV CONTAINMENT PURGE VENTILATION (VP) 1VP-00018 1576-1 1-06 2 A ACT Butteily AOV LT-TS - - - - - -
IVP-0002A 1576-1 l-07 2 A ACT Butteity AOV LT-TS - - - - - -
1VP-0003B 1576-1 K-06 2 A ACT Butteity AOV LT-TS - - - - - -
1VP-0004A 1576-1 K-07 2 A ACT Butteity AOV LT-TS - - - - - -
1VP-0006.B 1576-1 E-06 2 A ACT Buttedly AOV LT-TS - - - - - -
IVP-0007A 1576-1 E-07 2 A ACT Butterfly AOV LT-TS - - - - - -
1VP-0008B 1576-1 DE 2 A ACT Butterfly AOV LT-TS - - - - - -
1VP-C009A 1576-1 D47 2 A ACT Butterfly AOV LT-TS - - - - - -
1VP-0010A 1576-1 J-08 2 A ACT Butterffy AOV LT-TS - - - - - -
IVP-C0118 1576-1 J-09 2 A ACT Butterffy AOV LT-TS - - - - -
IVP-0012A 1576-1 1-08 2 A ACT Butterfly AOV LT-TS - - - - - -
1VP-0013B 1576-1 1-09 2 A ACT Butterfly AOV LT-TS - - - - - -
TVP-0015A 1576-1 F-08 2 A ACT Butterfly AOV LT-TS - - - - - -
IVP-00168 1576-1 F-09 2 A ACT Butterfly AOV LT-TS - - - - -
IVP-0017A 1576-1 B-07 2 A ACT Butterfly AOV LT-TS - - - - - -
1VP-00188 1576-1 B-06 2 A ACT Butterfly ADV LT-TS - - - - - -
IVP-0019A 1576-1 B-08 2 A ACT Butter!)y AOV LT-TS - - - - - -
1VP-CD20B 1576-1 B-09 2 A ACT Butterfly AOV LT-TS - - - -- - -
11/1/93 VP - 1 of 1
Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF TEST JUSTIF OF VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQ %fT #2 REQST DEFERRAL REMARKS ALTERNATIVES REY CONTAINMENT AIR RELEASE AND ADDITION (VQ) 1VO4001A 1585-1.0 J-04 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
IVO40028 1585-1.0 J-06 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
IVO.00050 1585-1.0 E-06 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
IVO-0006A 1585-1.0 E-03 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
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L Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATUR TEST TEST REUFF JUST1F OF TEST VALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQ'Mr #2 REQST DEFERRAL REMARKS ALTERNATWES REV STATION AIR (VS) 1VS-00128 1605-2.2 K-05 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
IVS-0013 1605-2.2 l-05 2 AC ACT Check -
MTC-Q LT-RF -
1-MC-VS1 -
MT-RF' -
11/1/93 - VS - 1 of 1
Unit 1 - McGuire Nuciect Station Inservice Testing Program FLOW f1OW ASME VALVE ACT VALVE ACTUATOR TEST TFST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ ~hfr #1 REQ'MT #2 REQST DEFERRAL REMARK 5 ALTERNATIVES REV CONTAINMENT AIR RETURN EXCHANGE AND HYDROGEN SKIMMER (VX) 1VX-0001 A 1557-1 l-03 2 B ACT Butterfly E'MO ST-O - - - - - -
1VX-00028 1557-1 1-12 2 B ACT Butterfly EMO ST-O - - - - - -
IVX-0030 1557-1 J-03 2 AC ACT Check -
MTC-O LT-RF -
1-MC-VX1 - MT-RF -
1VX-003 t A 1557-1 J-13 2 A ACT Diaphram AOV ST O LT-RF - - - - -
1VX-00338 1557-1 J-12 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
1VX-0034 1557-1 K-12 2 A PAS Diaphram -
LT-RF - - - ~ ~
E IVXM 1557-1 K-03 2 A PAS Diaphram -
LT-RF - - - - -
11/1/93 VX - 1 of 1
Unit I - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JL511F OF TEST .
VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYPE TYPE REQ MT #1 REQ'hfr #2 REQST DETERRAL REMARKS ALTERNATIVES REV EQUIPMENT DECONTAMINATION (WE) 1WE-0013 1568-1.0 E-08 2 A PAS Kerotest -
LT-RF - - - ' '
COE 1WE-0023 1568-1.0 E-10 2 A PAS Kerotest -
LT-RF - - - ' ~
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Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JLSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TWE TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV -
WASTE GAS (WG) 1WG-0092 1567-2.0 F-14 3 C ACT Relief -
1WG-0097 1567-2.0 F-12 3 C ACT Relief -
SP - - - -
150 PSIG -
1WG-0104 1567-2.0 F-10 3 C ACT Relief -
1WG-0112 1567-2.0 F-08 3 C ACT Relief -
SP - - - -
150 PSIG -
1WG-0117 1567-2.0 F-05 3 C ACT Relief -
1WG-0124 1567-2.0 F-03 3 C ACT Relief -
1WG-0146 1567-2.1 F-11 3 C ACT Relief -
SP - - - -
100 PSIG -
tWG-0153 1567-2.1 F-6 3 C ACT Relief -
SP - - - -
150 PSIG -
11/1/93 WG - 1 of 1
Unit 1 - McGuire Nuclear Station Inservice Testing Program FtDW flow ASME VALVE ACT VALVE ACTUATOR TEST TEST RFLIEF JUST!F OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ %fT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV LIQUID WASTE RECYCLE (WL) 1WL-00018 1565-1.1 L-11 2 A ACT Diaphram EMO ST-O LT-RF - - - - -
1WL-0002A 1565-1.1 K-13 2 A ACT Diaphram EMO ST-O LT-R F - - - - -
1WL-0024 1565-1.1 J-14 2 AC ACT Check -
MTC-O LT-RF -
1-MC-WL1 - MT-RF* -
1WL-0039A 1565-1.1 J-05 2 A ACT Kerotest EMO S's -C LT-RF - - - - -
1WL-0041B 1565-1.1 K-05 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1WL-0064A 1565-1.0 J-03 2 A ACT Diaphram EMO ST-O LT-RF - - - - -
1WL-00658 1565-1.L K-05 2 A ACT Diaphram . EMO ST-O LT-RF - - - - -
1WL-0264 1565-1.0 J-02 2 AC ACT Relief -
SP LT-RF - - -
100 PSIG -
1WL-0321 A 1565-7.0 H47 2 A ACT Butterfly EMO ST-O LT-RF - - - - -
1WL-03220 1565-7 0 1-06 2 A ACT Butterfy EMO ST-O LT-RF - - - - -
1WL-0385 1565-7.0 H-07 2 AC ACT Check -
MTC-O LT-RF - 1-MC-WL2 -
MT-RF* -
1WL-1302A 1565-1.0 E-09 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
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Unit 1 - McGuire Nuclect Station Inservice Testing Program TIDW ITDW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TEST VALVE NUMBER DIAGRAM CCUR CLASS CATECORY PAS TsT'E TWE REQ'MT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTTRNATIVES REV DIESEL GENERATOR ROOM SUMP PUMP (WN) 1WN@03 1609-7.0 L-11 3 C ACT Check - MTO,C-O -
yp 1WN-0005 1609-7.0 K-11 3 C ACT Check -
MTO.C-Q - ' ' ' '
W I' "
1WN-0007 1609-7.0 J-11 3 C ACT Check -
MTC-O - ' ' ' ~
WN 1WN-0011 1609-7.0 F-11 3 C ACT Check -
MTO C-Q -
y 1WN-0013 1609-7.0 E-11 3 C ACT Check -
MTO,C-Q - - - - -
7 1WN-Oo15 1609-7.0 C
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D-11 3 ACT Check -
MTC-Q -
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Unit 1 - 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 l'AS TY1'E TTTE REQ MT 81 REQ %fT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV GROUNDWATER DRAINAGE (WZ) 1WZ-0001 1581-1.0 G-3 3 C ACT Check -
MTO.C-O - - - - - -
1WZ-0003 1581-1.0 G-5 3 C ACT Check -
MTO.C-O - - - - - -
1WZ-0005 1581-1 0 G-9 3 C ACT Check - MTO,C-O - - - - - -
1WZ-0007 1581-1.0 G-G 3 C ACT Check -
MTO.C-Q - - - - - -
1WZ-0009 1581-1.0 G-10 3 C ACT Check -
MTO.C-O - - - - - -
1WZ-0011 1581-1.0 G-13 3 C ACT Check -
MTO C-O - - - - - -
11/1/93 WZ - 1 of 1
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Unit 1 - McGuire Nuclear Stoflon Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST
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VALVE NUMBLR DIAGRAM COOR CLASS CATEGORY PAS TYPE TWE REQ MT #1 REQ'MT 82 REQST DEFERRAL REMARKS ALn1 NATIVES REV CONTROL AREA CHILLED WATER (YC) .
1YC-CD02A 1618-1 H42 3 B ACT Kerotest EMO ST-O - - - - - -
1YC-0007 .1618-1 K-02 3 C ACT Relief -
SP - - - -
30 PSIG -
1YC-0013 1618-1 K-09 3 C ACT Check -
MTO-O - - - - - -
1YC CD14 1618-1 K-10 3 C ACT Check -
MTO-O - - - - - -
1YC-CO38A 1618-1 E-12 3 B ACT Gate EMO ST-O - - - - - -
1YC-0039B 1618-1 F-12 3 8 ACT Gate EMO ST-O - - - - - -
1YC-0054 1618-1 H-09 3 B ACT Control -
FS-O - - - - - -
1YC-0076 1618-1 H-04 3 B ACT Control -
FS-O - - - - - -
1YC-0083B 1618-1 F-02 3 B ACT Kerotest EMO ST-O - - - - - -
1YC-0088 1618-1 C-02 3 C ACT Rehef -
SP - - - -
30 PSIG -
1YC-0094 1618-1 C-09 3 C ACT Check -
MTO-O - - - - - -
1YC-0095 1618-1 C-10 3 C ACT Check -
MTO-O - - - - - -
1YC-0113 1618-1 F-09 3 B ACT Contro! -
FS-O - - - - - -
1YC-0135 1618-1 F-04 3 B ACT Control -
FS-O - - - - - -
1YC-0148 1618-2 E-02 3 B ACT Control -
FS-O - - - - - -
1YC-0162 1618-2 E-03 3 B ACT Control -
FS-O - - - - - -
1YC-0176 1618-2 E-05 -3 B ACT Control -
FS-Q - - - - - -
11/1/93 YC - 1 of 2 -
k Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW 11.OW ASNfE VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF 1TST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REY .,
CONTROL AREA CHILLED WATER (YC) .
1YC-0190 1618-2 E-07 3 B ACT Control -
FS-Q - - - - - -
1YC-0204 1618-2 E-08 3 B ACT Control -
FS-O - - - - -
1YC4218 1618-2 E-10 3 B ACT Control -
FS-O - - - - - -
1YC-0232 1618-2 E-12 3 B ACT Control -
FS-O - - - - -
1YC424G 1618-2 E-14 3 B ACT Control -
FS-O - - - - - -
1YC-0347 1618-4 G-05 3 B ACT Control -
FS-O - - - - -
1YC-0357 1618-4 G-12 3 B ACT Control -
FS-O - - - - - -
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Unit 1 - McGuire Nuclect Station Inservice Testing Program FIDW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TLST RELIEF JUSTIF 0F TEST VALVE NUMBER DIACRAM COOR CLASS CATT. GORY PAS TYPE TYPE REQ MT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV a MAKEUP DEMINERAllZED WATER (YM) 1YM-01150 1601-2.4 C-09 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1YM-0116 1601-2.4 C-11 2 AC ACT Check -
MTC-O LT-RF -
1-MC-YM1 - RP -
11/1/93 YM - 1 of I r _ _ _ _ . .u_________.____m_m._________1 __ . -_
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1 McGuire Unit 1 DUKE POWER COMPANY McGUIRE NUCLEAR STAT;ON UNIT 1 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 submittal is 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 isolatiori 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 alternative to verify operability of check valves. The check valves where sample disassembly will be utilized will be specified in the contents of the program submittal and performed according to the guidelines of Generic Letter 89-04.
11/1/93 SECTION 11.1 1 of 1
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McGUIRE UNIT 1 l TABLE OF ABBREVIATIONS ANS )
Duke System Designed for Safety ;
Valve Class Code Desien Criteria Seistnic Loadine Class ;
A Class 1, ASME Section III,1971 Yes 1 B Class 2, ASME Section III,1971 Yes 2 C Class 3, ASME Section III,1971 Yes 3 D Class 2, ASME Section III,1971 No 2 E ANSI H31.1.0 (1967) No NSS F ANSI B31,1.0 (1967) Yes NSS G ANSI B31.1.0 (1967) No -
H Duke Power Company Specification No -
I.EGEND CAT - Category PC - Procedure Check CIV - Containment Isolation Valve PIV - Pressure Isolation Valve CL - Class Q - Quarterly !
CS - Cold Shutdown RF - Refueling Outage 'j FS - Fail Safe RR - Relief Request LT - Leak Test SL) - 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 j
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RELIEF REOUEST JUSTIFICATION OF DEFERRAL 1- MC . RR - VG - 1 1.- MC - CA - 1' l SEQUENCE l SEQUENCE !
TEM SYSTEM RELIEF REQUEST STATION STATION UNIT UNIT 11/1/93 SECTION 11.2 1OF1 l
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McGuire Unit 1 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 retum 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 i Refueling Outage (RF) conditions.
Stroke Time (ST) 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 (LIJ 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 irwolved. 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 means.
. Quarlerly 10) Testing will be performed at least once per three months.
11/1/93 SECTION 11.3 1OF2
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2 McGuire Unit 1 Refuelino Outaae (RF) Testing will be performed when the unit is shut down for refue!ing. Test-ing may be done while in No Mode as well as Modes 3,4,5 and 6.
Refue!ina 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 setpoint. Testing will be performed per the requirements of IWV-3510.
Failsafe (FS) Valve will be tested to verify it will reposition to its design safe position upon loss of control air per IWV-3415.
