ML20092H646
| ML20092H646 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/24/1995 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20092H641 | List: |
| References | |
| PROC-950724, NUDOCS 9509210125 | |
| Download: ML20092H646 (229) | |
Text
{{#Wiki_filter:_____ ________ .- . ._ .. SENT SY: Xerox Telecopier 7021 i 6- 7-05 ; 3:51PM ; 2665* 205 802 03811# 1 n O E. l. HATCH NUCLEAR PLANT
- UNITS 1 AND 2 INSERVICE TESTING PROGRAM R ITS ITS ITS HNMS E DATE DESCRIPTION' PREP'O REV'D APPV APPV V By BY BY BY 0 07/24/95 Initial Issue IM $$4 dMI VI 0
HNP ISI/IST APPROYAL Written By: $NC-ITS Deeartment Reviewed By: @ M M M , Enge. Supv: MUz b , Yor. Enor: bb1$ in QA Review [ ld) h 7[s. N ANII Rev M k M O M d 8 PRB Review: k6 E965'79 [9 '1-96 AGM-PS App G G S d l45 AGN.P0 Appv:MJ d1/tr
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DISTRIBUTION LIST 4 l HOLDER MANUAL M ER E. C. Sorrell (GPC-Hatch) 1 D. G. Atwood (SNC-HNMS) 2
- A. D. Huber (GPC-Hatch) 3 B. C. Mosley (GPC-Hatch) 4 Resident NRC Inspector (Hatch) 5 l
ANI/ANII (c/o QC Supt. GPC-Hatch) 6 > ); W. M. (Rocky) Wright (SCS) 7 j ITS Shelf Copy 8
- D. M. Swann (SNC-ITS) 9 i
O 4 i f 1 5 O . 4 See naae #2 for addresses. Page 1 of 2
~ . - . . . . - . . .== - . - . .- . . . - - - - - - . _ . . . - . . - . - - . .
HAME/ ADDRESS E. C. Sorrell Doc. Cont. Supv. l ' Service Building ,- Plant Hatch t i D.'G. Atwood , . SNC-HMS ' ? Bin B052 ,. SNC, Bham. . A. D. Huber . Engineering Department Simulator Building
- . Plant Hatch
! 'B. C. Mosley-l Dperations Engineering - Service Building 4 Plant Hatch b ANI/ANII (D. R. Laakso)
- c/o Q. C. Dept. .
Service Building Plant Hatch M. H. Googe ' , Manager-Dutage Management
- - Simulator Building i Plant Hatch 4
i W. M. Wright Bin B241 SCS, Bham. , 1 ' D. M. Swann ITS Department , Bin B063 , i SNC, Bham. 4 i i i i 1 A 1 i .
- i i
4 i O\ Page 2 of 2 ;
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TABLE OF COMTENTS Section Pages 1.0 IST PROGRAM INTRODUCTION 1-1 thru l-3 2.0 ABBREVIATIONS 2-1 thru 2-3 3.0 INSERVICE TESTING OF PUMPS 3-1 4.0 PUMP TEST NOTES 4-1 5.0 HNP-1 PUMP TEST TABLES 5-1 thru 5-3 6.0 HNP-2 PUMP TEST TABLES 6-1 thru 6-3 7.0 PUMP RELIEF REQUESTS 7-1 thru 7-12 8.0 INSERVICE TESTING OF VALVES 8-1 thru 8-4 9.0 VALVE NOTES 9-1 thru 9-3 10.0 HNP-1 VALVE TABLES (Table 10) I thru 58 11.O HNP-2 VA'NE TABLES (Table 11) 1 thru 60 12.0 VALVE RELIEF REQUESTS 12-1 thru 12-11 l - 13.0 VALVE COLD SHUTDOWN JUSTIFICATIONS 13-1 thru 13-13 l 14.0 VALVE REFUELING OUTAGE JUSTIFICATIONS 14-1 thru 14-29 l 15.0 GENERAL RELIEF REQUESTS 15-1 thru 15-5 See Active Page List for complete listing of document contents. O Page 1 of 1 Rev. O
ACTIVE PAGE LIST i Paae No. Revision No.