Passive Valve does not perform a mechanical motion during the course of accom-plishing a system safety function. (IWA-9000) t 11/1/93 SECTION 11.3 2OF2 h
r-INSERT THE FOLLOWING SECTION UNDER TAB: ;
II.4 5
m UNIT 1
Unit 1 - M:Guire Nuclect Station Inservice Testing Program FLOW FLOW ASME VALVE Ar T VALVE. ACTUATOR IT.ST TEST RELIEF .IUSTIF OF TEST VALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ MT #1 REQMT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SERVICE WATER SYSTEM (RN)
CRN40028 1574-1.0 K-10 3 B ACT Butterfly EMO ST-O - - - - - -
OR40003A 1574-1.0 K-10 3 B ACT Butterfly EMO ST-O - - - - -
ORN-0004AC 1574-1.0 F-13 3 B ACT Butterfly EMO GT-Q - - - - - -
ORN4005B 1574-1.0 E-12 3 8 ACT Butterfiy EMO ST-O - - - - - -
ORN4007A 1574-1.0 J-09 3 B ACT Butterfty EMO ST-O - - - - - -
ORS 00090 1574-1.0 D-09 3 0 ACT Butterfly EMO ST-O - - - - - -
OP 0010AC 1574-1.0 G-11 3 8 ACT Butterfly EMO ST-O - - - - - -
ORN-00118 1574-1.0 F-11 3 B ACT Butterfly EMO ST-O - - - - - -
ORM-0012AC 1574-1.0 1-11 3 B ACT Butterfly EMO ST-O - - - - - -
ORN-0013A 1574-1.0 J-11 3 0 ACT Butterf!y EMO ST-O - - - - - -
ORN4014A . 1574 1.0 1-13 3 8' 'ACT Butter 1!y EMO ST-O - - - - - -
ORN-0015B 1574-1.0 F-13 3 B ACT Butterfly EMO ST-O - - - - - -
ORN-0147AC 1574-1.0 H-02 3 0- ACT Butterfty EMO ST-O - - - - - -
ORN-0148AC 1574-1.0 H-03 3 B ACT Butterity EMO ST-O - - - - - -
ORN-0149A 1574-1.0 J-07 3 8 ACT Butterffy EMO ST-O - - - - - -
ORM-0150A 1574-1.0 I-06 3 B ACT Butterfty EMO ST-O - - - - - -
ORN41518 1574-1.0 F-06 3 B ACT Butterfly EMO ST-O - - - - - -
11/1/93 RN - 1 of 2
Unit 1 - McGuire Nuclear Station Inservice Testing Progrom FLOW FLOW ASME VAtXE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TEST VALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS TWE TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SERVICE WATER SYSTEM (RN)
ORN-0152B 1574-1.0 E-07 3 B ACT Butterfly EMO ST-O - - - - - -
ORN-0283AC 1574-1.0 F-02 3 B ACT Buttetfly EMO ST-O - - - - - -
ORN42848 1574-1.0 F-02 3 B ACT Buttedly EMO ST-O - - - - - -
ORN-0301AC 1574-1.0 G-10 3 0 ACT Butterfly EMO ST-O - - - - - -
ORN-03028 1574-1.0 F-10 3 B ACT Butterfty EMO ST-O - - - - - -
11/1/93 RN - 0 of 2
Unit 1 - McGuire Nacioct Station Inservice Testing Progrom FLOW nOW ASME VALVE ACT VALVE ACTUF(OR TEST TEST RELIEF JLSIIF OF TEST
"~
VALVE NUMBER DIAGRAM COOR Cl ASS CATEGORY PAS TYPE TYl'E REQ'MT #1 REQMT #2 REQ 5T DEFERRAL REMARKS ALTERNATIVES REV STEAM GENERATOR BLOWDOWN RECYP E (BB) 1 BB-C001 B 1580-1.0 H42 2 B ACT Gate AOV ST-O - - - - - -
1BB-00028 1580-1.0 t:44 2 B ACT Gate AOV ST-O - - - - - -
IBB-C003B 1580-1.0 H-10 2 B ACT Gate AOV ST-O - - - - - -
1BB4004B 1580-1.0 H-10 2 B ACT Gate AOV ST-O - - - - - -
1BB-C005A 1580-1.0 F-02 2 B ACT Gate AOV ST-O - - - - - -
1 BB-0006A 1580-1 0 F-04 2 B ACT Gate AOV ST-O - - - - - -
I BB-0007A 1580-1.0 F-12 2 B ACT Gate AOV ST-O - - - - - -
1 BB-0008A 1580-1.0 F-10 2 B ACT Gate AOV ST-O - - - - - -
11/1/93 BB - 1 of 1
-. + - _ _ . ._
Unit 1 - McGuire Nuclear Station Inservice Testlog Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUS 11F OF TEST
- VALVE NUMBER DIAGRAM .COOR CLASS CATEGORY PAS TiPE TYPE REQ'MT #1 REQ 1TT82 REQST DEF ERRAL REMARKS ALTERNATIVES REV AUXIUARY FEEDWATER (CA) 1CA4007AC 1592-1.1 B-10 3 B ACT Gate EMO ST-O - - - - - I 1CA-0008 1592-1.1 B-11 3 C ACT Check -
MTC-O - -
1-MC-CA3 - RF# -
1CA M 1592-1.1 C-05 3 B ACT Gate EMO ST-O - - - - - -
1CA-0010 1592-1.1 C-05 3 C ACT Check -
M10-0 - -
1-MC-CA3 -
RF# -
1CA-0011 A . 1592-1.1 B-04 3 D ACT Gate EMO ST-O - - - - - -
1CA-0012 1592-1.1 B-03 3 C ACT Check -
MTC-O - -
1-MC-CA3 -
RF# - '
ICA-0015A 1592-1.1 D-03 3 B ACT Gate EMO ST-O - - - - - -
1CA-0018D .1592-1.1 D-04 3 D ACT Gate EMO ST-O - - - - - -
ICA-0020AB 1592-1.1 1-10 3 AC ACT Control AOV ST-O LT - - - - -
- 1CA-0022 1592-1.1 1-10 3 C ACT Check -
MTO-O - - - - - -
1CA-0026 1592-1.1 1-04 3 C ACT Check -
MTO-O - - - - - -
ICA-0027A 1592-1.1 J--05 3 AC ACT. Control AOV ST-O LT - - - - -
1C A-0031 1592-1.1 1-07 3 C ACT Check -
MTO-O - - - - - -
ICA-0032B 1592-1.1 J-08 3 AC ACT_ Control AOV ST-O LT - - - - -
1CA-0036AB 1592-1.0 L-10 3 D ACT Control AOV ST-O - - - - - -
ICA-0037 1592-1.0 K-14 2 C ACT Check -
MTO.C-O - -
1-MC-CA1 - - -
1CA-0038B 1592-1.0 J-14 2 B ACT- Gate EMO ST-O - - - - - -
11/1/93 CA - 1 of 3
Unit 1 - McGuire Nuclear Station Inservice Testing Program FIDW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REllEF RJSTIF OF TEST V ALVE NUM15ER DIAGRAM COOR CLASS CA1EGORY PAS TYPE TYPE REQ'MT *1 REQMT #2 REQST DEFERRAL REMARKS ALTERNA1TVES PfV' ~
AUXILIARY FEEDWATER (CA) 1CA-00dCB 1592-1.0 G-14 3 B ACT Controt , AOV ST-O - - - - - -
ICA-0041 1592-1.0 H-14 2- C ACT Check -
MTOC-O - -
1-MC-CA1 - - -
1CA-0042B 1592-1.0 l-14 2 B ACT Gate EMO ST O - - - - - -
1CA-00448 1592-1.0 C-11 3 S ACT Control AOV ST-O - - - - - -
1CA-0045 1592-1.0 C-09 2 C ACT Check -
MTO,C-O - - 1-MC-CA1 - - -
1CA-00468 1592-1.0 D-08 2 B ACT Gate EMO ST-O - - - - - -
1 CA-00.48AB 1592-1.0 K-08 3 B ACT Control AOV ST-O - - - - - -
1CA-0049 1592-1.0 H48 2 C ACT Check - MTO,C-O - -
1-MC-CA1 - - -
1CA-OO50B 1592-1.0 G-08 2 B ACT Gate EHO ST-O - - - - - -
! 1CA-0052AB 1592-1.0 K-07 3 B ACT Control AOV ST-O - - - - - -
1CA-0053 1592-1.0 H-07 2 C ACT Check -
MTO.C-O - -
1-MC-CA1 - - -
.1 CA-005'4AC 1592-1.0 G-07 2 B ACT Gate Eiv.? ST-O - - - - - -
1CA-0056A 1592-1.0 C-04 3 B ACT Control AOV o r-v - - - - - -
1CA-0057 1592-1.0 C-06 2 C ACT Check - MTO,C-O - -
1-MC-CA1 - - -
1CA4058A 1592-1.0 D-07 2 B ACT Gate EMO ST-Q - - - - - -
1CA-0060A 1592-1.0 G-01 3 B ACT Control AOV ST-O - - - - - -
1CA-0061 1592-1.0 H-01 2 C ACT Check - MTO,C-O - -
1-MC CA1 - - -
11/1/93 CA - 2 of 3
i l
l Unit 1 - McGuire Nuclec- Station Inservice Testing Program VALVE ACT VALVE AC113ATOR TEST TEST RELIEF JUSTIF OF TEST FLOW FLOW ASME DEFERRAL REMARKS ALTERNATIVES REV VALVE NUMBER DIAGPAM CCOR CLASS CATFGORY PAS TYPE TYPE REQhff 81 REQ' Afr #2 REQST AUXIUARY FEEDWATER (CA) 1CA-0062A 1592-1.0 1-01 2 B ACT Gate EMO ST-O - - - -
ICA-0064AB 1592-1.0 L-04 5 B ACT Control AOV ST-O ' - - -
1CA-0065 1592-1.0 K-01 2 C ACT Check -
MTO.C-O - -
1-MC-CA1 - -
1CA-006 SAC 1592-1.0 J-01 2 B ACT Gate EMO ST-O - - - -
1CA-0086A 1592-1.1 C-14 3 B ACT Gate EMO ST-O - - - -
1CA-01160 1592-1.1 E-14 3 B ACT Gate EMO ST-O - - - -
D-13 3 C ACT Relief SP - - - 135 PSIG -
1CA-0128 1592-1.1 - -
C-14 3 C ACT Check MTO.C-O - 1-MC-CA2 - RF# -
1CA-0165 1592-1.1 - -
F-14 3 C ACT Check MTO.C-O -
1-MC-CA2 - RF# -
1CA-0166 1592-1.1 - -
1CA-0167 1592-1.1 F-2 3 C ACT Relief -
SP - - - -
135 PStG -
1CA-0168 1592-1.1 E-6 3 C ACT Relief -
11/1/93 CA - 3 of 3
l' i
Unit 1 - McGuire Nuclear Station l Inservice Testing Program I
FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TEST VALVE NUMBFR DIAGRAM COOR CLASS CATFCORY PAS TYPE TWE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTER!JATWES . REV FEEDWATER (CF) e 1CF-0017AB 1591-1.1 K-03 B ACT Globe AOV ST-O - -
1-MC-CF2 - - -
33 p 1CF-0020AB 1591-1.1 K-06 B ACT Globe AOV ST-O - -
1-MC-CF2 - - -
gg 7 1CF-0023AB 1591-1.1 K-09 ^ * ^ ' ' ' ' '
Ct. ASS F .
E
- 1CF-0026AB 1591-1.1 H-03 2 B ACT Gate g a ST-O - -
1-MC-CF1 - - -
ICF-0028AB 1591-1.1 H-06 2 B ACT Gate ,
ST-O - -
1-MC-CF1 - - -
1CF-0030AB 1591-1.1 H-09 2 B ACT Gate y ST-O - -
1-MC-CF1 - - -
1CF-0032AB 1591-1.1 K-13 B ACT Globe AOV ST-O - -
1-MC-CF2 - - -
C SS F 1CF-0035AB 1591-1.1 H-13 2 B ACT Gate ST-O - -
1-MC-CF1 - - -
H 1CF-0104AB 1591-1.1 K-12 ^ U" ' ^ ~ ' ' ' ~
CLASS F 1CF-0105AB 1591 1,1 K-09 B ACT Conho. AOV ST-O - -
1-MC-CF4 - - -
C SS F 1CF-0103AB 1591-1.1 - K-05 ^ ' ^ ' ' ' ~ ~
CLASS F +
1CF-0107AB 1591-1.1 K-02 ^ " ^ ~ ' ' ' '
~~
CLASS F 1CF-0126B 1591-1.1 H-14 2 B ACT Gate EMO ST-O - -
1-MC-CF3 - - -
1CF-01278 1591-1.1 H-10 2 B ACT Gate EMO ST-O - -
1-MC-CF3 - - -
1CF-0128B 1591-1.1 H-07 2 B ACT Gate EMO ST-O - -
1-MC-CF3 - - -
- 1CF-01298 - 1591-1.1 H-03 2 B ACT Gate EMO ST-O - -
1-MC-CF3 - - -
1CF-0134A 1591-1.1 G-13 2 B ACT Kerotest - EMO- ST-O - - - - - -
11/1/93 CF - 1 of 2
Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSITF OF TT.ST VALVE NUMBER DIAGRAM COOR CLASS CAITGORY PAS TWE TWE REQ'MT #1 REQ'MT 82 REQST DEFEKKAL REMARKS ALTERNATIVES REV FEEDWATER (CF) 1CF-0135A 1591-1.1 G-10 2 B ACT Kerotest EMO ST-O - - - - -
1CF-0136A 1591-1.1 G-07 2 B ACT Korotest EMO ST-O - - - - - -
1CF-0137A 1591-1.1 G43 2 B ACT Kerotest EMO ST-O - - - - - -
1CF 0151B 1591-1.1 G-12 2 B ACT Gate EMO ST-O - - - - - -
1CF-0152 1591-1.1 F-12 2 C ACT Check -
MTC-O - -
1-MC-CFS - - -
1CF-01538 1591-1.1 F-08 2 B ACT Gate EMO ST-O - - - - - -
1CF-0154 1591-1.1 E-08 2 C ACT Check -
MTC-O - -
1-MC-CF5 - - -
1CF-0155B 1591-1.1 F-07 2 B ACT Gate EMO ST-O - - - - - -
1CF-0156 1591-1.1 E-07 2 C ACT Check -
MTC-O - -
1-MC-CF5 - - -
1CF-01578 1591-1.1 G-12 2 B ACT Gate EMO ST-O - - - - - -
1CF-0158 1591-1.1 F-12 2 C ACT Check -
MTC-O - -
1-MC-CF5 - - -
.11/1/93 CF - 2 of 2'
1 Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW f1DW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JLW OF 1EST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ 11T #1 REQ'MT #2 REQST DEFERRAL REMARKS . ALTERNATIVES REV -
DIESEL GENERATOR ENGINE FUEL OIL (FD) 1FD-0005 1609-3.0 E-2 3 C ACT Relief -
SP - - - -
50 PSIG -
1 FD-0013 1609-3 0 C-14 3 C ACT Relief -
SP - - - -
50 PS!G -
1 FD-0016 1609-3.0 H-14 3 C ACT Check -
MTO.C-O - - - - - -
SET @ HEADER 1 FD-0018 1609-3.1 1-10 3 C ACT Relief -
SP - - - -
PRESSURE 1 FD-0028 1609-3.1 E-2 3 C ACT Relief -
SP - - - - 50 PStG -
1FD-0036 ' 1609-3.1 C-14 3 C ACT Reliei -
SP - - - -
50 PSIG -
1 FD-0039 1609-3.1 H-14 3 C ACT Check - MTO,C-O - - - - - -
1 FD-0041 1609-3.1 1-10 3 C ACT Relief -
SP - - - - '
R SS RE 1 FD-0083 1609-3.0 D-2 3 C ACT Relief -
SP - - -
10 PSIG -
IFD-0092 1609-3.0 E-13 3 C ACT Check - MTO,C-O - - - - - -
1 FD-0093 1609-3.0 J-14 3 C ACT. Check -
MTO.C-O - - - - - -
1 FD-0096 1609-3.1 0-2 3 C ACT Relief -
SP - - - -
10 PSIG -
1FD-0104 1609-3.1 E-13 3 C ACT Check - MTO,C-O - - - - - -
1 FD-0105 1609-3.1 J-14 3 C. ACT Check - MTO,C-O - - - - - -
11/1/93 FD - 1 of 1
- x. .
Unit 1 -' McGuire Nuctect Station Inservice Testing Program FLOW FLOW ASME VALVE ACF VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBLR DIAGRAM COOR CLASS CATEGORY PAS TWE TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV. -
REFUELING WATER (FW) 1 FW-0001 A 1571-1.0 E-11 2 B ACT Gate EMO ST-O - - - - - -
I FW-0004 1571-1.0 D-08 2 A PAS Gate -
LT-RF - - - ~ '
C S 1 FW-0005 1571-1.0 C-07 2 A PAS Cbeck -
LT-RF - - - - - -
1 FW-0011 1571-1.0 C-02 2 A PAS Diaphram -
LT-RF - - - ' ~
C D 1 FW-0013 1571-1.0 D-02 2 A PAS Diaphram -
LT-RF - - - ' ~
C S 1 FW-0027A . 1571-1.0 C-12 2 B ACT Gate EMO ST-O - -
1-MC-FW1 - - -
1 FW-0028 1571-1.0 B-11 2 C ACT Check -
MTO.C-C - - 1-MC-FW2 - - -
1 FW-00328 1571-1.0 E-11 2 B ACT Gate EMO ST- - - - - - -
1FW-0033A 1571-1.0 F-11 2 D ACT Kerotest EMO ST-O - - - - - -
1 FW-0049B 1571-1.0 F-10 2 D ACT Kerotest EMO ST-O - - - - - -
1 FW-0052 1571-1.0 1-05 ^ ' ~ ~ ~ ' ' ' '
C SS E 1 FW-0067 1571-1.0 C-01 2 A PAS Check - LT-RF - - - - - -
1FW-0074 1571-1.0 J-14 3 C ACT Check -
MTC-O - - - - - -
11/1/93 FW - 1 of1
.m l
I' Unit 1 - McGelre Nuclear Station Inservice Testing Program l
FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUST1F OF TEST
^
VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE DPE REQ'MT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV AIRLOCK (IA)
IIA-5080 1499-IA1 N/A 2 A ACT Solenok! SOV ST-O LT-RF - - - - -
IIA-5160 1499-IA1 N/A 2 A ACT Solenoid SOV ST-O LT-RF - - - - -
11A-5260 1499-IA1 N/A 2 AC ACT Check -
LT-RF - -
1-MC-IA1 - - -
Il A-5270 1499-!A1 N/A 2 AC ACT Check -
LT-RF - -
1-MC-lA1 - - -
ilA-5280 1499-IA1 N/A 2 AC ACT Check -
LT-RF - -
1-MC-IA1 - - -
IIA-5290 1499-lA1 N/A 2 AC ACT Check -
LT-RF - -
1-MC-1A1 - - - t ilA-53GO 1499-1A1 N/A 2 AC ACT Check -
LT-RF - -
1-MC-IA1 - - -
11A-5310 1499-IA1 N/A 2 AC ACT Check -
LT-RF - -
1-MC-tA1 - - -
IIA-5320 1499-IA1 N/A 2 AC ACT Check -
LT-RF - -
1-MC-IA1 - - -
flA-5330 1499-!A1 N/A~ 2 AC ACT Check -
LT-RF - -
1-MC-IA1 - - -
11A-5340 1499-lA1 F#A 2 AC ACT Check -
LT-RF - -
1-MC-IA1 - - -
- t tA-5350 1499-lA1 N/A 2 AC ACT Check -
LT-RF - -
1-MC-IA1 - - -
IIA-5230 1499-1A1 N/A 3 AC ACT Check -
LT-RF - -
1-MC-IA1 - - -
IIA-5370 1499-IA1 N/A 3 AC ACT Check -
LT-RF - - 1-MC-IA1 - - -
IIA-5380 1499-IA1 N/A 3 AC ACT - Check -
LT-RF - -
1 -MC-lA1 - - -
IIA-5390 1499-IA1 N/A 3 AC ACT Check -
LT-RF - -
1-MC-IA1 - - -
11/1/93 IA - 1 of 1
~
._A.-
Unit 1 - McGuire Nuclear Station Inservice Testing Progrom FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF 1TST ,
VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV COMPONENT COOLING (KC) 1KC-0001 A 1573-1.0 C-07 3 B ACT Butterfly EMO ST-O - - - - - -
1 KC-0002B 1573-1.0 C-08 3 B ACT Butterfly EMO ST-O - - - - - -
1KC-0003A 1573-1.0 C-07 3 B ACT Gate EMO ST-O - - - - - -
1KC-0005 1573-1.0 F-04 3 C ACT Check -
MTO-O - - - - - -
1KC-0008 1573-1.0 F-04 3 C ACT Check -
MTO-O - - - - - -
1KC-0011 1573-1.0 F-11 3 C ACT Check -
MTO-O - - - - - -
1KC-0014 1573-1.0 F-11 3 C ACT Check -
MTO-O - - - - - -
1KC 40188 1573-1.0 C-08 3 8 ACT Gate EMO ST-O - - - - - -
1KC-0047 1573-4.0 L-12 2 AC ACT Check MTC-O LT-RF 1-MC-KC9 MT-RF -
1KC-0050A 1573-1.0 K-07 3' B ACT Butterfly EMO ST-O - - - - - -
1 KC-0051 A 1573-1.0 J-05 3 8 ACT Gate EMO ST-O - - - - - -
1KC-0053B 1573-1.0 K-08 3 B ACT Butterfly EMO ST-Q - - - - - -
1KC-0054B 1573-1.0 J-10 3 B ACT Gate EMO ST-O - - - - - -
1KC-0056A 1573-1.1 E-02 3 8 ACT Butterffy EMO ST-O - - - - - -
1KC-0057A 1573-1,1 D-06 3 B ACT Butterffy ' AOV ST-O - - - - - -
I KC-0061 1573-1.1 E-05 3 C ACT Check -
SP - - - -
150 PSIG -
' 1 KC-0079 1573-1.1' B45 3 C ACT Check -
SP - - - -
150 PSIG -
1KC-00818 1573-1.1 E-13 3 B ACT Butterfly EMO ST-O - - - - - -
11/1/33 KC - 1 of 5
Unit 1 - McGuire Nuclear Sfotion Inservice Testing Progrorn FLOW FIDW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TEST DEFERRAL REMAR)3 VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQMT #2 REQST ALTERNATI\TS REV COMPONENT COOLING (KC) 1KC-0082B 1573-1.1 D-09 3 B ACT Butterfly AOV ST O - - - - - -
1KC-0086 1573-1.1 E-10 3 C ACT Relief -
SP - - - -
150 PStG -
1KC-0104 1573-1.1 B-10 3 C ACT Relief -
SP - - - -
150 PSIG -
1 KC-0108 1573-1.1 G-06 3 C ACT Check -
MTC-O - - - - - -
1KC-0112 1573-1.1 G-09 3 C ACT Check -
MTC-O - - - - - -
1KC-0138 1573-2.0 E-12 3 C ACT Relief -
SP - - - -
150 PSIG -
1 KC-0147 1573-2.0 E-09 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0154 1573-2.0 C-06 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0161 1573-2.0 F-03 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0170 15734.0 C-12 3 C ACT Relief -
SP - - - -
150 PS!G -
1KC-0187 1573-2.1 H42 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0193 1573-2.1 F-02 3 C ACT Relief -
SP - - - -
150 PSIG -
. 1 KC-0199 1573-2.1 D-02 3 C ACT Relief -
SP - - - -
150 PStG -
1KC-0205 1573-2.1. D-13 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0211 1573-2.1 F-13 3 C ACT Relief -
SP - - - -
150 PSIG -
1XC-0217 1573-2.1 H-13 3 C ACT Relief -
SP - - - -
150 PStG -
1 KC-0223 1573-2.1 J-13 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0228B 1573-1.0 K-08 3 B ACT Gate EMO ST-O - - - - - -
o 4
11/1/93 KC - 2 of 5 e
Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JL*STIF OF TEST CLASS CATEGORY PAS TWE
~
VALVE NUMBER DLAGRAM COOR TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV COMPONENT COOLING (KC) 1 KC-0230A 1573-1.0 K-07 3 B ACT Gate ' EMO ST-O - - - - - -
1 KC-0234 1573-22 G-09 3 C ACT Relief -
SP - - - - 150 PStG -
1KC-0241 1573-2.2 G-11 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0248 1573-22 G-14 3 C ACT Relief -
SP' - - - -
150 PSIG -
1 KC-0261 1573-2.2 G-06 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0268 1573-2 2 G-04 3 C ACT Relief -
SP - - - -
150 PSIG -
1 KC-0275 1573-22 G-02 3 C ACT Relief -
SP - - - -
150 PSIG -
iKC-0279 1573-3.1 K-04 2 AC ACT Check -
MTC-O LT-RF -
1-MC-KC7 -
MT-RF -
1KC-0280 1573-3.1 D-01 2 AC ACT Check -
MTC-Q LT-RF -
1-MC-KC5 -
MT-RF -
1KC-0281 1573-3.1 J-02 3 C ACT Relief -
SP - - - -
150 PStG -
1 KC-0305B 1573-3 1 D-14 2 B ACT Gate EMO ST-O - - - - - -
IKC-0313 1573-3.1 1-13 2 C ACT Relief -
SP - - - -
150 PSIG -
1KC-03158 1573-3.1 L-13 2 B ACT Gate EMO ST-O - - - - - -
1KC-0320A 1573-3.1 C-10 2 A ACT Diaphram AOV ST-O LT-RF -
1-MC-KC4 - - -
1 1KC-0322 1573-3.1 C-09 2 AC ACT Check -
MTC-O LT-RF -
1-MC-KC6 -
MT-RF --
1KC-0330 1 $73-3.1 C45 3 C ACT Relief -
SP - - - -
150 PSIG -
. 1KC-0332B 1573-3.1- D-01 2 A ACT Diaphram AOV ST-O LT-RF -
1-MC-KC3 - - -
1KC-0333A 1573-3.1 G-01 2 A ACT Diaphram AOV ST-O LT-RF -
1-MC-KC3 - - -
11/1/93 KC - 3 of 5
l I
! Unit 1 - McGuire Nuclear Station l Inservice Testing Program l
FLOW FLOW ASME VALVE ACT VALVE AC113ATOR TEST TEST RELIEF JL5TIF OF TEST
, VAIXE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYPE TWE REQ'MT #1 REQ MT #2 REQST DEFERRAL RGLMG3 ALTERNATTVES REV '
COMPONENT COOLING (KC) 1KC-03388 1573-3.1 D-12 2 A ACT Butterfty EMO ST-O LT-RF -
1-MC-KC2 - - -
1MC-0340 1573-3.1 E-12 2 AC ACT Check -
MTC-O LT-RF -
1-MC-KC8 -
MT-RF -
1KC-0349 1573-3.0 G-09 2 C ACT Relief -
SP - - - -
2485 PSIG -
1 KC-0355 1573-3.0 E-14 3 C ACT Relief -
SP - - - -
150 PSIG ' -
1KC-0361 '1573-3.0 F-13 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0368 1573-3.0 H 49 2 C ACT Relief -
SP - - - -
2485 PSIG -
1KC-0374 1573-3.0 J-14 3 C ACT Re%f -
SP - - - -
150 PStG -
1KC-0380 1573-3.0 K-13 3 C ACT Relief -
SP - - - -
150 PSIG ~
1XC-0386 1573-3.0 K-03 3 C ACT Relief -
SP - - - -
150 PSIG -
1 KC-0392 -1573-3.0 J-02 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0398 1573-3.0 1-06 2 C ACT Relief -
SP - - - -
2485 PSIG -
1 KC-040'4 1573 4 0 G-02 3 C ACT Relief -
SP - - - -
150 PSIG -
- KC-0410 1573-3.0 E-02 3 C ACT Re!ief -
SP - - - -
150 PSIG -
- KC-0417 1573-3.0 D07 2 C ACT Relief -
SP - - - -
2485 PSIG -
1MC-0424B 1573-3.1 L-04 2 A ACT Butterfly EMO ST-O LT-RF -
1-MC-KC1 - - -
1KC-0425A 1573-3.1 L-06 2 A ACT Butterfly EMO ST-O LT-RF -
1-MC-KC1 - - -
1KC-04298 1573-4.0 K-12 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1KC-0430A 1573-4.0 K-10 '2 A ACT Kerotest EMO ST-O LT-RF - - - - -
11/1/93- KC - 4 of 5
Unit 1 - McGuire Nuclect Stafion Inservice Testing Program rLOW FtXMV ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTTF OF TTST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TWE TYPE REQ ~MT #1 RFQ MT 82 REQST DEFERRAL REMARKS ALTERNATIVES REV COMPONENT COOLING (KC) .