- O , 1 2 1 i i
, IST Program l Introduction 1-1 x 1-2 x l-3 x 4 Abbreviations 2-1 x j 2-2 x i
- 2-3 x !
Pump Testing 3-1 x Pump Notes 4-1 x
- HNP-1 Pump
, , Table 5-1 x 5-2 x 5-3 x i HNP-2 Pump 4 Table 6-1 x 6-2 x 4 6-3 x l Pump Relief
- Requests 7-1 x 7-Za x ,
7-2b x 7-3 x
- 7-4 x
- 7-Sa x 7-5b x
- 7-6 x
- 7-7 x 7-8 x i- 7-9 x
, 7-10 x 7-Ila x 7-11b x
- 7-12 X 1.
Valve Testing 8-1 x 8-2 x 8-3 x 8-4 x , Valve Notes 9-1 x 9-2 x 9-3 x Page 1 of 5 t _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - ' -' ^^ ^ ~ ^ ^ ^ ~'
, i
- j. ~ Pace No. Revision No.
- - HNP-1. Valve A 1 2 1 1 1
'~ Table 10 1 x , 2 x
- 3 x 4 'x 5~ x 6 x
- 7 x 8 x 9 x i
10 x i 11 x ! 12 x 13 x 14 x , 15 x -1 ! 16 x i : 17 x j 18 x 19 x :
- 20. x 21' x i 22 x i 23 x !
i 24 x 25 x i g 26 x ! 27 x l ! 28 x
- 29 x 30 x 31 x 32 x j 33 x !
34 x i 35 x i 36 x l i 37 x '
- - 38 x
- . 39 x 40 x ,
4 41 x 42 x l 43 x ' i 44 x 44 x 46 x ! 2 47 x 48 x
' 49 x 50 x i
51- x 52 x 53 x 54 - x , Page 2 of 5 -
_ _ . . . _ _ . -_ . - _ _ _ _. . _ _ _ _ _ _ _ - . _ . _ _ _ _ ~ _ _ _ . . _ - . _ . . _ _ . . __ 4 4 Paae No. Revision No.
?
9 1 1 1 i i iO 55 x 56 x
; 57 x 1
58 x 4
; HNP-2 Valve ! Table 11 1 x
{ 2 x 3 x ll 4 x 5 x
- 6 x i 7 x j 8 x 9 x
- 10 x 11 x i
12 x ! 13 x
- 14 x i
15 x 16 x j 17 x 5 18 x 19 x 20 x ! 21 x 22 x ! 23 x ! 24 x
- 25 x 26 x 27 x l 28 x 29 x 30 x 31 x
- 32 x 33 x 34 x 35 x 36 x 37 x j 38 x i
39 x
- 40 x
'. 41 x 42 x 43 x 44 x
- 45 x 46 x 47 x
- 48 x Page 3 of 5
d i Paae No. Revision No. 2 1 1 1 i i 49 x 50 x 51 x i 52 x i 53 x
- 54 x 55 x 56 x 57 x 58 x l
59 x 60 x Valve Relief Requests 12-1 x 12-2 x 12-3 x
- 12-4 x 12-Sa x
- 12-5b x
; 12-6 x 12-7a x 4
12-7b x 12-8a x
- . 12-8b x 12-9 x 12-10a x
- 12-10b x l
12-Ila x 12-11b x t Valve Cold ! Shutdown
- Justifications 13-1 x 13-2 x 13-3 x 13-4 x 13-5 x 13-6 x i
13-7 x 13-8a x l 13-8b x 13-9 x { 13-10 x 13-11 x 13-12 x 13-13 x Valve Refueling Outage
;O Justifications 14-1 14-2 x
x i 14-3 x 14-4 x { Page 4 of 5 1
l 4 i Pace No. Revision No.
- 2 1 1 1 i i 14-5 x 14-6 x 14-7 x 14-8 x 14-9 x 14-10 x 14-11 x 4
14-12 x
- 14-13 x i 14-14 x 14-15a x 14-15b x 14-16 x 14-17 x
- 14-18 x l 14-19 x
! 14-20 x , 14-21 x 14-22 x 14-23 x 14-24 x 14-25 x , 14-26 x 14-27 x 14-28a x 14-28b x j 14-29 x i General Relief 1 Requests 15-1 x i 15-2 x ! 15-3' x i 15-4 x i 15-5 x i i i i i 4
- O Page 5 of 5
i 1.0 IST PROGRAM INTRODUCTION j 1.1 GENERAL r . This document describes the Inservice Testing (IST) Program for Edwin I. Hatch Nuclear Plant, Units 1 and 2. The below table identifies important dates j associated with the Inservice Testing Program. l MP-1 MP-2 i
- Construction Permit 09-30-69 12-27-72 1
Commercial Operation 12-31-75 09-05-79 l ! Ist 10-Year Interval 01-01-75 to 09-06-79 to l 12-31-85 12-31-85
- i 2nd 10-Year Interval 01-01-86 to 01-01-86 to j 12-31-95 12-31-95 i
! 3rd 10-Year Interval 01-01-96 to 01-01-96 to l 12-31-06 12-31-06
- HNP-2 was optionally updated at the same time as Unit I for the 2nd 10 l l -year interval in order to place both units on the same edition of the l Code.
i ! ' The edition of 10 CFR 50.55a current on January 1,1995, was used to determine the , applicable Code (s) for this program update. This 10 CFR 50.55a edition identified : ! the ASME Section XI Code,1989 Edition, as the applicable Code. The 1989 edition i of ASME XI references OM Part 6 and OM Part 10 as being applicable for pump (IWP) l t and valve (IWV) testing respectfully. 10 CFR 50.55a(b)(2)(viii) references the l OMa-1988 Addenda to 0M-1987 Edition of ANSI /ASME part 6 and 10 for pump and valve , j testing. ! ASME issued the OM Code-1990 Edition which included requirements for pump, valve, ! relief valve and dynamic restraint inservice testing, and subsequently issued the 5 OMb-1992 Addenda, the OMc-1994 Addenda, and the OM-1995 Code Edition. 1herefore the below listed Code versions are proposed for application through this IST Program update pursuant to 10 CFR 50.55a(a)(3)(i). t l ASME ON Code-1990 Edition (all except ISTD and Appendix 1) l ASME ON Code-1995 Edition. Appendix I { The ON Code-1990 Edition will be utilized for all pump and valve testing with the exception of relief valves, vacuum breaker valves, and rupture disks. The OM 3 Code-1995 Edition will be utilized for testing relief valves, vacuum breaker i valves, and rupture disks. l .
; This document includes inservice testing requirements for pumps and valves. The '
j inservice testing of dynamic restraints (snubbers) is not included in this program and at the present time is considered to be part of the Plant Technical Specification and/or Inservice Inspection Program. l NRC Generic Letter 89-04 and Supplement 1 (NRC NUREG-1482) were used, to the extent practical, for guidance in the development of this program. 1-1 Rev. 0
l 1.2 EFFECTIVE DATE - The IST Program, for the 3rd 10-year interval will become effective on January 1, 1996 and will be utilized through December 31, 2005 unless the federal regulations are revised otherwise. l 1.3 10.Qfi ; i This document is a description of the IST Program to.be implemented for Units 1
- and 2 at Plant Hatch. This document describes only the IST surveillance testing l applicable to pumps and valves included in the program.
, 1.4 COMPONENT UPGRADING
- Plant components have been reviewed to determine the appropriate classification j for inservice testing. Regulatory Guide 1.26 was used for guidance in determining component classifications.
1 i Note that the classification of pumps and valves as ASME Class 1, 2, or 3 , equivalent for this program does not imply that the components were designed in ; accordance with ASME requirements. Pump and valve design remains as stated in the 4 FSAR. 1.5 SUBSEQUENT PROGRAM REVISIONS ' It is anticipated that this Program will be reviewed again near the end of the 120 i month interval and compared to a later NRC approved edition and addenda of the ASME Code applicable for IST. At that time, the program will be modified, if i required, to comply to the extent practical with the later code edition. Any ! , additional relief requests for impractical requirements will be submitted in ; accordance with the applicable federal regulations. ' [ 1.6 RESPONSIBILITY I Georgia Power Company, as Owner, bears the overall responsibility for the , ! implementation of the inservice testing activities contained in this program per l
- ASME OM Code-1990, ISTA 1.4.