1XC-0458 1573-4.0 C-10 3 C ACT Reiief -
SP - - - -
150 PSIG -
1KC-0431 1573-4.0 E-08 3 C ACT Relief -
SP - - - -
150 PSIG -
-1 KC-0472. 1573-4.0 E-05 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-04E0 1573-3.1 E-09 3 C ACT Relief -
SP - - - -
150 PSiG -
1 KC-0491 1573-3.1 F-09 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0492 1573-3.1 H-09 3 C ACT Relief -
SP - - - -
150 PSIG -
1KC-0493 1573-3.1 J49 3 C ACT Relief -
SP - - - -
150 PSIG -
I KC-0495 1573-1.1 G-05 3 C ACT Check -
MTO-O - - - - - -
1 KC-0498 1573-1.1 G-10 3 C ACT Check -
MTO-O - - - - - -
1KC-0800 1573-1.1 1-11 3 C ACT Relief -
SP - - - -
10 PSIG -
1KC-0897 1573-1.0 K-2 3 C ACT Check -
MTC-O - - - - - -
1KC-0903 1573-1.0 K-13 3 C ACT Check -
MTC-O - - - - - -
1 KC-0958 1573-1.0 1-8 3 C ACT Check -
MTC-O - - - - - -
1 KC-0972 1573-1.1 J-10 3 C ACT Relief -
SP - - - -
15 PSIG -
11/1/93 KC - 5 of 5
_____-_____.-._.__.m_________m- - - _ - - - _ ^_ __--- - - -
Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW AShfE VALVE ACT VALVE ACTUATOR TEST 1T.ST L TlEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ MT #1 REQ'MT #2 REWT DEFERR.AL REMARKS ALTERNATIVES REV DIESEL GENERATOR COOLING WATER (KD) 1 KD-0C09 1609-1.0 E-14 3 B ACT Control ADV FS-O - - - - -
1KD-0016 1609-1.0 C-07 3 C ACT Cheek - MTO,C-O - - - - - -
1KD-0018 1609-1 0 G-06 3 C ACT Check -
MTC-O - - - - - -
1KD-0029 1609-1.1 E-14 3 B ACT Control AOV FS-O - - - - - -
1KD-0036 1609-1.1 C-07 3 C ACT Check -
MTO.C-O - - - - - -
1 KD-0038 1609-1.1 G-06 3 C ACT Check -
MTC-O - - - - - -
11/1/93 KD - 1 of 1
Unit 1 - McGuire Nuclect Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR 'EST TEST RELIEF ]LSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE 'MT#1 REQ MT #2 REQST DETERRAL REMARKS ALTERNATIVES REV SPENT FUEL COOLING SYSTEM (KF) 1KF-0020 1570-1.0 K-5 3 C ACT Relief -
SP - - - -
150 PSIG -
1 KF-0031 1570-1.0 1-5 3 C ACT Relief -
SD - - - -
150 PSIG -
11/1/93 KF - 1 of 1
Unit 1 - McGuire Nuclear Station Inservice Tesfing Program FLOW n.OW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUST1F OF TEST
~~
V ALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS T1TE TYPE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV DIESEL LUBE OIL (LD) 1LD M 1 1609-2.0 1-10 3 C ACT Relief -
SP - - - -
75 PSIG -
1LD-0002 1609-2.0 J 3 C ACT Check -
MTO-O - - - - - -
ILD-CD04 1609-2.0 G-13 ' 3 C ACT Relief -
SP - - - -
75 PSIG -
1LD-0005 1609-2.0 G-13 3 C ACT Check -
MTC-O - - - - - -
1LD-0009 1609-2.0 F-09 3 C ACT Relief -
SP - - - -
45 PSIG -
1LD4011 1609-2.0 F-06 3 C ACT Relief -
SP - - - -
75 PSIG -
1LD-CD13 1609-2.0 H43 3 C ACT Retef -
SP - - - -
50 PSIG -
1LD-0031 1609-2.1 J-10 3 C ACT: Relief -
SP - - - -
-75 PSIG -
1LD-0032 1609-2.1 K-12 3 C ACT Check -
MTO-O - - - - - -
1LD-0034 1609-2.1 H-13 3 C ACT Relief -
SP - - - -
75 PStG -
1LD-0035 1609-2.1 1-13 3 C ACT Check -
MTC-O - - - - - -
l 1LD-0039 1609-2.1 H-09 3 C ACT Relief -
SP - - - -
45 PSIG -
1 LD-0041 1609-2.1 G-05 3 C ACT Relief -
SP - - - -
75 PSIG -
1LD-0043 1609-2.1 1-03 3 C ACT Relief -
SP - - - -
50 PSIG -
1LD-0108A 1609-2.0 G-12 3 B ACT Gate EMO ST-O - - - - -
- 1 LD-01138 1609-2.1 G-12 3 B ACT Gate EMO ST-O - - - - - -
11/1/93 LD - 1 of 1
Unit 1 - McGuire Nuclear Station inservice Testing Progrom MV FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RElfcF JUSTIF OF TEST VALVE NUMBER DLACRAM COOR CLASS CATECORY PAS TYPE TWE REQ MT #1 REQ'MT #2 REQST DEFER *AL REMARKS ALTERNATIVES REV RADIATION MONITORING (MI) 1Mi-5580 1499-M17 N/A 2 A ACT Solenod SOV ST-O LT-RF - - - - -
1MI-5581 1499-Mt7 N/A 2 A ACT Solenod SOV ST-O LT-RF - - - - -
' 1 Mi-5582 1499-Mt7 N/A 2 A ACT Solenod SOV ST-O LT-RF - - - - -
IMI-5583 1499-Mi7 N/A 2 A ACT Solenod SOV STO LT-RF - - - - -
11/1/93 MI - 1 of 1
i Unit 1 - McGuire Nuclear Station inservice Testing Program ROW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JL"STIF OF TEST VALVE NtJMBER DIAGRAM COOR CLASS CATEGORY I'A5 TYPE TWE REQ %!T 81 REQ MT 82 REQST DEFERRAL REMARKS ALTERNATIVES REV
~
BORON RECYLE (NB) 1NB-0003 1556-1.0 J-10 3 C ACT Relief -
SP - - - -
150 PSIG -
1NB-0103 1556-1.1 1-13 3 C ACT Check -
MTO-O - - - - - -
i l 1NB-02608 1556-3.0 - G-05 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
l 1 ND-0262 1556-3.0 G-03 2 AC ACT Check -
MTC-O LT-RF -
1-MC-NB1 -
MT-RF -
i l
l l
l l
11/1/93 NB - 1 of 1
I Unit 1 - McGuire Nuclect Station Inservice Testing Program o
FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TEST VALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS TYPE TTT'E REQMT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV REACTOR COOLANT (NC) 1NC-0001 1553-2.0 J-09 1 C ACT Relief -
SP - - - -
2485 PSIG -
1NC-0002 1553-2.0 J-10 1 C ACT Relief -
SP - - - -
2485 PSIG -
1NC-0003 1553-2.0 J-11 1 C ACT Relief -
SP - - - -
2485 PStG -
1NC-00318 1553-2.0 H-06 1 B ACT Gate EMO ST-Q - - - - - -
1NC-CO328 1553-2.0 J-06 1 B ACT Control AOV ST-O - -
1-MC-NC1 - - -
1NC-0033A 1553-2.0 H-04 1 B ACT Gate EMO ST-O - - - - - -
1NC-0034A 1553-2.0 J-04 1 B ACT Control AOV ST-O - -
1-MC-NCI - - -
1NC-0035B 1553-2.0 H-02 1 B ACT Gate EMO ST-Q - - - - - -
1NC-00368 1553-2.0 J-02 1 B ACT Control AOV ST-O - -
1 -MC-NC1 - - -
1NC-0053B 1553-2.1 1-10 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NC-0054A 1553-2.1 1-08 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
INC-00568 1553-2.1 E-13 2 A ACT Gate EMO ST-O LT-RF - - - - -
- 1NC-0057 1553-2.1 G-12 2 A PAS Check -
LT-RF - - - - - -
1NC-0059 1553-2.1 H-03 2 C ACT Check -
MTO-O - - - - - -
1NC-0141 1553-4.0 B-06 2 A PAS - Diaphram - -
LT-RF - - - -
1NC-0142 1553-4.0 B-05 2 A PAS Diaphram -
LT-RF - - - -
11/1/93 NC - 1 of 2
. ~ . . - _ _ _ _ - . _ _ _ _
Unit 1 - McGuire Nuclear Station Inservice Testing Program FlJCMV F1.OW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIFF JLSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ'MT #1 REQ MT #2 RrQST DETTRRAL REMARKS ALTERNATIVES REV REACTOR COOLANT (NC)
Isolated &
1NC-0195B 1553-4.0 K-07 2 A PAS Globe EMO LT-RF - - -
Tagged - -
CLOSED isolated &
1NC-0196A 1553-4.0 1-07 2 A PAS Globe EMO LT-RF - - -
Tagged - -
CLOSED 1NC-0259 1553-4.0 l-07 2 AC ACT Check -
MTC-O LT-RF -
1 MC-NC3 -
MT-RF* -
1NC-0261 1553-4.0 B-07 2 AC ACT Check -
MTC-O LT-RF -
1 -MC-NC3 - MT-RF* -
1NC-0272AC 1553-2,1 L-07 1 B ACT Globe Solenoid ST-O - -
1-MC-NC2 - - -
INC-0273AC 1553-2.1 L-07 1 B ACT Globe Solenoid ST-O - -
1-MC-NC2 - - -
1NC-02748 1553-2.1 K-07 1 B ACT Globe Solenoid ST-O - -
1-MC-NC2 - - -
1NC-02750 1553-2.1 K-07 1 B ACT Globe Solenoid ST-O - -
1 MC-NC2 - - -
1NC-0284 1553-2.1 H45 A heck -
MTO-O - - - - - -
CLASS E 11/1/93 NC - 2 of 2 '
L' _ - -
Unit 1 - McGuire Nuclear Station ,
inservice Testing Program FLOW FLOW ASME VALVE ACT VALV6 ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TWE TYPE REQ'MT 81 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV RESIDUAL HEAT REMOVAL (ND)
IND00018 1561-1.0 I-13 1 A ACT Gt s EMO ST-O LT-TS -
1-MC-ND1 -
P!V -
1 ND-0002AC 1561-1.0 H-13 1 A ACT Gate EMO ST-O LT-TS -
1-MC-ND1 -
PlV -
1ND-0GD3 1561-1.0 G-14 2 C ACT Refief -
SP - - - -
450 PSIG -
IND-00040 1561-1.0 E-12 2 B ACT Gate EMO ST-O - - - - - -
IND-0CD8 1561-1.0 D-08 2 C ACT Check - MTO,C-O - -
1-MC-ND6 - - -
1ND-C014 1561-1.0 D-03 2 B ACT Bu"erfly AOV ST-O - - - - - -
1ND-0015B 1561-1.0 E-03 2 B ACT Gate EMO ST-O - -
1-MC-ND3 - - -
1ND-G019A 1561-1.0 H-12 2 B ACT Gate EMO ST O - - - - - -
1ND-0023 1561-1.0 J-08 2 C ACT Check -
MTO.C-O - -
1-MC-ND6 - - -
1ND-0029 1561-1.0 J-03 2 B ACT But+erfly AOV ST-O - - - - - -
1ND-0030A 1561-1.0 1-03 2 B ACT Gate EMO- ST-O - -
1-MC-ND3 - - -
1ND-005G 1561-1.0 J-02 2 C ACT' Relief -
SP - - - -
600 PSIG -
1ND-0058A 1561-1.0 K-03 2 B ACT Gate EMO OT-Q - -
1 -MC-ND2 - - -
1ND-0631 1561-1.0 F-02 2 C ACT Relief -
SP - - - -
600 PSIG -
1ND-0G34 1561-1.0 E-02 2 C ACT Rehef -
SP - - - -
600 PSIG -
1NDOC37B 1561-1.0 B-09 '2 B ACT Kerotest EMO ST-O - - - - - -
1ND-0068A 1561-1.0 L-09 2 B ACT Kerotest EMO ST-O - - - - - -
IND-0070 1561-1.0 K-03 2 C ~ACT Check - MTO,C-O - -
1-MC-ND4 - - -
1ND-0071 1561-1.0 C-04 2 C ACT Check -
MTO.C-O - -
1-MC-NDS - - -
11/1/93 ND - 1 of 1
Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR fEST TEST REUEF JUST1F OF TEST ,.
Y ALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYTE TYTE FIQ MT #1 REQ %fT 82 REQST DEFERRAL REhtARKS ALTERNATIVES REV, ICE CONDENSER REFR!GERATION (NF) 1NF-0228A 1558-4 0 H-13 2 A ACT Diaphram AOV ST-Q LT-RF - - -
LT per TS -
1NF-0229 1558-4.0 F-13 2 AC ACT Check -
MTC-O LT-RF -
1 MC-NF1 -
MT-RF* -
1NF-02333 1558-4 0 K-12 2 A ACT Diaphram AOV ST-O LT RF - - - LT per TS -
INF-0234 A 1558-4.0 K 13 2 A ACT Diaphram AOV ST-Q LT-RF - - -
LT per TS -
il/1/93 NF - 1 of 1
I Unli 1 - McGuire Nuclect Station Inservice Testing Program FLOW FL OW ACME VALVE ACT VALVE ACTUATOR TEST TEST REllEF JLST1F CF TIST val.VE NUMBER DIAGRAM LTX7R CLASS CATEGORY PAS TWE TYPE REQMT #1 REQ MT #2 REQM DEFERRAL REM ARKS ALTERNATIVES REV SAFETY INJECTION (NI) 1N1-0009 A 1562-1.0 H-09 2 B ACT Gate EMO ST-O - -
1-MC-N11 - - -
INi@108 1562-1 0 G-09 2 B ACT Gate EMO ST-O -
1-MC-Nt 1 - - -
IN14012 1562-1.0 G-08 2 C ACT Check -
MTO-O - -
1-MC-Nt13 - - -
1Nt4015 1562-1.0 K47 1 C ACT Check -
MTO-O - -
1-MC-Nt12 - - -
I NT-0017 1562-1.0 1-07 1 C ACT Check -
MTO-O - -
1-MC-Ni12 - - -
1NI-0019 1562-1.0 F-07 1 C ACT Check -
MTO-O - -
1-MC-N112 - - -
1Ni-0021 1562-1.0 D-07 1 C ACT Check -
MTO-O - -
1-MC-N112 - - -
INi-0047A 1562-2.0 K-05 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1Nt4048 1562-2.0 K-03 2 AC ACT Check -
MTC-O LT-RF -
1-MC-N121 -
MT-RF* -
1Nt-0052 1562-2.0 E-05 2 C ACT Relief SP 700 PSIG -
1NI-0059 1562-2.0 D-13 1 AC ACT Check MTO.C-O LT TS 1-MC-Nt22 PiV RF# -
1N1-0060 1562-2.0 D-14 1 AC ACT Check MTO.C-O LT-TS 1-MC-NI24 -
PlV RF# .
1Ni-0033 1562-2.0 1-05 2 C ACT Rerief -
SP - - - -
700 PSIG -
1Ni-0070 1562-2.0 H-13 1 AC ACT Check MTO.C-O LT-TS -
1-MC-N122 -
PN RF# -
1Mi-0071 1562-2.0 H-13 1 AC ACT Check MTO.C-O LT-TS 1-MC-Ni24 -
PlV RF# -
1N1-0074 1562-2.1 J-05 2 C ACT Relief -
SP - - - -
700 PSIG -
1Nt4081 1562-2.1 C-03 1 AC ACT Check MTO.C-O LT-TS 1-MC-Ni22 -
PN RF# -
11/1/93 NI'- 1 of 5
~ .-
Unit 1 - McGuire Nuclect Station Inservice Testing Program FLOW FIDW ASME VALVE ACT VALVE ACTUATOR TEST TES~T RELIEF JUSTIF OF TEST CLASS CATEGORY PAS TYPE DPE REQMT #1 REQ MT #2 REQCT DETERRAL REMARKS AL11ERNATIVES REV V ALVE NUMBER DIAGRAM COOR SAFETY INJECTION (NI) 4 1N14082 1562-2.1 C-03 1 AC ACT Check -
MTO.C-O LT-TS -
1-MC-N124 - PIV RF# -
1N1-0086 1562-2.1 J-09 2 C ACT Retief -
SP - - - -
700 PSIG -
1Ni-0093 1562-2.1 C-08 1 AC ACT Chetk -
MTO.C-O LT-TS -
1-MC-Nt22 - PIV RF# -
1NHX)94 1562-2.1 C-08 1 AC ACT Check -
MTO C-O LT-TS -
1 -MC-Nt24 -
PlV RF# -
1NI-0095A 1562-2.1 F-12 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1N1-00960 1562-2.1 E-13 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NI-01000 1562-3.0 F-13 2 B ACT Gate EMO ST-O - - 1-MC-N!2 - - -
1 NI-0101 1562-3.0 F-13 2 C ACT Check -
MTO.C-O - -
1-MC-N114 - - -
1N1-0102 1562-3.0 1-13 2 C ACT Rehef -
SP - - - -
240 PSIG -
1NI-0103A 1562-3_0 J-14 2 B ACT Gate EMO ST-O - -
1 -MC-NI6 - - -
1NI-0114 1562-3.0 1-09 2 C ACT Check -
MTO-O - - - - - -
1Ni-0115B 1562-3.0 H-09 2 B ACT Kerotest EMO ST-O - -
1 MC-N13 - - -
1 N1-0116 1562-3.0 J-09 2 C ACT Check -
MTO.C-C - -
1-MC-N115 - - -
1NI-0118A 1562-3.0 H-07 2 B ACT Gate EMO ST-O - - - - - -
1Ni-0119 1562-3.0 K-07 2 C ACT Relief -
1NI-01200 1562-3.0 J-07 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NI-0121A 1562-3.0 J-06 2 B ACT Gate 'EMO ST-O - -
1-MC-N14 - - -
11/1/93 NI - 2 of 5
Unit 1 - McGuire Nucleon Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TTT'E TWE REQ MT #1 REQ'MT 82 REQST DEFERRAL REAtARKS ALTERNATIVES REV SAFETY INJECTION (NI) ,
1NIC124 1562-3 0 J43 1 AC ACT Check -
MTO C-O LT-TS -
1-MC-N116 -
PlV -
I Nf-0125 1562-3.0 1-03 1 AC ACT Check -
MTO.C-O LT-TS -
1-MC-N119 -
PlV -
1N14126 1562 4 0 J-02 1 AC ACT Check -
MTO,C-O LT-TS -
1-MC-NI19 -
PlV -
1N14128 1562-3.0 l-04 1 AC ACT Cneck -
MTO,C-O LT-TS -
1-MC-N116 -
_ PlV -
1N1-0129 1562-3.0 1 03 1 AC ACT Check -
MTO,C-O LT TS -
1-MC-N119 -
PlV -
1NI-0134 1562-3.0 G-04 1 AC ACT Check -
MTO,C-O LT-TS -
1-MC-N119 -
' PlV -
1N1-01358 1562-3 0 E-14 2 B ACT Gate EMO ST-O - - - - - -
INI-0136B 1562-3 0 C-14 2 B ACT Gate EMO ST-O - -
1-MC-Nf20 - - -
1Nt-0143 1562-3.0 F-09 2 C ACT Check -
MTO.C-O - - - - - -
1NI-0144B 1562-3 0 G-09 2 B ACT Kerotest EMO ST-O - - - - - -
1NI-0147A 1562-3.0 G-11 2 B ACT Kerotest EMO ST-O - -
1-MC-N13 - - -
INi-0148 1562-3.0 D-09 2 C ACT Check - MTO,C-O - -
1-MC-N115 - - -
1NI-0150B 1562-3.0 E-07 2 B ACT Gate EMO ST-O - - - - - -
1NI-0151 1562-3.0 C-07 2 C ACT Relief -
SP - - - -
1740 PStG -
1NI-01528 1562-3.0 D-06 2 B ACT Gate EMO ST-O - -
1-MC-N!4 - - -
1NI-0156 1562-3.0 D-03 1 AC ACT Check -
MTO.C-O LT-TS -
1-MC-NI16 -
PlV -
INT-0157 1562-3.0 D-02 1 AC ACT Check -
MTO,C-O LT-TS -
1-MC-N!16 -
PlV -
11/1/93 NI - 3 of 5
1 Unit 1 - McGuire Nuclear Station Inservice Testing Program F1.OW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST _
VALVE NUM5ER DIACRAM COOR CLASS CATEGORY PAS TITE TYPE REQ'MT #1 EEQ MT #2 REQST DETERRAL REMARKS ALTERNATIVES REV SAFETY INJECTION (NI) 1NI-0159 1562-3.0 0-04 1 AC ACT Check - MTO,C-O LT-TS -
1-MC-N116 -
PN -
1N14160 1562-3.0 B-03 1 AC ACT Check -
MTO,C-O LT-TS -
1-MC-N116 -
PIV -
1NI-0161 1562-3.1 K-12 2 C ACT Relief -
SP - - - -
1740 PS!G -
1N1-0162A 1562-3.1 K-11 2 B ACT Gate EMO ST-O - -
1-MC-N15 -
CS-NIS -
int 4165 1562-3.1 J-03 1 AC ACT Check -
MTO.C-O LT-TS -
1-MC-N117 - PN -
INi4167 1562 3.1 J45 1 AC ACT Check -
MTO.C-O LT-TS -
1-MC-NI17 - PlV -
1NI-0169 1562-3.1 J-06 1 AC ACT Check -
MTO.C-Q LT-TS -
1-MC-Ni t 7 -
PN -
1NI-0171 1562-3.1 J-07 1 AC ACT Check -
MTO C-O LT-TS -
1-MC-N117 -
P!V -
1Ni-0173A 1562-3.1 1-12 2 B ACT Gate EMJ ST-O - -
1 -MC-NI7 - -
- 1NI-0175 1562-3.1 l-08 1 AC ACT Check -
MTO.C-O LT-TS -
1 -MC-N118 PlV -
1 NI-0176 1562-3.1 H48 1 AC ACT Check -
MTO.C-O LT-TS -
1-MC-N118 -
PlV -
1 N1-0178B 1562-3.1 F-12 2 B ACT Gate EMO ST-O - -
1 -MC-NI7 - - -
1 N1-0180 1562-3.1 F-06 1 AC ACT Check -
MTO.C-O LT-TS -
1-MC-N118 -
PN -
1Ni-0181 1562-3.1 D-05 1 AC ACT Check -
MTO.C-O LT-TS -
1-MC-NI18 -
PN -
1 NI-0183B 1562-3.0 G-03 2 B ACT Gate EMO ST-O - -
MC-Ni9 - - -
1NI-0184B 1562-3.1 D-12 2 8 ACT Gate EMO ST-Q - -
1-MC-N110 - - -
1NI-0185A 1562-3.1 B-12 2 B ACT Gate EMO ST-O - -
1-MC-Nt10 - - -
11/1/93 NI - 4 of 5 m.________ m -. __-__._.m___ _ - _ _ _ _ _ __ m _ _ a_ _ _ _ _. - --m w w r v
Unit 1 - McGuire Nuclear Stofion Inservice Testing Program Fi1MY H.OW ASME VALVE ACT VALVE ACTUATOR TEST 1TST RELIEF JUSTIF OF TEST ,
VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TY1'E TYPE REQ MT 81 REQ %fT #2 REQST DETERRAL REMARKS ALTERNATIVES ~ REV SAFETY INJECTION (NI) 1NI-0332A 1562-3 0 L-14 2 0 ACT Gate EMO ST O - -
1-MC-N111 - - -
IN1-03330 1562-3.0 L-12 2 B ACT Gate EMO ST-O - -
1-MC-NI11 - - -
1NI-03348 15*2-3.0 L-11 2 B ACT Gate EMO ST-O - -
1-MC-N18 - - -
1N14347 1562-1.0 1-07 i C ACT Check -
MTO-O - -
1-MC-N112 - - -
1 NI-0348 1562-1.0 F-07 1 C ACT Check -
MTO-O - -
1-MC-Nt12 - - -
1NI-0349 1562-1.0 D-07 1 C ACT Check -
MTO-O - -
1-MC-N112 - - -
1NI-0354 1562-1.0 K-07 1 C ACT Check -
MTO-O - -
1-MC-N112 - - -
1NI-0430A 1562 2.0 E-04 2 B ACT Kerotest EMO ST-O - - - - - -
1NI-0431B 1562-2.0 J-04 2 B ACT Kerotest EMO ST-O - - - - - -
1NI-0436 1562-2.1 G-11 2 AC ACT Check -
MTC-O LT-RF -
1-MC-N123 - MT-RF* -
11/1/93 NI - 5 of 5
Unit 1 - McGuire Nuclear Station Inservice Testing Program FIDW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF 0F TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQMT *1 REQMT *2 RIQST DEITRRAL REMARKS ALTERNA11VES REV NUCLEAR SAMPLING (NM) 1NM4003AC 1572-1.0 K-03 2 A ACT Kerotest . EMO ST-O LT-RF - - - - -
1NM-0006AC 1572-1.0 J-03 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NM-00078 1572-1.0 K-06 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NM-0022AC 1572-1.0 J-12 2 A ACT Kerotest EMO OT-O LT-RF - - - - -
1NM4025AC 1572-1.0 K-12 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NM-0026B 1572-1.0 K-08 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NM-0069 1572-1.1 G-09 2 AC ACT Relief -
SP LT-RF - - -
700 PSIG -
1NM-00728 1572-1.1 l-06 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NM-0075B 1572-1.1 l-08 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
l 1NM-00788 1572-1.1 1-09 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1MM-00818 5572-1.1 1 11 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NM4082A 1572-1.1 E-09 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NM-0187A 1572-3.0 K-01 2 B ACT Kerotest EMO ST-O - - - - - -
IMM-0190A 1572-3.0 K-02 2 B ACT Kerotest EMO ST-O - - - - - -
1 NM-0191 B 1572-3.0 1-02 2 B ACT Kerotest EMO ST-O - - - - - -
l 1NM-01978 1572-3.0 K-05 2 B ACT Kerotest EMO ST-O - - - - - -
I NM-02008 1572-3.0 K-06 2 B ACT Kerotest EMO ST-O - - - - - -
11/1/93 NM - 1 of 2
Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RElfEF JUSTIF OF TEST VALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS Tii'E TYPE REQ h ". #1 REQhif #2 REQST DEFERRAL REMARKS ALTERNATIVES REV
~
NUCLEAR SAMPLING (NM) 1NM4201 A 1572-3.0 1-06 2 B ACT Kerotest EMO ST-O - - - - - -
1NM-0207A 1572-3.0 K-08 2 B ACT Kerotest EMO ST-O - - - - - -
INM-0210A 1572-3.0 K-09 2 B ACT Kerotest EMO ST-O - - - - - -
1NM42110 1572-3.0 1-09 2 B ACT Kerotest EMO ST-O - - - - - -
1NM-02170 .1572-3.0 K-11 2 B ACT Kerotest EMO ST-O - - - - - -
1NM-02200 1572-3 0 K-12 2 B ACT Kerotest EMO ST-O - - - - - -
1NM-0221 A 1572-3 0 1-12 2 B ACT Kerotest EMO ST-O - - - - - -
INM-0420 1572-1.0 J-03 2 AC ACT Check -
MTC-O LT-RF -
1-MC-NMI -
MT-RF* -
1 NM-0421 1572-1.0 J-12 2 AC ACT Check -
MTC-O LT-RF -
1-MC-NM1 -
MT-R F* -
11/1/93 NM - 2 of 2
Unit 1 - McGuire Nuclear Station Inservice Testing Program FIDW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF CF TEST DIAGRAM COOR CLASS CATEGORY PAS TWE
~
VALVE NUMBER TWE REQ MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV CONTAINMENT SPFIAY (NS) 1NS-0001B 1563-1.0 C-13 2 B ACT Gate EMO ST-O - - - - - -
1NS 0002 1563-1.0 0-12 2 C ACT Relief -
SP - - - -
220 PSIG -
1NS40030 1563-1.0 B-13 2 B ACT Gate EMO ST-O - - - - - -
1NS-0004 1563-1.0 B-12 2 C ACT Check -
MTO.C-O - -
1-MC-N S3 -
RF# -
1NS-00128 1563-1.0 C-04 2 B ACT Gate EMO ST-O - - - - - -
I' 1NS-0013 1563-1.0 0-02 2 C ACT Check -
MTO-O -
3,
' ' 1-MC-NS2 -
RF# -
1NS-00158 1563-1.0 D-04 2 B ACT Gate EMO ST-O - - - - - -
1NS-0016 1563-1.0 D-02 2 C ACT Check -
MTO-O -
1 -MC-NS2 -
RF# -
1NS-0018A 1563-1.0 G-13 2 B ACT Gate EMO ST-O - - - - - -
1NS-0019 1563-1.0 H-12 2 C ACT SP - - - -
220 PSIG -
1NS-0020A 1563-1.0 F-13 2 B ACT Gate EMO ST-O - - - - - -
eck '
1NS-0021 1563-1.0 F-12 2 C ACT MTO,C-O - -
1-MC-NS3 -
RF# -
1NS-0029A 1563-1.0 F-04 2 B ACT Gate EMO ST-O - - - - - -
1NS-0030 1563-1.0 F-02 2 C ACT Check -
MTO-O -
"" 1-MC-NS2 -
RF# -
1NS-0032A 1563-1.0 H-04 2 B ACT Gate EMO ST-O - - - - - -
1NS-0033 1563-1,0 H-02 2 C ACT Check -
MTO-O -
1-MC-NS2 -
RF# -
1NS-00388 1563-1.0 J-05 2 B ACT Gate .EMO ST-O - -
1-MC-NS1 - - -
11/1/93 NS - 1 of 2'-
Unit 1 - McGuire Nuclear Statiori inservice Testing Program FwW FLOW A%fE VALVE ACT VALVE ACTUATOR TEST TEST REllEF JUSTIT OF TEST VALVE NUMBER DIAGRAM COOK CLASS CATEGORY PAS TiFE DTE REQ MT 81 REQ'MT #2 REQST DEFEPJtAL REMARKS ALTERNATIVES REV CONTAINMENT SPRAY (NS) 1NS-0041 1563-1.0 J-03 2 C ACT Check MTO-O -
1-MC-NS2 -
RF# -
NS1 1NSELt3A 1563-1.0 K-05 2 B ACT Gate EMO ST-O - -
1-MC-NS1 - - -
l~
1NS-0046 1563-1.0 K-03 2 C ACT Check -
MTO4 -
fg ' 1-MC-NS2 -
RF# -
1NS-0140 1563-1.0 G-05 2 AC ACT Check -
M TO.C-O LT -
1-MC-NS4 - -
1NS4141 1563-1.0 C-05 2 AC ACT Check -
MTO.C-O LT -
1-MC-NS4 - -
1NS-5550B 1499-NS8 N/A 2 A ACT Solenod SOV ST-Q LT-RF - - - - -
INS-5551 A i499-NS8 N/A 2 A ACT Solenod SOV ST-O LT-RF - - - - -
11/1/93 NS - 2 of 2
Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TTST TEST REUEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR C1_ ASS CATEGORY PAS TYPE TYPE RFQ MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNAT1VES REV' CHEMICAL AND VOLUME CONTROL (NV) 1NV-0003 1554-1.2 K-09 2 C ACT Relief -
SP - - - -
600 PStG -
INV-0007B 1554-1.2 J-10 2 B ACT Globe EMO ST-O - -
1-MC-NV2 - - -
Spring 1NV-0020 1554-1 2 E-02 2 C ACT Check -
SP - - -
Loaded Ck 50 PSIG -
Vahre 1NV-0021 A 1554-1.2 E-03 1 D ACT Control AOV ST-O - -
1-MC-tN3 - - -
1NV-0029 1554-1.0 C-01 2 C ACT Check -
MTO-O - - - - - -
1NV-0031 1554-1.0 D-02 1 C ACT Check -
MTO-O - - - - - -
1NV-0035A 1554-1.2 K47 2 B ACT Gate AOV ST-O - - - - - -
1NV-0045 1554-1.0 C-06 2 C ACT Check -
MTO-O - - - - - -
1NV-0047 1554-1.0 D-08 1 C ACT Check -
MTO-O - - - - - -
1 NV-0061 1554-1,1 C-01 2 C ACT Check -
MTO-O - - - - - -
1NV-0063 1554-1.1 D-02 1 C ACT Check -
MTO-O - - - - - -
1NV-0077 1554-1.1 C-08 2 C ACT Check -
MTO-O - - - - - -
i 1NV4079 1554-1.1 D-08 1 C ACT Check -
MTO-O - - - - - -
1NV-0093 1554-1.1 K-12 2 C ACT Relief -
SP - - - -
150 PSIG -
1NV'-0094 AC 1554-1.1 J-13 2 B ACT Gate EMO ST-O - - 1-MC-NV1 - - -
I NV-00958 1554-1.1 H-13 2 B ACT Gate EMO ST-O - -
1-MC-NV1 - - -
1NV-0141 A 1554-2.0 B-08 2 B ACT Gate EMO ST-O - -
1-MC-NV4 - - -
l 11/1/93 'NV - 1 of 4
Unit 1 - McGuire Nuclear Station Inservice Testing Program FLOW TLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF IL5TIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATICORY PAS TiPE TYPE REQ'MT #1 REQ MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV CHEMICAL AND VOLUME CONTROL (NV) 1NV-0142B 1554-2.0 B-07 2 B ACT Gate EMO ST-O - -
1-MC-NV4 - - -
1NV-0143 1554-2.0 B-07 2 C ACT Check -
MTC-O - -
1-MC-NV15 - - -
1NV-0150B 1554-2.0 F-02 2 B ACT Kerotest EMO ST-O - -
1-MC-NV8 - - -
I NV-0151 A 1554-2.0 G-02 2 B ACT Kerotest EMO ST-O - -
1-MC-NV8 - - -
1 NV-0155 1554-2.0 146 2 C ACT Relief -
SP - - - -
150 PStG -
1NV-0156 1554-2.0 J49 2 C ACT Relief -
SP - - - -
255 PStG -
1NV-0164 1554-2.0 E-09 2 C ACT Check -
MTC-O - - - - - -
1NV-0170 1554-2.0 C-08 2 C ACT Relief -
SP - - - -
75 PStG -
1NV-0218 1554-3.0 J-05 2 C ACT Check -
MTC-O - - - - - -
1NV-0221 A 1554-3.1 H41 2 B ACT Gate EMO ST-O - -
1-MC-NV6 - - -
1NV-022.28 1554-3.1 tot 2 B ACT Gate EMO ST-Q - -
1-MC-NV6 - - -
1NV-0223 1554-3.1 1-02 2 C ACT Check -
MTO.C-O - -
1-MC-NV11 - - -
1NV-0225 1554-3.1 F-05 2 C ACT Check - MTO,C-O - -
1-MC-NV10 - - -
1 NV-0227 .1554-3 1 E-06 2 C ACT Check -
MTO,C-O - - - - - -
1 NV-0229 1554-3.1 1-12 2 C ACT Relief -
SP- - - - -
220 PSIG -
1NV-0231 1554-3.1 F-10 2 C ACT Check -
MTO.C-O - -
1-MC-NV10 - - -
1 NV-0233 1554-3.1 E-10 2 C ACT Check -
MTO.C-O - - - - - -
11/1/93 hV '- 2 of 4
Unit 1 - McGuire Nuclect Station Inservice Testing Progrom FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JU571F OF 1TST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TWE TiPE REQ'MT #1 REQMr #2 RFOST DEFERRAL REMARKS ALTERNATIVES REV CHEMICAL AND VOLUME CONTROL (NV) 1NV-0238 1554-3.1 G-04 2 S ACT Contro! -
FS-O - - - - - -
1NV-0244A 1554-3.0 K-08 2 B ACT Gate E.MO ST-O - -
1-MC-NV5 - - -
1NV-02458 1554-3 0 K-09 2 B ACT Gak EMO ST-O - -
1 -MC-NV5 - - -
1NV-0261 1554-3.1 J-03 2 C ACT Check -
MTC-O - -
1-MC-NV13 - - -
1NV-0263 1554-3.1 J-11 2 C ACT- Check -
MTC-O - -
1-MC-NV13 - - -
1NV-0264 1554-3.1 J-10 2 C ACT Check - MTO,C-O - -
1-MC-NV7 - - -
INV42658 1554-3.1 J-09 2 B ACT Globe EMO ST-O - -
1-MC-NV9 - - -
1NV-0383 1554-5.0 E-06 3 C ACT Check -
MTO,C-O - - - - - -
1NV-0386 1554-5.0 C-06 3 C ACT Check -
MTO.C-O - - - - - -
1 NV-0457A 1554-1.2 1-07 2 B ACT Ccotrol AOV ST-O - - - - - -
1NV-0458A 1554-1.2 J-07 2 B ACT Control AOV ST-O - - - - - -
I NV-0482 1554-2.0 D-07 2 C ACT Relief -
SP - - - -
150 PSIG -
1NV-0483 1554-2.0 D-11 3 C ACT Re!ief -
SP - - - -
150 PSIG -
1NV-0486 1554-3.1 J-09 2 C~ ACT Relief -
SP - - - -
150 PSIG -
1NV-0487 1554-3,1 J-10 2 C ACT Relief -
SP - - - -
150 PSIG -
1 NV-0488 1554-5.0 C-01 0 C ACT Relief -
SP - - - -
30 PSIG -
~ 1NV-0810 1554-1.0 D-03 1 C ACT Check -
MTO-O - - - - - -
11/1/93 NV - 3 of 4 e "4 Y
Unit 1 - McGuire Nuclect Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR ITST TEST REUEF JUSTIF OF TFST Y ALVE NUMBER DIAGRAM COOR CLASS CATTGORY PAS TYPE TY1'E REQMT #1 REQ'MT #2 RFQST DEFERRAL REMARAS ALTERNATBTS REV CHEMICAL AND VOLUME CONTROL (NV)
IPN-0811 1554-1.0 D-10 1 C ACT Check -
MTO-O - - - - - -
1NV-0812 1554-1.1 D-03 1 C ACT Check -
MTO-O - - - - - -
1NV-0813 1554-1.1 D-10 1 C ACT Check -
MTO-O - - - - - -
1NV-0849AC 1554-1.3 F-08 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1NV-1002 1554-1.3 F-10 2 AC ACT Check -
MTC-O LT-RF -
1-MC-NV14 -
RF -
INV-1007 1554-1.3 F-13 2 C ACT Check -
MTC-O - - - - - -
1NV-1008 1554-1.3 F-13 2 C ACT Check -
MTC-O - - - - - -
1NV-1009 1554-1.3 F-13 2 C ACT Check -
MTCO - - - - - -
1NV-1010 1554-1.3 F-13 2 C ACT Check -
MTC-O - - - - - -
1NV-1046 1554-3.0 H-12 2 C ACT Check -
MTC-O - -
1 MC-NV12 - - -
l 11/1/93 NV - 4 of 4
. ~ - . . _ . . . .