1.7 RECORDS
- Records and documentation of information and testing results, which provide the
- basis for evaluation and which facilitate comparison with results from previous
- and subsequent tests, will be maintained and available for the active life of the l component or system in accordance with ASME OM Code-1990, ISTA 3.
i 1.8 METHODS OF TESTING i' l The method of testing applicable to pumps and valves is listed adjacent to each j component identification in sections 2.0 and 3.0 of this program. The ASME OM i Code does not stipulate any specific training / certification requirements for ! personnel involved in pump and valve testing. At Plant Hatch, all pump and valve
- testing is performed by operations, maintenance or engineering department personnel who have been trained to perform specific testing tasks.
1.9 STANDARDS FOR TESTING EVALUATION i The acceptance criteria applicable for each pump and valve to be tested have been ) developed in accordance with the ASME OM Code requirements as modified by any 1-2 Rev. 0 i N
. _ . - . . .. . .... .. -. _-- . - ... - =.. . . .
\ { applicable relief requests. Acceptance criteria are not provided in the IST Program, but are provided in the IST Plans and the applicable surveillance testing procedures which are available for review at the plant site. !O i 1 i i 7 s !O a i i 1 i 1 1 J ^ 4 l 4 l 1
!O ;
A I- 1-3 Rev. 0 1
ABBREVIATIONS ABBREVIATION DEFINITION A Active A OM Code Category "A" Valve (See OM Code) Accum Accumulator Act Actuation ADS Automatic Depressurization System AP Category A, Passive Valve (See OM Code) A0 Air Operated A0V Air Operated Valve App-J 10 CFR 50, Appendix J Analy Analysis BFV Butterfly Valve Bldg Building Brker Breaker C Closed Cat Category CC Code Classification Chan Chamber CIV Containment Isolation Valve Cond Condensate Cnet Containment Cont Control Coord Coordinate CS Cold Shutdown CS Core Spray CSJ Cold Shutdown Justification O CV AP Check Valve Differential Pressure Depress Depressurization DG Diesel Generator DIME Disassemble, Inspect and Mechanical Exercise Disc Discharge Disch Discharge
- DNO During Normal Operation Drn Drain l DRW
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Dirty Rad Waste , DW Drywell l EFCV Excess Flow Check Valve i Equip Equipment , Exh Exhaust l ~ Exp1 Explosive FW Feedwater F1r Floor ' Gen Generator
- GlV Globe Valve i
GV Gate Valve H2 Hydrogen HCU Hydraulic Control Unit HOV Hydraulic Operated Valve HPCI High Pressure Coolant Injection ,p HVAC Heating, Ventilating and Air Conditioning Hx Heat Exchanger l (j ID . Identification Inbrd Inboard i 2-1 Rev. O
ABBREVIATION DEFINITION Inj Injection fs Injec Injection U Inst Instrument ISO Isolation LC Locked Closed LPCI Low Pressure Coolant Injection LTV Leak Tight Valve (Other than OM Code or Appendix J) Man Manual Maint Maintenance . MCR Main Control Room Min Minimum Mon Monitoring MOV Motor Operated Valve MSIV Main Steam Isolation Valve MSRV Main Steam Relief Valve Mtr Motor N Pump Speed NA Not Applicable
.N2 Nitrogen NIT Non-intrusive Testing NP Normal Position 0 Open 0/C Open/ Closed 02 Oxygen Outbrd Outboard P Passive Pd Discharge Pressure Pi Inlet Pressure O- Po Outlet Pressure Piping and Instrumentation Diagram P&ID PASS Post Accident Sampling System PCV Pressure Control Valve PEQ Partial Exercise Quarterly PIV Pressure Isolation Valve Press Pressure Prod Products l Purif Purification l Q Flowrate Quarterly Qtr
. RBCCW Reactor Building Closed Cooling Water , RCIC Reactor Core Isolation Cooling '. RCS Reactor Coolant System
- RD Rupture Disk
! Recirc Recirculation Recom Recombiner Redun Redundant Reqd Required RF Refueling Floor RHR Residual Heat Removal RHRSW Residual Heat Removal Service Water t Rm Room. : R0 Refueling Outage ' ! ROJ Refueling Outage Justification ; l RPV Reactor Pressure Vessel RR Relief Request RW Radwaste ! RWCU Reactor Water Clean Up 2-2 Rev. 0