Unit I - McGuire Nuclect Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR IIST TEST RELIEF [LSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLA% CATTGORY PAS nPE TYPE REQ'MT 41 REQMT #2 REQ 57 DETERRAL REAtAKKS ALTERNATIVES REV FIRE PROTECTION (RF) 1RF-0821 A 1599-2.2 E-05 2 A PAS Diaphram AOV LT-RF - - - - -
1RF-0823 1599-2.2 E-07 2 AC ACT Check -
MTC-O LT-RF -
1-MC.R F I MT-R F* -
1 RF-0832A 1599-2.2 1-05 2 A PAS Diaphram AOV LT-RF - - -
U2CfV -
4 1 RF-0834 1599-2.2 1-08 2 AC ACT Check -
MTC-Q LT-R F -
2-MC-RF1 -
MT-RF*, U2CIV -
'1111/93 RF - 1 of 1
Unit 1 - McGuire Nuclect Station Inservice Testing Program FLOW FLOW ASME VALVF ACT VALVE ACTUATOR TEST TEST REUEF JUSTTF OF TEST VALVE NUMET R DIAGRAM COOR C1_ ASS CATEGORY PAS TWE TYTE REQMr el REQ %fT C REQST DEFERRAL REMARKS ALTFRNATIVES REV
- NUCLEAR SERVICE WATER (RN) 1 RN-0016A 1574-1.1 J43 3 B ACT Butedty EMO ST-O - - - - - -
1 RN-0018B 1574-1.1 E-02 3 B ACT Butterffy EMO ST-O - - - - - -
1RN4021 A 1574-1.1 J-02 3 B ACT Gate AOV ST-O - - - - - -
1 RN-0022A 1574-1.1 H-05 3 B ACT Gate AOV ST-O - - - - - -
1 RN-0025B 1574-1.1 C-04 3 B ACT Gate AOV ST-O - - - - - -
1 RN-0026B 1574-1.1 G-05 3 8 ACT Gate AOV ST-O - - - - - -
1RN4028 1574-1.1 J49 3 C ACT Check -
MTO-O - - - - - -
- 1RN-0030 1574 1.1 E-09 3 C ACT Check -
MTO-O - - - - - -
1 RN-0040A 1574-1.1 1-12 3 B ACT Butterffy EMO ST-O - - - - - -
1 RN-00418 1574-1.1 F-12 3 8 ACT Buttedfy EMO ST-O - - - -
U1 & U2 SIGNAL -
1RN4042A 1574-4.0 B-09 3 B ACT Buttedly EMO ST-O - -
1-MC-RN3 - - -
1RN-0043A 1574-1.1 F-12 3 B ACT Buttedly EMO ST-Q - - - -
U1 & U2 SIGNAL -
1 RN-00638 1574-1.0 I-02 3 B ACT Buttedly EMO ST-O - -
1-MO-RN4 - - -
1 RN-0064 A 1574-1.0 1-02 3 B ACT Buttedty EMO ST-O - -
1-MC-RN4 -
1RN-0068A 1574-1.1 K-12 3 B ACT Control AOV- ST-O - - - - - -
1RN-0069A 1574-2.0 K-03 3 B ACT Gate EMO ST-O - - - - - -
1 RN-0070A 1574-2.0 F-03 3 B ACT Butterffy EMO ST-O - - - - - -
11/1/93 RN - 1 of 5.
~
Unit 1 - McGuire Nuclect Station Inservice Testing Program FLOW Ftrnv ASME VALVE ACT VALVE ACTUATOR TEST TEST REllEF JISITE OF TEST V AI.VE NL'MBER DIACRAM COCR CLASS CATECORY PAS TITE T1PE REQ ~MT 81 REQ MT a2 REQST DEFERRAL REMARKS ALTERNATIVE 5 REV NUCLEAR SERVICE WATER (RN) 1RN-0073A 1574-2 0 1-03 3 B ACT B-utted'y EMO STO - - - - - -
1RN-0077 1574-2.0 1-03 3 C ACT Rehef -
SP - - - -
135 PSIG -
1RN-0086A 1574-2.0 D{9 3 B ACT Btrerf?y EMO ST-O - - - - - -
1 RN-0089A 1574-2.0 J-10 3 B ACT Buttedfy AOV ST-O - - - - - -
1RN-CD90 1574-2 0 D-12 3 C ACT Relief -
SP - - - -
VAC BREAKER -
1RN-0092 1574-2.0 1-12 3 C ACT Rekt -
SP - - - -
VAC BREAKER -
1RS0103A 1574-2.1 C-06 3 B ACT Diaphram AOV ST-O - - - - - -
1RM-0112A 1574-2.0 1-06 3 8 ACT Contrcl AOV ST-O - - - - - -
1RN4114A 1574-2.1 B-11 3 B ACT Diaphram AOV ST-O - - - - - -
1RN-0117A 1574-2 0 1-08 3 B ACT Contro! AOV ST-O - - - - - -
1RN4126A 1574-2 1 D-09 3 B ACT G!cbe AOV ST-O - - - - - -
1RN-0130A 1574-2 1 C-10 3 B ACT Globe AOV S T-O - - - - - -
1 RN-0134 A 1574-2.1 C-07 3 B ACT Butterffy EMO ~ ST-O - - - - - -
1RN4137A 1574-2.1 H-07 3 B ACT ButteWy EMO ST-O - - - - - -
1RN-0138 1574-2.1 H-05 3 C ACT. Rehet -
SP - - - -
135 PSIG -
1RN-0140A 1574-2.0 E-13 3 B ACT Gkte AOV ST-O - - - - - -
1RE0161B 1574-1.1 B-13 3 B ACT Control AOV ST-O - - - - - -
-11/1/93 RN .- 2 of 5
. . . _.a.._._
Unit 1 - McGuire Nuclect Station Inservice Testing Program FLO W FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF 1TSr VALVE NUMBER DIAGRAM COCR CLASS CATEGORY PAS TWE TzTE RFQ MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SERVICE WATER (RN) 1RN4162B 1574-3.0 K-03 3 B ACT Gate EMO ST-O - - - - - -
1RN4166A 1574-2.0 1 02 3 B ACT Diaphram AOV ST-O - - - - - -
1RN-0170B 1574-3.0 1-01 3 B ACT Diaphram AOV ST-O - - - - - -
1RN-0171 B 1574-3 0 E-03 3 8 ACT Butterfly EMO ST-O - - - - - -
1RN4174B 1574-3 0 i-03 3 B ACT Butterf'y EMO ST-O - - - - - -
1RN4178 1574-3.0 1-03 3 C ACT Relief -
SP - - - -
135 PSIG -
1RN-01878 1574-3.0 E-10 3 B ACT Butterfly EMO ST-O - - - - - -
1RN-01900 1574-3.0 J-10 3 B ACT Butterfly AOV ST-O - - - - - -
1RN4191 1574-3.0 E-12 3 C ACT Relief -
SP - - - -
VAC BREAKER -
1RN-0193 1574-3.0 H-12 3 C ACT Relief -
SP - - - -
VAC BREAKER -
1RN-0204B 1574-3.1 C-05 3 B ACT Diaphram AOV ST-O - - - - - -
1 RN-02138 1574-3.0 J-0G 3 B ACT Control AOV ST-Q - - - - - -
1 RN-0214 1574-3.0 D-13 3 C ACT Check -
MTO-O - -
1-MC-RN5 -
RF# -
1RN-02158 1574-3.1 B-11 3 B ACT Diaphram AOV ST-O - - - - - --
1RN-0218B 1574-3.0 148 3 B ACT Control AOV ST-O - - - - - -
1RN-0227B 1574-3.1 E-10 3 B ACT Globe AOV ST-O - - - - - -
1RN-0231B 1574-3.1 C-10 3 B ACT Globe AOV ST-O - - - - - -
11/1/93 RN - 3 or5 w +7--
Unit 1 - McGuire Nuclear Station Inservice Testing Prograrn FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REllEF JUSTTF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TITE TYPE REQA1T*1 REQ %fT #2 REQST DETERRAL REMARKS ALTERNATIVES REV NUCLEAR SERVICE WATER (RN) 1RN-02358 1574-3.1 E-07 3 B ACT Butterfy EMO ST-O - - - - - -
1RN{238B 1574-3.1 1-07 3 8 ACT Butterf!y EMO ST-O - - - - - -
1 RN-0240B 1574-3.0 E-13 3 B ACT G!cbe AOV ST-O - - - - - -
1RN-0252B 1574-4.0 E-02 2 A ACT Diaphram AOV ST-O LT-RF -
1-MC-RN t - - -
1 RN-0253A ' 1574-4.0 C-02 2 A ~ACT Diaphram EMO ST-O LT-RF -
1-MC-RN1 - - -
1R40276A 1574-4.0 J-02 2 A ACT Diaphram EMO ST-O LT-RF -
1-MC-RN2 - - -
1RN-02778 1574-4.0 1-02 2 A ACT Diaphram AOV ST-O LT RF -
1-MC-RN2 - - -
1 RN-0279B 1574-1.0 K-02 3 B ACT Butterfy EMO ST-O - - - - - -
' 1RN-0280 1574-1.0 K-03 3 C ACT Relief -
SP - - - -
VAC BREAKER -
1 RN-0293 1574-3.1 G-05 3 C ACT Relief -
SP - - - -
135 PSIG -
1RN-0294 1574-3.0 H-10 3 O ACT Relief -
1 RN-0295 1574-2.0 H-10 3 C ACT Relief -
SP - - - -
135 PSIG -
1RN-0296A 1574-1.0 1-01 3 r ACT Butterfly EMO ST-O - - -- - - -
1 RN-0297B 1574-1.0 G-02 3 B ACT Butterfly EMO ST-O - - - - - -
1RN-0299A 1574-1.0 K-02 3 B ACT Butterfy EMO ST-O - - - - - -
' 1RM-0442 1574-2.0 J-11 3 8 ACT Butterfly AOV ST-O - - - - - -
1RN-0445 _1574-2.0 J-11 3 B ACT Butterfly AOV ST-O - - - - - -
11/1/93 RN - 4 of 5
_2n -
Unit 1 - McGuire Nuclear Station Inservice Testing Progrom FLOW FLOW AS\fE VAL \T ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TWE TYPE REQ ~hrT 81 REQ ~MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV NUCLEAR SERVICE WATER (RN) 1 RM-0457 1574-3 0 J-11 3 B ACT But*erf!y AOV ST-O - - - - - -
1RM-0460 1574-3.0 J-11 3 B ACT Dutter'!y AOV ST-O - - - - - -
1 RN-0891 1574-2.0 J-03 3 C ACT Check -
MTO.C-O - -
1-MC-RN6 - - -
1 RN-0892 1574-2.0 J-03 3 C ACT Check - MTO,C-O - -
1-MC-RN6 - - -
1-MC-RR-C-07 3 C ACT Check MTC-Q RN1 1 RN-0994 1574-3.1 - . . . .
1-MC-RR-Check MTC-O RN1 1 RN-1006 1574-2.1 E-06 3 C ACT - . . . . .
l l
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'11/1/93 RN - 5 of 5
Unit 1 - McGuire Nuclect Station Inservice Testing Program 11_OW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JLSTIr OF TEST VALVE NUMBER DIAGRAM COOR C1 ASS CARGORY PAS TYPE TTT'E REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNATIVES REV CONTAINMENT VENTILATION COOLING WATER (RV) 1 RV-0032A 1604-3.0 K-10 2 A ACT Buttedfy EMO ST-Q LT-RF -
1-MC-RV1 - - -
1 RV-0033B 1604-3.0 K-12 2 A ACT Butterfly EMO ST-Q LT-RF - 1-MC-RV1 - - -
1 RV-0076A 1604-3.0 C-12 2 A ACT Butterffy EMO ST-O LT-RF -
1-MC-RV1 - - -
1 RV-0077B 1604-3.0 C-10 2 A ACT Butterf!y EMO ST-O LT-RF -
1-MC-RV1 - - -
1RV4079A 1604-34 K-07 2 A ACT Diaphram AOV ST-Q LT-RF - - - - -
1RV-0380B 1604-3.0 K-05 2 A ACT Diaphram AOV ST-O LT-RF - - - - -
1RV-0101 A 1604-3.0 C-05 2 A ACT Diaphram AOV ST-Q LT-RF - - - - -
1 RV-01028 1604-3.0 C-07 2 A ACT Diaph am AOV ST-O LT-RF - - - - -
1 RV-0445 1604-3.0 J-12 2 AC ACT Relief -
SP LT-RF - - -
135 PSIG -
1 RV-0446 1604-3.0 0-12 2 AC ACT Relief -
SP LT-RF - - -
135 PStG -
11/1/93 RV - 1 of 1
Unit 1 - McGuire Nuclect Station Inservice Testing Program FLOW fl.OW ASME VALVE ACT VALVE ACTUAIUR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLAc.S CATECORY PAS TYPE TYPE REQ'MT #1 REQMT #2 REQST DETERRAL REMARKS ALTERNATIVES REV MAIN STEAM SUPPLY TO AUXILIARY EQUIPMENT / TURBINE EXHAUST (SA) 1SA-0005 1593-1.2 F-04 2 C ACT Check -
MTO.C-O - -
1-MC-SA1 - RF# -
1 SAM 1593-1.2 F-04 2 C ACT Cryeck -
MTO.C-O - -
1-MC-SA1 -
RF# -
1SA-0048ABC 1593-1.2 E-04 2 B ACT Gate AOV ST-O - - - - - -
1SA-0049AB 1593-1.2 F-02 2 D ACT Gate AOV ST-O - - - - - -
11/1/93 SA '- 1 of 1
i i
Unit 1 - McGuire Nuclear Station Inservice Testing Program I
l FtJOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST
- VALVE Nt%fBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQ MT 81 REQMr #2 REQST DEFERRAL REMARKS ALTERNATIVES REV MAIN STEAM (SM)
ISM-0001 AB 1593-1.3 l-14 2 B ACT Globe AOV ST-O - -
1-MC-SM1 - - -
ISM-0003AB 1593-1.3 C-14 2- B ACT Globe AOV ST-O - -
1-MC-SM1 - - -
1SM-0005AB 1593-1.0 1-14 2 B ACT Globe AOV ST-O - -
1-MC-SM1 - - -
1SM-0007AB 1593-1.0 C-14 2 B ACT Globe AOV ST-O - -
1-MC-SM1 - - -
1SM-0009AB 1593-1.3 1-13 2 B ACT Control AOV ST-O - - - - - -
ISM-0010AB 1593-1.3 C-13 2 B ACT Control AOV ST-O - - - - - -
1SM-0011 AB 1593-1.0 l-13 2 B ACT Control AOV ST-O - - - - - -
1SM-0012AB 1593-1.0 C-13 2 B ACT Control AOV ST-O - - - - - -
11/1/93 SM - 1 of 1 -
.~ x Unit 1 - McGuire Nuclear Station Intervice Testing Progrom FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIFF JUSTIF OF 1TST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TWE DTE DFFERRAL REMARKS REQ MT #1 REQ'MT e2 REQ 5T ALTERNATIVES KEV MAIN STEAM VENT TO ATMOSPHERE (SV) 1SV-0001 AB 1593-1.3 L-05 2 B ACT Control AOV ST-O - - - - - -
1SV-0002 1593-1.3 K-06 2 C ACT Relief SP 1170 PStG -
1SV-0003 1593-1.3 K-07 2 C ACT Reitef -
SP - - - -
1190 PSIG -
ISV-0004 1593-1.3 K-09 2 C ACT Relief SP 1205 PS!G -
ISV-0005 1593-1.3 K-11 2 C ACT Relief -
SP - - - -
1220 PSIG -
1SV-0006 1593-1.3 K-12 2 C ACT Relief SP 1225 PSIG -
1SV-0007ABC 1593-1.3 G-05 2 B ACT Control AOV ST-O - - - - - -
1SV-0008 1593-1.3 E-06 2 C ACT Relief SP 1170 PSIG -
1SV-0009 1593-1.3 E-07 2 C ACT Relief -
SP - - - -
1190 PSIG -
1SV-0010 1593-1.3 E-09 2 C ACT Relief -
SP - - - -
1205 PSIG -
1SV-0011 1593-1.3 E-11 2 C ACT Rehef -
SP - - - -
1220 PSIG -
1SV-0012 1593-1.3 E-12 2 C ACT Relief -
SP - - - -
1225 PSIG -
ISV-0013AB 1593-1.0 L-04 2 B ACT Control AOV ST-O - - - - - -
ISV-0014 1593-1.0 K-05 2 C ACT Relief .
SP - - - -
1170 PSIG -
1SV-0015 1593-1.0 K-07 2 C ACT Relief -
SP - - - -
1190 PSIG -
1SV-0016 1593-1.0 K-09 2 C ACT Relief -
SP - - - -
1205 PSIG -
1SV-0017 1593-1.0 K-10 2 C ACT Relief -
SP - - - -
1220 PSIG -
11/1/93 SV - 1 of 2
Unit 1 - McGuire Nuclear Station Inservice Testing Program ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF 0F TEST FlfMV FLOW T)PE TTTE DEFERRAL REMARKS ALTERNATIVES REV VALVE NUMBER DIAGRAM CCCR CLASS CATEGORY PA5 REQ %fr #1 REQ 3fT 82 REQST MAIN STEAM VENT TO ATMOSPHERE (SV) 1SV-0018 1593-1.0 K-12 2 C ACT Relief -
SP - - - -
1225 PS!G -
1SV-0019AB 1593-1.0 G-04 2 B ACT Control ADV ST-O ^ - - - - -
ISV-0020 1s93-1.0 E-05 2 C ACT Relief -
SP - - - -
1170 PStG -
1SV-0021 1593-1.0 E47 2 C ACT Relief -
SP - - - -
1190 PSIG -
1SV-0022 1593-1 0 E49 2 C ACT Relief -
1SV-0023 1593-1.0 E-to 2 C ACT Relief -
GP - - - -
1220 PSIG -
1SV-0024 1593-1.0 E-12 2 C ACT Relief - SP - - - -
1225 PSIG -
L 11/1/93 sy . 2 of 2
Unit 1 - McGuire Nuclear Station Inservice Testing Program TEST TEST RELEF JL5TIF CF TEST FIDW FIOW ASME VAINE ACT VAIXE ACTUATOR DEFERRAL REMARKS ALTERNATIVES REV V ALVE NUMBER DIACRAM COOR CLASS CATEGORY PAS TWE TYPE REQ'MT #1 REQ'MT #1 REQST BREATHING AIRIVB) 1605-3.1 G-02 2 A ACT Kerotest EMO ST-O LT-RF - - -
1VB-00498 Check MTC-O LT-RF - 1-MC-VB1 - MT-RF* -
1VB-0050 1605-3.1 E-04 2 AC ACT -
11/1/93 VB - 1 of 1 -
(_.
Unit 1 - McGuire Nuclear Sh-on Inservic0 T9 sting Progroi.:
VALVE ACTUATOR ITST TEST REUEF JUSTIF OF TTST FLOW FLOW ASME VALVE ACT DEFERRAL REMARKS ALTERNATIVES REV VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TWE RFQ MT #1 REQMT #2 REQST CONTROL AREA VENTILATION (VC) 1VC-0001 A 1578-1 1-13 B ACT Butterfy EMO ST-O - - - -
AS 1VC M 2A 1578-1 1-13 B ACT Butterfty EMO ST-O - - - -
" ACT Butterfly EMO ST-O - - - -
IVC-0003B 1578-1 1-13 B - -
AS E 1VC4004B 1578-1 H-13 B ACT Butterfly EMO ST-O - - - -
SE 1VC-0009A 1578-1 E-13 B ACT Butterfly EMO ST-O - - - -
ASME 1VC-0010A 1578-1 D- I B ACT Butterffy EMO ST-O - - - -
AS E 1VC-0011 B 1578-1 E-13 ^ """ Y
~ ~ ~ ~ ~ ~ ~
SE tvCoO12B 1578-1 0-13 y,NE ^ "" ' ' ' ' ' ' '
111/1/93- VC - 1 of 1
Unit 1 - McGuire Nuclear Stofion Inservice Testing Program FIDW FIDW ASME VALVE ACF VALVE ACTUATOR TEST TEST RELJEF ,fUSTIF OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS DTE D PE REQ MT W1 REQ'MT *2 RFQST DEFERRAL REMARKS ALTERNATIVES REV ANNULUS VENTILATION (VE) 1VE-0005A 1564-1 G-04 2 A ACT Gate EMO ST-Q LT-RF - - - - -
IVE-000GB 1564-1 G-04 2 A ACT Gate EMO ST-O LT-RF - - - - -
IVE-0008A 1564-1 J-02 2 B ACT Gate EMO ST-O - - - - - -
IVE-G010A 1564-1 H-03 2 A ACT Diaphram EMO ST-O LT-RF - - - - -
1VE-0011 1564-1 H-03 2 A PAS Check LT-RF - - - - - -
11/1/93 VF .1 of 1
_s e.a._. .
Unit 1 - McGuirE Nuclear Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTTF OF TEST l VALVE NUMBER DIAGRAM COOR CLASS CATECORY PAS TYPE TYPE REQ MT *1 REQ MT #2 REQW DEFERRAL REMAPd5 ALTERNATIVES REV l
l DIESEL GENERATOR STARTING AIR (VG)
( IVG-0003 1609-4.0 J-12 3 C ACT Check -
MTO-O - - - - - -
l 1VG-0004 1609-4.0 E-12 3 C ACT Check -
MTO-O - - - - - -
IVG-0017 1609-4.0 J-06 3 C ACT Check -
MTO-O - -
1 -MC-VG1 - - -
1VG-0018 1609-4.0 I-06 3 C ACT Check -
MTO-O - -
1 -MC-VG1 - - -
1VG-0019 1609-4.0 E-06 3 C ACT Check -
MTOO - -
1-MC-VG1 - - -
l 1VG-0020 1609-4.0 D-06 3 C ACT Check -
MTO-O - -
1 -VC-VG1 - - -
1VG-0021 1609-4.0 L-13 # * ^ ~ ' ' -
I ' '
C SS G 1VG-0622 1609-4.0 l-13 SS G
^ * ~
b - ' ' ' '
1VG-0023 1609-4.0 G-13 A R -
S - - - -
275 PSIG -
C S G
( 1VG-0024 1609-4.0 C-13 C SS G A Rehef -
S - - - -
5 PSG -
IVG-0033 1609-4.0 L-07 3 C ACT Relief -
SP - - - -
250 PStG -
1VG-0034 1609-4.0 l-07 3 C ACT Relief -
SP - - - -
250 PSIG -
1VG-0035 1609-4.0 G-07 3 C ACT Relief SP 250 PSIG l
i 1VG-0036 1609-4.0 C47 3 C ACT Reiief -
SP - - - -
250 PSIG -
IVG-0061 1609-4.0 K-02 3 8 ACT Solenoid SOV ST-O - - - - - -
1VG-0062 1609-4.0 K-02 3 B .ACT Solenoid SOV ST-O - - - - - -
1VG-0063 16094.0 H-02 3 B ACT Solenoid SOV ST-O - - - - - -
l 11/1/93 VG - 1 of 3
Unit L- McGuire Nuclect Station Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF 0F TEST VALVE NUMBER DIAGRAM CCOR CLASS CATEGORY PAS TYPE TWE REQ'MT #1 REQ'MT #2 REQST DEFERRAL REMARKS ALTERNAll\TS REY DIESEL GENERATOR STARTING AIR (VG) 1VG-0064 1609 4 0 142 3 B ACT Solenoid SOV= ST-Q - - - - - -
1VG M S 1609-4.0 E-02 3 B ACT Solenoid SOV ST-O - - - - - -
1VG-0066 1609-4.0 F-02 3 B ACT Solenoid SOV ST-O - - - - - -
1VG4067 1609-4 0 C-02 3 B ACT Solenoid SOV ST-Q - - - - -
1VG20068 16094.0 C-02 3 B ACT Soienoid SOV ST-O - - - - -
IVG-0079 1609-4 0 I-11 3 C ACT Relief -
SP - - - -
139 PSIG -
1VG4080 1609-4.0 D-11 3 C ACT Relief -
i 1VG-0083 1609-4.0 J-10 3 C ACT Relief -
SP - - - -
139 PSIG -
IVG4084 10,,A0 D-10 3 C ACT Relief -
SP - - -
139 PSIG -
1VG-011 *> 1609-4.0 K-09 3 C ACT Check -
MTO-O - - - - - -
IVG-0116 16094.0 H-09 3 C ACT Check -
MTO-O - - - - - -
1VG-0117 1609-4.0 F-09 3 C ACT Check -
MTO-O - - - - - -
. IVG-0118 1609-4.0 C-09 3 C ACT Check -
MTO-O - - - - - --
IVG-5160 1499-VG3 N/A 3 D ACT Solenoid SOV ST-O -
yg 1VG-5161 1499 VG3 N/A 3 8 ACT Sotenoid SOV ST-O -
y 1VG-5162 1499-VG3 WA 3 B ACT Solenoid SOV ST-O - - - - -
I ~
1VG-5163 1499-VG3 N/A 3 B ACT Solenoid SOV ST-O - - - - -
'11/1/93 VG - 2 of 3
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i Unit 1 - McGuire Nuclear Station Inservice Testing Program Flinv FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REUEF JUSTIF OF TEST VALVE NL%tBER DIAGRAM CCUR CLASS CATIGORY l'AS TWE TWE REQ %fT #1 RFQttT #2 REQST DEFERRAL REhtARKS ALTERNATIVES REV DIESEL GENERATOR STARTING AIR (VG) 1VG-5170 1499-VG3 N/A 3 0 ACT Solenod SOV ST-O -
yg 1VG-5171 1499-VG3 N/A 3 D ACT Sciened FV ST-C -
y I
IvG-5172 1499-VG3 N/A 3 B ACT Solenod SOV ST-O -
y I "~
' 1VG-5173 1499-VG3 N/A 3 8 ACT Solenod SOV ST-O -
g 11/1/9? - VG - 3 of 3
Unit 1 - McGuire Nuclear Sfotion Inservice Testing Program FLOW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST RELIEF JUSTIF OF TEST VALVE NUMEER DIAGRAM COOR CLASS CATEGORY PAS TWE TWE REQ'MT #1 REQ 1fi #2 REQST DEFERRAL REMARKS ALTERNATTVES REV INSTRUMENT AIR (VI) 1VI-0040 1605-1.3 H-04 2 AC ACT Check -
MTC-O LT-RF -
1-MC-Vl3 - MT-RF* -
1VI-0113 1605-1.13 1-13 3 C ACT Relief -
SP - - - -
120 PSIG -
1VI-0114 1605-1.13 1-13 3 C ACT Relief -
IVI-0115 1605-1.13 J-02 3 C ACT Relief -
SP - - - -
120 PSIG -
T VI-0116 1605-1.13 J42 3 C ACT Relief -
SP - - - -
120 PSIG -
1VI-0117 1605-1.13 H-02 3 C ACT Renef -
SP - - - -
120 PSIG -
1VI-0118 1605-1.13 H42 3 C ACT Relief -
SP - - - -
120 PSIG -
1VI-0119 1605-1.13 J-09 3 C ACT Rehef -
SP - - - -
120 PSIG -
i 1VI-0120 1605-1.13 J-09 3 C ACT Relief -
SP - - - -
120 PSIG -
1VI-0124 1605-1.2 D-03 2 AC ACT Rehef -
MTC-O LT-RF -
1-MC-V12 - MT-R F* -
1V14129B 1605-1.17 J-06 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
t 1VI-01480 1605-1.14 C-04 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
1VI-0149 1605-1.2 1-03 2 AC ACT Check -
MTC-Q LT-RF -
1-MC-V12 -
MT-RF* -
1Vl41508 1605-1.14 B-03 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
i 1VI-01600 1605-1.17 C-06 2 A ACT Kerotest EMO ST-O LT-RF - - - - -
4 1VI-0161 1605-1.3 E 2 AC ACT Check -
MTC-O LT-RF -
1-MC-V!3 -
MT-RF* -
IVI-0362A 1605-12 142 2 A ACT Kerotest EMO ST-Q LT-RF - - - - -
11/1/93 VI - 1 of 2
. . _ . w ..
Unit 1 - McGuire Nuclear Station Inservice Testing Program FIDW FLOW ASME VALVE ACT VALVE ACTUATOR TEST TEST REllFF JLST1F OF TEST VALVE NUMBER DIAGRAM COOR CLASS CATEGORY PAS TYPE TYPE REQMT el REQ 3fT W2 REQ 5T DEFERRAL REMARKS ALTERNATIVES REV INSTRUMENT AIR (VI) ivi-o3ca leos-1.3 ta7 gS F C ACT Check -
MTO-O - -
1-MC-V11 - -
tvi-0372 160s-1.3 I-08 jS F C ACT Check -
MTC-Q - -
1-MC-V11 - - -
1vi-oa73 160s-1.3 Ca7 jS F C ACT Check -
MTO-Q - -
1-MC-V11 - - -
^ ~ ~ ~ ~ ~ ~
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11/1/93 VI - 2 of 2
1 INSERT TIIE FOLLOWING SECTION UNDER TAB:
II.6 i
?
P UNIT 1
I I
McGuire Unit 1 Specific Relief Reque_s_t ;
-1 Item Number: 1-MC-RR-NS1 ,
Valve:. INS-13, INS 16, INS-30, INS-33, INS-41, INS-46 Flow Diagram: MC-1563-1.0 j Code Category: C ASME Class: 2 Function: Open on flow from containment spray pumps.
Test Requirement: Verify proper volve movement once per three months as required by OMa-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 1-MC-NS2.) There are currently two separate subgroups within this popplation of volves. Group 1 contains the 2 volves associated with RHR discharge flow and group 2 contains the 4 valves associated with NS pump discharge flow. The present disassembly schedule inspects one valve from each group every refueling outage. During the four year history of disassembly, there have been no indications of wear, corrosion or degradation to the internal components.
This is attributed to the fact that this population of volves 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 valve population, disas-sembly of any valve requires scaffolding to be erected on top of the polar crane. Tools, equipment, parts. electrical power and airlines rnust 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~
1 OF 5
McGuire Unit 1 Specific Relief Requesj ltem Number: 1-MC-RR-NS1 (cont.)
This concern for personnel safety is also coupled with the -
fact that these check valves are cover hung, swing check ,
vahres.
This type of volve does not allow the technician to visually or physically verify exact seat realignment 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 regrouped 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 volves in group 2 and extend the disassembly rate for the two volves in group 1. After disassembly, a portial -
stroke test will be performed with air flow through the volves. The partial stroke test will not be performed each outage as scaffolding and polar crane use time is required for it also. This schedule of disassembly is to begin during i EOC9. All six volves will be disassembled and inspected. A partial stroke will be performed offer reassembly. The volves will not be disassembled again until EOCl3. !
l 11/1/93 SECTION 11.6 I 2OF5
]
.]
u I
l McGuire Unit 1 Specific Relief Requesj ltem Number: 1-MC-RR-RN1 Valve: 1 RN-994,1 RN-1006 INSTRUMENT DETAIL: MC-1574-2,1 ,
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- t 1988, Part 10, Section 4.3.2.1 and 4.3.2.2.
Basis for Relief: Testing these valves 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 row 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 valves would severely change the chemistry in the wet lay up state which would result in higher corrosion risk and major cost impact.
Test Alternative & Frequency: 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 i shutdowns.
11/1/93 SECTION 11.6 3OF5
McGuire Unit 1 Specific Relief Request Itern Number: 1-MC-RR-VG1 Valve: 1VGSV5160, IVGSVS161, IVGSV5162, IVGSV5163, IVGSV5170, IVGSVS171, IVGSV5172, IVGSV5173 INSTRUMENT DETAIL: MC-1499-VG3 Code Category: B ASME Class: 3 function: Supply control air to the Diesel Generator air /oll booster cylinder, the intercooler temperature controller, and the run/ shutdown cylinder.
Test Requirement: Stroke time test in accordance with OMo - 1988. Port 10, 4.2.
Basis for Relief: Direct observation of these volves is impossible. These volves are automatically opened when the diesel generator is started. Similar volves (the starting air solenoid volves) are tested with acoustic emission monitoring. Umitations on available acoustic equipment prevents its use on these volves. Additionally, these volves are scneduled to be modified in function during refueling outage lEOC9, Their new function will not be within the scope of the IST program.
To comply with the requirements of OMo - 1988. Port 10,4.2 would impose a cost burden of additional acoustic moni-toring equipment for the quarterly timing. Due to the short time before these volves are modified, no adverse trends could be developed from the quorierly testing.
Test Alternative & Frequency: Design Bases Document MCS-1609 VG-00-0001 paragraph 20.4.3.1 states that these volves shall b o tested by the diesel stort tests. These tests are performed monthly, and a failure of any one of these volves would result in a failure of -
the diesel start test. The monthly diesel stort 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 OMo -
1988, Port 10,4.2 requirements.
11/1/93 SECTIOll li,6 4OF5
, McGuire Unit 1 l l
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l Specific Relief Request I
l Item Number: 1-MC-RR-WN1 Valve: 1WN-3,1WN-5,1WN-7,1WN-11, lWN-13, lWN-15 Flow Diagram: MC-1609-7.0 Code Category: C ASME Class: 3 Function: Pump discharge check valves. All volves isolate parallel pump flow losses. lWN-3.1WN-5, lWN-11 and 1WN-13 open to allow and 1WN-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: These 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.
11/1/93 SECTION 11.6 5OF5
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INSERT TIIE FOLLOWING SECTION UNDER TAB:
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McGuire Unit 1 l
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ditstificatioltof Deferral :
l Item Number: 1-MC-CA1 Volvo: 1CA-37, ICA-41, ICA-45, ICA-49, ICA-53, ICA-57, ICA-61, ICA-65 Flow Diagram: MC-1592-1.0 Code Category: C ASME Class: 2 Function: Check flow from the steam generators to Auxiliary Feedwater. Open to allow Auxiliary Feedwater supply to the Steam Generators.