- ABBREVIATION DEFINITION RV Relief Valve
, Rx Reactor O SDC SDV Ser Shutdown Cooling Scram Discharge Volume Service SGTS Standby Gas Treatment System SLC Standby Liquid Control SOV Solenoid Operated Valve SP Safety Position SPC Suppression Pool Cooling ST Stroke Time Stg Storage Stm Steam Stor Storage i Suc Suction Suct Suction Supp Suppression SW Service Water Sys System
- Test Testable 1 TIP Tranversing Incore Probe
- Turb Turbine V Vibration Vac Vacuum VB Vacuum Breaker j Vlv Valve Wkly Weekly Wtr Water i
l t i d l l I i O 2-3 Rev. 0
3.0 INSERVICE TESTING OF PUMPS l ! 3.1 GENERAL This IST program was developed to comply with the requirements of 10 CFR 50.55a(f) which delineate the testing requirements for ASME Class 1, 2, and 3 pumps. The ! Code of record required by 10 CFR 50.55a for pump IST is the ASME/ ANSI part 6 of l the OMa-1988 Addenda to the OM 1987 Standard. However, Georgia Power Company (GPC) previously obtained approval from the NRC to use the ASME OM Code 1990 Edition for pump IST at Edwin I. Hatch Nuclear Plant. The supplemental guidance of NRC Generic Letter 89-04 and Supplement 1 (NUREG-1482) have been applied to the ! extent practicable. For pumps which are within the scope of IST, as stipulated i in 10 CFR 50.55a, where specific Code requirements cannot be met, relief has been requested from the specific Code requirements. l 3.2 SCOPE Safety-related ASME Class 1, 2, and 3 pumps meeting the criteria of the ASME OM . Code and falling under the Regulatory Position of Regulatory Guide 1.26 are j included within the scope of this program. Special scope features of the Hatch IST Program are discussed below. i
- It is recognized that 10 CFR 50 Appendix A, GDC-1, and Appendix B, Criterion XI l intend that all pumps necessary for safe operation of the plant be tested to i demonstrate that they will perform satisfactorily in service. This testing is to
- be performed to a level commensurate with the function of the pump. This testing is generally performed per the requirements of the plant Technical Specifications 4
or other requirements. In cases where Code requirements are impractical for i i certain pumps, or an alternate testing method is considered an improvement over , i O v OM Code requirements, a relief request has been developed. Pump relief requests are located under a separate tab. i No credit is taken in any of the accident analyses for the RCIC system. i Therefore, the RCIC pumps have been included in this Program to provide a readily l accessible, documented method of testing. This testing will be performed in a j manner similar to the OM Code testing and should adequately detect degradation. Subsequently, relief requests are not considered to be required. l The Diesel Generator Fuel Oil Transfer Pumps are not ASME classed components and i are not included within the scope of Regulatory Guide 1.26. These pumps have been i included in this Program to provide a readily accessible, documented method of l testing. This testing will be performed in a method similar to that found in the l- OM Code, and should adequately detect degradation in these particular pumps. ! The Spent Fuel Pool Cooling Pumps have not been included in this Program because
- they are not safety-related. Credit is taken in the FSAR for Plant Service Water as the safety-grade makeup source to the spent fuel pool and the RHR system is used as the backup cooling source.
j The Core Spray Jockey Pumps have not been included in this Program because they i are not considered to be safety-related.
$ l l
O .
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3-1 Rev. O I
! PUMP TEST NOTES i 1. The flow rate for this pump is calculated by measuring the change in the test j tank level and pump run time.