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 testing these valves would unnecessarily thermal shock the steam generators and feedwater piping.
Test Alternative & Frequency: Valves will be full stroke exercised at cold shutdown.
Closure will be verified quarterly.
11/1/93- SECTION II.7 1 OF 95
McGuire Unit 1 dystification of Deferral Iterr "-bor: 1-MC-CA2 Valve: ICA-165, ICA-166 Flow Diagram: MC-1592-1.1 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 De some 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 con 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 valves 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 offer two consecutive refueling outages. Failure of one valve to properly full stroke during a refueling outage will result in the remaining valves being disassembled and full stroked during that outage. Samplo disassemble will also be usod to verify proper closure of valves.
11/1/93 SECTION ll.7 2 OF 95
McGuire Unit 1 Justification of Deferral Item Number: 1-MC-CA3 Valve: ICA-8. ICA-10, ICA-12 Flow Diagram: MC-1592-1.1 Code Category: C ASME Class: 3 Function: Auxiliary Feedwater Pump Suction Check valver, 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 Deferrol: These valves 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, 1 CA-8 is disassembled every refueling outage, ICA-10 and ICA-12 every other refueling outage on a staggered basis.
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11/1/93 SECTION 11.7 ' I 3 OF 95
McGuire Unit 1 Justifica_ tion of Deferral [
item Number: 1-MC-CFl Valve: 1 CF-26AB, 1 CF-28AB, 1 CF-30AB. 1 CF-35AB Flow Diagram: MC-1591-1.1 Code Category: B ASME 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 Deferra!; Closure of these volves would isolate the Steam Generator feedwater which could result in a severe translent in the i
Steam Generator, resulting in a Unit trip.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 -
4 OF 95 i
McGuire Unit 1 Jusli.fication of Deferraj ltem Number: 1-MC-CF2 Valve: ICF-17AB. ICF-20AB.1CF-23AB, ICF-32AB -
Flow Diagram: MC-1591-1.1 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 those 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.
11/1/93 SECTION l1.7 ,
5 OF 95 w _ - _ _ _ _ - _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ - _ _ . _ _ _ _ _ . _ _ . . _ _ _ _ _ . _ _ _ _ _ _
McGuire Unit 1 d!Lslification of Deferral item Number: 1-MC-CF3 Valve: ICF-126B.1CF-1278, ICF-1288,1CF-129B Flow Diagram: MC-1591-1.1 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, 4.2.1.1.
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 causing vibrations in the preheater section of the steam generators.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
I 11/1/93 SECTION 11.7 6 OF 95
McGuire Unit 1 Lu.slification of Deferraj ltem Number: 1-MC-CF4 Valve: 1CF-104AB,1CF-105AB, ICF-106AB,1CF-107AB Flow Diagram: MC-1591-1.1 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 Part 10, 4.2.1.1.
Basis for Deferral: Closing this valve 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.
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McGuire Unit 1 i
JustiLication of Deferraj Item Number: 1-MC-CF5 ;
Valve: 1CF-152,1CF-154,1CF-156,1CF-158 l Flow Diagram: MC-1591-1.1 ,
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 volve movement once per three months as required by OMo-1988 Part 10,4.3.2.1.
Basis for Deferral: During normal operoflon, there is constant flow through these valves to keep the auxillary feedwater nozzles tempered. Testing these valves would require supplying the Steam Generators with cold water and thus thermally shocking these nozzles.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
11/1/93 SECTION 11.7 8 OF 95
McGuire Unit 1 Justification of Defenal Item Number: 1-MC-FW1 Valve: 1FW-27A Flow Diagram: MC-1571-1.0 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 Deferral: Closure of this valve during normal power operation would render all low pressure injection 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
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1 McGuire Unit 1 1 dmtification of Deferral item Number: 1-MC-FW2 Valve: 1FW-28 Flow Diagram: MC-1571-1.0 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.
Tost Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
11/1/93 SECTION 11.7 10 OF 95
t McGuire Unit 1 3Lustification of Deferral item Number: 1-MC-IA1 Valve: 11A 5260, llA-5270, llA-5280, llA-5290. IIA-5300, llA-5310.
IIA-5320, llA-5330, llA-5340, llA-5350, llA-5360,11A-5370, llA-5380,llA-5390 Flow Diagram: MC-1499-lAl Code Category: A,C ASME Class: 2&3 Function: llA-5260, 5270, 5280. 5290, 5300, 5310, 5320 and 5330 pre-vent loss of air from receiver tank on each personnel airlock door in the event oiloss of instrument air supply to door seals. These check valves form a pressure boundary for the ,
inflatable seals.
IIA-5340 and 5350 provide the inside containment Isolation barrier in the event of a break on the flexible hose connection on the air supply tc the door seals. The outside isolation valves are llA-5080 and 5160. These check valves are on the auxiliary bei! ding side of the airlocks.
IIA-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 fest once per 2 years in accordance with OMa-1988 Port 10, 4.2.2.2.
- 3) Leak test in accordance with Technical Specification 4.6.1.3.d.
Basis for Deferral: 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
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i McGuire Unit 1 Austification of Deferral Item Number: 1-MC-KC 1 Valve: 1 KC-424B.1 KC-425A Flow Diagram: MC-1573-3.1 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 alther 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 l 12 OF 95
McGuire Unit 1 dystification of Deferraj ltem Number: 1-MC-KC2 Valve: 1KC-338B Flow Diagram: MC-1573-3.1 Code Category: A ASME Class. 2 Function: Provide containment isolation for penetration M-327.
Test Requirement: Stroke time test in accordance with OMa-1988 Port 10, 4.2.1.1.
Basis for Deferral: Failure of this valve in the closed position during testing would inhibit flow to the reactor vessel support coolers. This action could result in damage to the reactor vessel.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION ll.7 -l 13 OF 95 I
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McGuire Unit 1 JustificatLon of Deferral liern Number: 1-MC-KC3 Valve: I KC-332B.1 KC-333A Flow Diagram: MC-1573-3.1 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.-
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McGuire Unit 1 dpstification_of Deterral ltom Number: 1-MC-KC4 Valve: 1 KC-320A Flow Diagram: MC-1573-3.1 ,
Code Category: A '
ASME Class: 2 ;
Function: Provide containment isolation for penetration M-376.
Test Requirement: Stroke , test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferrol: Failure of this valve 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. 1 Test Alternative & Frequency: Valve will be cycled and timed o .:;ng cold shutdown. :
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11/1/93 SECTION 11.7 15 0F 95 ;
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9 McGuire Unit 1 Justification of Deferraj item Number: 1-MC-KC5 Valve: 1 KC-280 Flow Diagram: MC-1573-3.1 Code Category: AC ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection of line between 1KC-332B and 1KC-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 volve cannot be practically tested during operation due to the design of the system.
Test Alts ,
.ve & 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 16 OF 95
McGuire Unit 1 dp_slif[Catiori of Deferra_l Itern Number: 1-MC-KC6 Valve: 1 KC-322 Flow Diagram: MC-1573-3.1 ,
Code Category: A,C ASME Class: 2 ;
Function: Provides containment isolation on penetration M-376.
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: 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.
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fdrGatire Unit 1 Lu_sjlfication of Deferraj ltem Number: 1-MC-KC7 Valve: 1 KC-279 Flow Diagram: MC-1573-3.1 Code Category: A,C ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection of line between 1KC-4248 and 1 KC-425A on penetration M-320.
Test Requirement: 1) Verify proper volve 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.
Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will b.) verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION 11.7
- 18 0F 95
McGuire Unit 1 Justification of Deferral item Number: 1-MC-KC8 Valve: 1 KC-340 Flow Diagram: MC-1573-3.1 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 . " 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 Alternat!ve & 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 19 OF'95-
McGuire Unit 1 Justification of Deferral item Number: 1-MC-KC9 Valve: 1 KC-47 Flow Diagram: MC-1573-4.0 Codo Category: A,C ASME Class: 2 Function: Provides containment isolation on penetration M-322.
Test Requ!rement: 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 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 20 OF 95
McGuire Unit 1 dualification of Doferral Item Number: 1-MC-NBl Valve: 1 NB-262 Flow Diagram: MC-1556-3.0 Code Category: A,C ASME Class: 2 Function: Provides containment isolation on penetration M-259.
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 21 OF 95
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McGuire Unit 1 i
duttificallo_a_Qf Deferraj ,
item Number: 1-MC-NC1 Valve: INC-32B, INC-34A. INC-36B Flow Diagram: MC-1553-2,0 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 for 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.
l 11/1/93 SECTlON 11.7 22 OF 95 ;
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McGuire Unit 1 dystification of DeferLaj i
Item Number: 1-MC-NC2 Valve: INC-272AC, INC-273AC, INC-274B, INC-275B Flow Diagram: MC-1553-2.1 Code Category: B ASME Class: 1 Function: Reactor vessel head vent, k Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, '
4.2.1.1.
Basis for Deferral: Opening these volves 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.
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11/1/93 SECTION 11.7 j 23 OF 95 i i
1 McGuire Unit 1 ;
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Justificatiqn of Deferral '
Item Number: 1-MC-NC3 ,
Valve: 1 NC-259,1NC-261 Flow Diagram: MC-1553-4.0 Code Category: A,C ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection of line between 1NC-1958 and 1NC-196A on penetration M-361, and line between INC- -
141 and INC-142 on penetration M-326 respectively, Test Requirement: 1) Verify proper valve 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 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 24 OF 95 -;
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McGuire Unit 1
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Item Number: 1-MC-ND1 ;
Valve: IND-1B, IND-2AC flow Diagram: MC-1561-1.0 Code Category: A A5ME Class: I function: Provides suction for Residual Heat Removal pumps during normal cooldown.
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 volves have on interlock which prevents their opening when the Reactor Coolant System pressure is greater than 385psig.
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.
P 11/1/93 SECTION 11.7 25 OF 95 P
McGuire Unit 1 Justification of Deferral r
item Number: 1-MC-ND2 Valve: IND-58A Flow Diagram: MC-1561-1.0 ,
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 Deferral: Opening this valve during operation would render both trains of Residual Heat Removalinoperable.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown, 11/1/93 SECTION 11.7 26 OF 95
McGuire Unit 1 Justification of Deferraj llem Number: MC-ND3 Valve: IND-158, IND-30A Flow Diagram: MC-1561-1.0 Codo 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 1 R
dustification of Deferral item Number: 1-MC-ND4 Valve: 1 ND-70 Flow Diagram: MC-1561-1.0 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 volve 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 IND-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. Valve will be partial stroked quarterly.
11/1/93 SECTION l1.7 28 OF 95
McGuire Unit 1 f
s!Msti[igallgR_QLQ_e.lcHaj ltem Number: 1-MC-NDS Valve: IND-71 flow Diagram: MC-1561-1.0 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 propor volve 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 INi-1368 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.
lest Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
11/1/93 SECTION 11.7 29 OF 95 i
r McGuire Unit 1 ,
slus_tification of Deintral i
Item Number: 1-MC-ND6 Valve: IND-8, IND-23 Flow Diagram: MC-1561-1.0 P
Code Ccrogory: C ASME Class: 2 Function: Residual Heat Removal pump discharge check valve.
Test Requirement: Verify proper valve 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 overcorne RCS pressure.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown. Valves will be partially stroked quarterly. The opposite train valves will be tested closed quarterly except when the opposite train of ND is in service.
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30 0F 95 l l
1 McGuire Unit 1 dqat!floalion ofyeferraj P
ltem Number: 1-MC-NF1 Valve: INF-229 Flow Diagram: MC-1558-4.0 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 ineasurement of local leak rate using air or nitrogen.
Basis for Deferral: The system design does not provide a means of verifying volve closure upon flow reversal.
Test Alternative & Frequency: 1) Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refu' ling outage frequency.
- 2) Leak Rate testing of the valve will be performed per Tech Spec 4.6.1.2.d.4).
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11/1/93 SECTION 11.7-31 OF 95 ;
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McGuire Unit 1 Justification of Deferral item Number: 1-MC-Nil Valve: INI-9A. INI-10B Flow Diagram: MC-1562-1.0 Code Category: B ASME dass: 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, 4.2.1.1.
Basis for Deferral: Opening either of these valves during operation would increase the charging flow into the Reactor Coolant System resulting in ar. increase of pressure and a rapid change in the primary system boron concentration. This could create a transient and possible unit shutdown.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
l 11/1/93 SECTION 11.7 32 OF 95
McGuire Unit 1 - :
l Justification of Deferral item Number: 1-MC-N12 Valve: 1 NI-100B Flow Diagram: MC-1562-3.0 Code Category: B ASME Class: 2 Function: Flowpaih from the Refueling Water Storage Tank the Safety injection Pump suction.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: Closing this volve during operation would render both trains of Safety injection 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 ll.7 33 OF 95
McGuire Unit 1 i
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Aust[fLcation of Deferral item Number: 1-MC-N13 Valve: 1NI-147A, INil ISB Flow Diagram: MC-1562-3.0 Code Category: B ASME Class: 2 Function: INI-147A provides flowpath for both trains of Safety injection recirculation line to the Refueling Water Storage Tank. INI-l158 provides flowpath for A train of Safety injection recirculation line to the Refueling Water Storage Tank.
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 injectico inoperable. INI-147A is open with 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 34 OF 95
McGuire Unit 1-Jys_tification t of Deferral item Number: 1-MC-N14 Valve: INl-121 A,1NI-1528 Flow Diagram: MC-1562-3.0 Code Category: B ASME Class: 2 Function: Isolates Safety injection flow to the hot legs.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: These van'es are closed with power removed above Mode 4 per Tech Spec 4.5.2.
Test Alternative & Frequency: Valve wi!! be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 35 OF 95
McGuire Unit 1 Justification of Deferral item Number: 1-MC-N15 Valve: :41-162A Flow Diagram: MC-1562-3.1 Code Category: B ASME 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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11/1/93 SECTION l1.7 36 OF 95
i McGuire Unit 1 slustification of Deferral item Number; l-MC-NI6 Valve: 1 N!-103A Flow Diagram: MC-1562-3.0 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 volve 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 11.7 .]
37 OF 95 ;
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i McGuire Unit 1 !
, -l slustificatLon of Deferral llem Number: 1-MC-NI7 Valve: 1NI-173A, INI-178B Flow Diagram: MC-1562-3.1 Code Category: B ASME Class: 2 Function: Provides flowpath for Residual Heat Removal to the cold legs.
Test Roquirement: 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 will be cycled and timed during cold shutdown.
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i 11/1/93 SECTION 11.7 38 OF 95 1
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McGuire Unit 1 Justification of Deferral item Number: 1-MC-NI8 Val, e: 1 NI-334B Flow Diagram: MC-1562-3.0 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 OMo-1988 Port 10, 4.2.1.1.
Basis for Deferrol: Closing this volve during power operation degrades both trains of Safety injection.
Test Alterr'otive & Frequency: Volve will be cycled and timed during cold shutdown 11/1/93 SECTION l1.7 39 OF 95
McGuire Unit 1 s.
Justification of Deferral Item Number: 1-MC-NI9 Valve: 1NI-183B Flow Diagram: MC-1562-3.0 ;
I Code Category: B ASME Class: 2 Function: Isolates Residual Heat Removal flow to the hot legs.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferral: This volve is closed 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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l 11/1/93 SECTION 11.7 40 OF 95 1
McGuire Unit 1 Justification of Deferral item Number: 1-MC--N110 Valve: IN1-1848,1NI-185A Flow Diagram: MC-1562-3.1 Code Category: B ASME Class: 2 Function: Provides flowpath from the Containment Sump to the Residual Heat Removal Pump and the Containment Sprov Pump suction.
Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
Basis for Deferrol: 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.
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11/1/93 SECTION 11.7 ,
41 OF 95 l
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McGuire Unit 1 ,
Justification of Deferral Item Number: 1-MC-N111 Valve: INI-332A INI-333B Flow Diagram: MC-1562-3.0 ;
Code Category: B ASME Class: 2 Function: Provides flowpath to Centrifugal Charc,ing 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 Defeiral: Opening these valves during power operations requires 1NI-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 1NI-334B degrades both trains of Safety injection.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION 11.7 42 OF 95
McGuire Unit 1 Jurtification of Deferral 1
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t Item Number: 1-MC-Nil 2 -l Valve: 1 NI-15, I Ni-17,1 NI-19,1 NI-21, 1 Ni-347,1 NI-348,1 NI-349,1 NI-354 ,
Flow Diagram: MC-1562-1.0 f Code Catecc- C ASMEt in: 1 Function: Opens to oilow flow to the cold legs from the Centrifugal Charging 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: Injecting flow through these valves from the Centrifugal Charging Pumps during power operatic is could result in unnecessary thermal shock to the injection nozzles.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
1 11/1/93 SECTION 11.7 43 0F 95 ,
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!- McGuire Unit 1 ;
Y Justification of Deferral item Number: 1-MC-Nil 3 Valve: 1 NI-12 Flow Diagram: MC-1562-1.0 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 Part 10,4.3.2.1.
Basis for Deferral: Injecting flow through this valve from the Centrifugal Charging ? umps 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.
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11/1/93 SECTION 11.7 44 OF 95
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McGuire Unit 1 Justification of Deferral i
Item Number: 1-MC-Nil 4 Valve: 1 N1-101 Flow Diagram: MC-1562-3.0 Code Category: C ASME Class: 2 Function: Opens to allow flow from the Refueling Water Storage Tank to the Safety injection Pumps. Closes to provide suction pressure boundary for these pumps from the Residuct Heat Removal Pump discharge.
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 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 1 J_ustification of Deferral f
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! tem Number: 1-MC-Nil 5 Valve: I Ni-116,1 NI-148 j Flow Diagram: MC-1562-3.0 Code Category: C ASME Class: 2 Function: Pump discharge check valve, opens to allow Safety !
Injection Flow. Closes to prevent noposite train flow losses. :
Test Requirement: Verify proper volve movement once per three months as required by OMa-1988 Port 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. i Test Alternative & Frequency: Valve will be full stroke exercised 'at cold shutdown. Valve will be verified closed quarterly. .
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11/1/93 SECTION 11.7 i 4G OF 95 -
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McGuire Unit 1 Justification of Deferral item Number: 1-MC-NI16 Valve: 1 NI-124, I N1-128,1 NI-156.1 NI-157, I N!-159,1 NI-160 Flow Diagram: MC-1562-3.0 Code Category: AC ASME Class: 1 Function: 1) Or ens 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 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.
Dosis 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 fest in accordance with Tech Spec 4.4.6.2.2.
11/1/93 SECTION IL7 47 OF 95
i Mc.duire Unit 1 Justification of Deferral item Number: 1-MC-Nil 7 Valve: INI-165,1NI-167,1NI-169,1NI-171 Flow Diagram: MC-1562-3.1 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 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 10,4.2.2.3.
Basis for Deferrol: Valves cannot be full or partial stroke tested during power operations since the Safety injection Pumps cannot overcorae 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 48 OF 95
McGuire Unit 1 Justification of Deferral item Number: 1-MC-Nil 8 Valve: 1 NI-175,1 NI-176.1 NI-180,1 NI-181 Flow Diagram: MC-1562-3.1 ;
Code Category: AC ASME Class: 1 Function: 1) Opens on flow from the Residual Heat Rernoval Pumps to the cold legs.
- 2) Reactor Coolant System pressure boundary.
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 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 ll.7 49 OF 95 t
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1 McGuire Unit 1 Justification of Deferral item Number: 1-MC-N119 Valve: 1 NI-125,1NI-126.1 NI-129,1 NI-134 Flow Diagram: MC-1562-3.0 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 por 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 i 50 0F 95
McGuire Unit 1 Justification of Deferr.a_l item Number: 1-MC-N120 Valve: 1Ni-136B Flow Diagram: MC-1562-3.0 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 valve during power operation renders both trains of Residual Heat Removalinoperable.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
11/1/93 SECTION 11.7-51 OF 95
McGuire Unit 1 Justification of Deferral item Number: 1-MC-N121 Valve: INi-48 Flow Diagram: MC-1562-2.0 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.
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- 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 52 OF 95
r McGuire Unit 1 L
Justification of Deferral s
item Number: 1-MC-N122 Valve: 1 NI-59,1 NI-70.1 Ni-81,1 NI-93 Flow Diagram: MC-1562-2.0. MC-1562-2.1 Code Category: AC ASME Class: 1 Function: Opens on flow from the NI cold leg occumulator to the Reactor Coolant System. Reactor Coolant Boundary valve.
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.
- 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, Valves will not be tested ,
during cold shutdown since disassembly is requ! red.
Disassembly would render one train of RHR looperable for an 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.
l Partial stroke will not be performed at cold shutdown since Tech Spec 4.4.6.2.2 requires leak testing after 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.
l 11/1/93 SECTION 11.7 l 53 0F 95 l
McGuire Unit 1.
J_ustification of Deferral item Number: 1-MC-N123 Valve: 1 NI-436 Flow Diagram: MC-1562-2.1 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 n ,
accordance with 10CFR50 Appendix J at refueling outage frequency.
11/1/93 SECTION 11.7 54 OF 95
McGuire Unit 1 diistification of Deferr_a_1 Item Number: 1-MC-NI24 Valve: INI-60. INI.71,1NI-82, INI-94 Flow Diagram: MC-1562-2.0, MC-1562-2.1 ;
i Code Category: A,C ,
ASME Class: 1 i Function: Opens on flow from the Ni cold leg accumulator to the Reactor Coolant System. Reactor Coolant Boundary valve. ;
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.
- 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 volves. 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 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 after 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.
11/1/93 SECTION 11.7 55 OF 95 i
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- McGuire Unit 1-slustification of Deferral Item Number: 1-MC-NM1 Valve: 1 NM-420,1 NM-421 Flow Diagram: MC-1572-1.0 Code Category: AC ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection for penetrations M-235 and M-309 respectively.
Test 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 56 OF 95
i McGuire Unit 1 Justification of Deferral item Number: 1-MC-NS1 Valve: INS-38B,1NS-43A Flow Diagram: MC-1563-1.0 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 operoflon '
renders both trains on Residual Heat Removal inoperable.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION l1.7 57 OF 95
McGuire Unit 1 Justification of Deferral item Number: 1-MC-NS2 Volve: INS-13, INS-16, INS-30, INS-33,1NS-41, INS-46 Flow Diagram: MC-1563-1.0 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 Port 10,4.3.2.1.
Basis for Deferrol: Fu!! stroke exercising of these check volves is not practical since there is no externalindication 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: These volves will be verified to fully cycle by sample disos-sembly at refueling outage frequencies.
N_ ole Relief is being requested on 1hese volves. Refer to relief re-quest 1-MC-RR-NS1, When relief is granted, this Justification Of Deferrol will be deleted.
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l 11/1/93 SECTION 11.7 i 58 OF 95 i l
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Justification of Deferral :
Item Number: 1-MC-NS3 Valve: I NS-4,1 NS-21 ,
Flow Diagram: MC-1563-1.0 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 volves 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-ure of one of valve to properly full stroke during a refueling outage will result in the remaining valve being disassem-bled and full stroked during that outage. Valves will be partial stroked quarterly.
11/1/93 SECTION l1.7 59 0F 95 ,
l McGuire Unit 1 ;
Justification of Deferral item Number: 1-MC-NS4 Vafve: I NS-140,1 NS-141 Flow Diagram: MC-1563-1.0 i
Code Category: A,C ASME Class: 2 .
Function: Must open to allow Containment Spray to the spray ring headers. Must close to prevent column separation of water in the header offer initial building spraydown and pump shutdown. During this time, the column of water in the vertical piping up to the spray rings could separate, creating a void in the system at sub-atmospheric pressure.
Upon pump restart, the collapse of this void would damage the piping system.
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.
j Basis for Deferral: Full stroke exercising of these check valves is not practical since there is no externalindication 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: Valves will be verified to full stroke open using sarnple disas-sembly every other refueling outage on a staggered basis. 7 Valves will be partial stroked quarterly. Valves will be leak ;
tested at refueling outages. Leak testing will also verify closure of these valves.
11/103 SECTION 11.7 60 OF 95
McGuire Unit 1
'l Justifipation of Deferraj +
llem Number: 1-MC-NV1 Valve: I NV-94AC, I NV-95B i Flow Diagram: MC-1554-1.1 Code Category: B ASME Class: 2 ,
1 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 nurnber 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 cold shutdown.
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11/1/93 SECTION 11.7 l 61 OF 95 1
McGuire Unit 1 Justification of Deferral t
Item Number: 1-MC-NV2 Valve: 1 NV-7B Flow Diagram: MC-1554-1,2 Code Category: B ASME Class: 2 Function: 1) Provides flowpath for normal letdown. '
- 2) Provides containment isolation for penetration M-347.
Test Requirement: Stroke ilme test in accordance with OMa-1988 Part 10, -
4.2.1.1.
Basis for Deferrol: Failure of this volve in a closed position could result in loss of ,
pressurizer level control and resu!t in unit shutdown.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown. .
l 11/1/93 SECTION 11.7 62 OF 95 l
1 McGuire Unit 1 i
Justification of Defertal item Number: 1-MC-NV3 Valve: INV-21 A Flow Diagram: MC-1554-1.2 Code Category: B ASME Class: 1 Function: Provides isolation for Pressurizer Auxiliary spray.
Test Requirement: Stroke time test in accordance with OMa-1988 Port 10, 4.2.1.1.
Basis for Deferral: Opening this valve during power operations could result in a reactor low pressure trip.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 63 OF 95 l
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McGuire Unit 1 Justification of Deferral item Number: 1-MC-NV4 Valve: INV-141 A, INV-142B Flow Diagram: MC-1554-2.0 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 these volves 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 causing damage to the seals.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown. ,
11/1/93 SECTION l1.7 j 64 0F 95 1 l
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McGuire Unit 1 Justificalion of Deferral item Number: 1-MC-NV5 {
- Valve: INV-244A INV-245B j Flow Diagram: MC-1554-3.0 Code Category: B ASME Class: 2 Function: Isolates charging to the Reactor Coolant System upon Safety injection.
l l Test Requirement: Stroke time test in accordance with OMa-1988 Part 10, 4.2.1.1.
l Basis for Deferral; 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.
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11/1/93 SECTION ll.7 65 OF 95
McGuire Unit 1 Justification of Deferral item Number: 1-MC-NV6 Valve: I NV-221 A, INV-222B Flow Diagram: MC-1554-3.1 Code Category: B ASME Class: 2 Function: Flowpath for Refueling Water Storage Tank to the suction of the Centrifugal Charging Pumps.
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 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 tirned during cold shutdown.
6 1 /1/93 SECTION 11.7 66 OF 95 1
McGuire Unit 1 I
Lustification of Deferral item Number: 1-MC-NV7 ,
Valve: INV-264 Flow Diagram: MC-1554-3.1 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 volve movement once per three months as required by OMa-1988 Part 10,4.3.2.1.
Basis for Deferrol: 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, iesiduci boric acid would be injected cousing a transient.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
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11/1/93 SECTION 11.7 67 OF 95
McGuire Unit 1 -
Justification of Deferral item Number: 1-MC-NV8
- Valve: INV-1508, l'NV-151 A Flow Diagram: MC-1554-2.0 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 Deferrol: If either valve were to fait closed while testing, the Charging Pump miniflow protection line is isolated possibly '
causing damage to the pump.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
s 11/1/93 SECTION ll.7 68 OF 95
McGuire Unit 1 Justification of Deferral Item Number: 1-MC-NV9 -
Valve: INV-265B Flow Diagram: MC-1554-3.1 ,
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 accordance with OMa-1988 Port 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 cousing '
a transient.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 .i 69 0F 95 :
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McGuire Unit 1 Justification of Deferral item Numbe.: 1-MC-NV10 Valve: INV-225. INV-231 Flow Diagram: MC-1554-3.1 Code Category: C ASME Class: 2 Function: Pump discharge check vo ve. 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 Deferrol: 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. Normal letdown 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 11.7 70 OF 95
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McGuire Unit 1 i
Justification of Deferral item Number: 1-MC-NV11 Valve: INV-223 Flow Diagram: MC-1554-3.1 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 purnps.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Port 10. 4.3.2.1.
Basis for Deferral: Testing this volve during power operations would require opening of either 1NV-221 A cr 1NV-222B. Opening these volves 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.
11/1/93 SECTION 11.7 71 OF 95
1 McGuire Unit 1 Justification of Deferral Item Number: 1-MC-NV12 Volve: INV-1046 r
Flow Diagram: MC-1554-3.0 .
Code Category: C ASME Class: 2 Function: Closes to provide pump suction pressure boundary for -
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 os required by OMo-1988 Port 10,4.3.2.1, .,
Basis for Deferrol: Testing this volve during power operation would result in the '
addition of highly borated water into the Reactor Coolant System cousing a transient.
Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown.
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11/1/93 SECTION 11.7 '
72 OF 95
l McGuire Unit 1 Justification of Deferraj ltem Number; l-MC-NV13 Vaive: I NV-261, I NV-263 Flow Diagram: MC-1554-3.1 Code Category: C ASME Class: 2 Function: These valves shall close to proviae pump suction pressure isolation for the Centrifugal Charging Pumps by preventing backflow to the Chemical Mixing Tank or the RMWST respective!y.
Test Requirement: Verify proper valve movement once per three months as required by OMa-1988 Part 10. 4.3.2.1, Basis for Deferral: Testing these valves requires INI-121 A to be opened. This vaive 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 4
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McGuire Unit 1 Justification of Deferral item Number: 1-MC-NV14 1 Valve: 1NV-1002 Flow Diagram: MC-1554-1.3 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 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 outogo ,
frequency. )
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t 11/1/93 SECTION 11.7 74 OF 95
McGuire Unit 1 Justification of Deferral item Number: 1-MC-NV15 Valve: INV-143 Flow Diagram: MC-1554-2.0 Code Category: C ASME Class: 2 Function: This volve, 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 Part 10,4.3.2.1, Basis for Deferral: This volve 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.
p 11/1/93 SECTION 11.7 75 OF 95
McGuire Unit 1
. Justification of Deferral item Number: 1-MC-RFl Valve: 1RF-823 Flow Diagram: MC-1599-2.2 :
Code Category: AC ASME Class: 2 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 Port 10,4.2.2.2.
Basis for Deferral: The system desipa does not provide a means of verifying valve closure upon flow reversal.
Test Alternative & Frequency: Valve will be verified c.osed by leak test performed in accordance with 10CFR50 Appendix J at refueling outags frequency.
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11/1/93 SECTION ll.7 -
76 0F 95
)'
l McGuire Unit 1 l
l Lustification of Defe_rlal Item Number: 1-MC-RN1 Valve: 1 RN-252B,1RN-253A l Flow Diagram: MC-1574-4.0 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 Part 10, 1 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 i
McGuire Unit 1 Justification of Deferral item Number: 1-MC-RN2 Valve: 1RN-276A.1RN-277B Flow Diagram: MC-1574-4.0 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 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 II.7 78 OF 95
q McGuire Unit 1 Justification of Deferra_t item Number: 1-MC-RN3 Valve: 1RN-42A Flow Diagram: MC-1574-4.0 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 valve during power operation isolates cooling water flow to the Steam Generator Blowdown Heat Exchanger. Failure in the closed position could result en damage to the heat exchanger.
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
e 11/1/93 SECTION 11.7 79 OF 95 l
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McGuire Unit 1 Justification of Deferral item Number: 1-MC-RN4 ,
Valve: 1 RN-63B,1 RN-64A .
Flow Diagram: MC-1574-1.0 Code Categor/: 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 Port 10, 4.2.1.1.
Basis for Deferral: Closing either of these valves 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, t
Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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I 11/1/93 SECTION 11.7 I 80 OF 95
McGuire Unit 1 Justification of Deferral Item Number: 1-MC-RN5 Volve: 1RN-214 Flow Diagram: MC-1574-3.0 Code Category: C ASME Class: 3 Function: Must or9n 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-3676. This volve is scheduled to be deleted from the system during lEOC9 refueling outage.
Until it is deleted, it will be included in the test program and tested as outlined below.
Test Requirement: Verify proper volve movement once per three months os required by OMo-1988 Port 10, 4.3.2.1.
Basis for Deferrol: Volves cannot be full stroked at any time without putting row water into the Spent Fuel Pool.
Test Alternative & Frequency: This volve will be disassembled and full stroked during each refueling outage untilit is deleted from the system. The volve will be partial stroked quarterly.
i 11/1/93 SECTION 11.7 81 OF 95
McGuire Unit 1 Justification of Deferral ltem Number 1-MC-RN6 r Valve: 1RN-891,1RN-892 Flow Diagram: MC-1574-2.0, MC-1574-3.0 Code Category: C ASME Class: 3 Function: Check flow from the RN return line (from the KD heat exchanger to the RN essential header) to maintain RN system integrity, during a seismic event. Open to allow Nuclear Service Water return 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 reverse 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 Alternative & 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, t
11/1/93 SECTION ll.7 82 OF 95
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McGuire Unit 1
-l Justification of Deferra_t Item Number: 1-MC-RV1 Valve: 1RV-32A 1RV-33B 1RV-76A 1RV-778 Flow Diagram: MC-1604-3.0 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 Units cousing an increase in lower containment temperature which could exceed Tech Spec limits.
1 Test Alternative & Frequency: Valve will be cycled and timed during cold shutdown.
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11/1/93 SECTION 11.7 83 0F 95 -
McGuire Unit 1 JustificatLon of Deferral b
Item Number: 1-MC-SA1 Valve: 1 SA-5,1 SA-6 Flow Diagram: MC-1593-1.2 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 1B and IC.
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 volve 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 valves 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 valve being disassembled and full stroked during that outage. Valves will be full stroked open quarterly, 11/1/93 SECTION ll.7 84 OF 95
McGuire Unit 1 Justification of Deferral Item Number: 1-MC-SM1 Valve: 1SM-1 AB,1SM-3AB, ISM-5AB, ISM-7AB Flow Diagram: MC-1593-1.0, MC-1593-1.3 ,
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 volves cannot be fully cycled closed during power operation since a unit shutdown would result.
Test Alternative & Frequency: These valves will be partially cycled closed while in Modes 1,2 and 3. These volves will be cycled and timed during l cold shutdown.
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11/1/93 SECTION 11.7 85 OF 95 1
McGuire Unit 1 Lustification of Deferral item Number: 1-MC VB1 Valve: IVB-50 Flow Diagram: MC-1605-3.1 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 ypars in accordance with OMo-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.
'P 11/1/93 SECTION 11.7 86 OF 95 J
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McGuire Unit 1 Justification of Deferral item Number: 1-MC-VG 1 Valve: 1VG-17, IVG-18, IVG-19, IVG-20 Row Diagram: MC-1609-4.0 Code Category: C ASME Class: 3 Function: Provides flowpath for Diesel Generator control air from individual starting air banks.
Test Requirement: Verify proper valve 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 siarted on a single bank of control air which is considered a degraded condition. This is not justified for quarterly starts.
This test is required to be done on an 18 month frequency as committed 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.
11/1/93 SECTION ll.7 87 OF 95
McGuire Unit 1 Justification of Deferral item Number: 1-MC-Vl1 Valve: I VI-368,1VI-372,1VI-373,1VI-374 Flow Diagram: MC-1605-1.3 Code Category: C ASME Class: ANSI B31.1.0 (1967)
Function: 1Vl-368 and IVI-373 must open to allow nitrogen to the PORV actuator.
1VI-372,1VI-374 must close to prevent loss of Nitrogen pres-sure if instrument air is lost.
Test Requirement: Verify pror 'er valve movement once per three months as required by OMo 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 # 1-MC-NC1 Test Alternative & Frequency: Valve will be full stroke exercised at cold shutdown. ;
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11/1/93 SECTION 11.7 !
88 OF 95 l l
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McGuire Unit 1 Justifica1 ion of Deferral item Number: 1-MC-V12 Valve: 1Vl-124, IVI-149 Flow Diagram: MC-1605-1,2 ,
Code Category: A.C ASME Class: 2 Furiction: Provides containment isolation on penetrations M-317 and M-386 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 des!gn 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
, 89 0F 95 l
i McGuire Unit 1 Justification of Deferral e
item Number: 1-MC-Vl3 Valve: IVI-40, IVI-161 Flow Diagram: MC-1605-1.3 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 Port 10,4.3.2.1.
- 2) Leak test once per 2 years in accordance with OMo-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 of refueling outage frequency.
11/1/93 SEC TION 11,7 90 OF 95
1 McGuire Unit 1 i
l J_ualification of Deferral l l
Item Number: 1-MC-VS1 '
1 Valve: 1VS-13 l
Flow Diagram: MC-1605-2.2 )
i Code Category: AC ASME Class: 2 Function: Provides containment isolation on penetration M-219.
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.
1 Basis for Deferral: The system design does not provide a means of verifying valve closure upon flow reverso!. !
Test Alternative & Frequency: Valve will be verified closed by leak test performed in i accordance with 10CFRSO Appendix J of refuelin0 outage frequency.
I 11/1/93 SECTION l1.7 91 OF 95 L .,
p- -.1 McGuire Unit 1 Justification of Deferral item Number: 1-MC-VX1 Valve: IVX-30 Flow Diagram: MC-1557-1 Code Category: A.C ASME Class: 2 Function: Provides containmen t isolation on penetration M-325.
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 l1.7 92 OF 95 m
1 McGuire Unit 1 Justification 91.Deferral i
i item Number: 1-MC-WL1 Valve: 1WL-24 Flow Diagram: MC-1565-1.1 Code Category: A,C ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection of line between 1WL-1B and 1WL-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.
Test Alternative & Frequency: Valve will be verified closed by leak test performed in accordance with 10CFR50 Appendix J at refueling outage frequency.
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11/1/93 SECTION ll.7 93 OF 95 w .)
b McGuire Unit 1 dug 1Jfication of Deferral Item Number: 1-MC-WL2 Valve: 1WL-385 Flow Diagram: MC-1565-7.0 Code Category: AC ASME Class: 2 Function: Provides containment isolation and thermal over pressurization protection of line between lWL-322B and 1WL-321 A on penetration M-221.
Test Requirement: 1) Verify proper valve movement once por 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.
T 11/1/93 SECTION l1.7 94 OF 95
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McGuire Unit 1 slustification of Deferral l
Item Number: 1-MC-YM1 Valve: 1YM-116 Flow Diagram: MC-1601-2.4 Code Category: AC ASME Class: 2
- unction: Provides containment isolation on penetration M-337.
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 10,4.2.2.2.
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 95 OF 95 W . + ___ __ _ _ _ ____ S