- 2. Diffe'rential pressure for this pump is calculated by measuring the discharge
- pressure and the river level and computing the required pressure. The test plan and the surveillance test procedure include the equation used to i calculate the differential pressure. This measurement method is acceptable i per ISTB 4.6.5 and NUREG-1482, paragraph 5.5.3.
1 l
- 3. As discussed in the " SCOPE" section of this program document (para. 3.2), the
! RCIC system is not required to be included in the IST Program. However, it ! is desirable to maintain the system in a documented testing program. Testing
- will be performed in a manner as close as practical to OM Code test l requirements.
- 4. 1(2)E51-PI-R002 exceed the range limit of 3 times the reference value.
However, the gages are calibrated to il% full scale accuracy which results in i the final variance being within the maximum allowable tolerance of the OM Code 1 (i.e.1.4 psig versus 1 psig for Unit I and 1.8 psig versus 1 psig for Unit ] 2). ! 5. 1(2)E51-FI-R612 exceed the maximum Code allowable total loop accuracy, . however, the indicator used has a full scale range less than the Code i allowable. The maximum variance allowed by the Code is 24 gpm (.02 X 1200)
- whereas the actual maximum variance is 13 gpa (.0212 X 600). Therefore, the
- actual accuracy of the instrument loop is better than that required by the j Code. -
O e. This sxstem does et feii witai the scope reauireme ts f the asac oa code as implemented by 10 CFR 50.55a (i.e. not ASME Class 1, 2 or 3), is not i covered by the Regulatory Position of Regulatory Guide 1.26, and was not ! designed to facilitate performance of OM Code type pump testing. Therefore, j it is only included in this program document to provide a readily accessible, ! controlled mechanism for testing. As discussed in the Scope Section of this l document, testing will be performed in a manner similar to that of the OM ! Code, and such testing should adequately detect degradation. l 7. Since instrumentation was not provided to measure flow (or pressure), a i portable ultrasonic type instrument will be used to measure flow. The piping j basically forms a fixed resistance system; therefore, measurement of Po and Pi is not deemed necessary. If the flowrate decreases below a procedural
- specified value, the pump will be declared inoperable. This value will be determined taking into account the repeatability of this type of flow
- measuring device and the specific design parameters of the pump.
l 1 8. The Diesel Generator Fuel Oil Transfer Pumps are located inside the storage tanks with the motor and pump coupling area located above the tank. This arrangement provides inherent deficiencies for detection of degradation through vibration testing. Therefore, best effort motor vibration l measurements will be taken quarterly to assist in the detection of degradation j in the pumps. 4 O l 4-1 Rev. 0 l
O O O 15r-1 PINF TESTIM TABLES P&ID/ Code Test Test Pums ID Description Coord Class Parameters Freeuency RR/ Remarks IC41-C001A-- Standby Liquid Control X-16061 2 Pd Qtr RR-P-Il (Positive Displacement) E-6 - IC41-C0018 H-16061 Q Qtr Note 1 F-6 RR-P-11 V Qtr RR-P-1 RR-P-11 N M M AP M M
.IEll-C002A Residual Heat Removal H-16330 2 Pd M RR-P-2 (Centrifugal) H-9 IE11-C0028 H-16329 Q Qtr RR-P-3~
H-3 RR-P-ll IE11-C002C H-16330 V -Qtr RR-P-ll H-11 1 Ell-C002D H-16329 N M M H-1 AP Qtr RR-P-2 RR-P-11 IEll-C001A RHR Service Water D-Il004 3 Pd M M (Vertical Line Shaft) A-7 IE11-C0018 D-11004 Q Qtr RR-P-11 D-7 IEll-C001C D-11064 V Qtr- RR-P-4 C-7 RR-P-Il IE11-C001D D-11004 N M MA
. E-7 AP Qtr Note 2 RR-P-ll 5-1 Rev. o
O O O M P-1 PUNP TESTING TABLES P&lD code Test Test Pues ID Description Coord Class Parameter Freeuency RR/ Remarks IE21-C001A Core Spray H-16331 2 Pd NA NA (Centrifugal) H-9 - IE21-C001B H-16331 Q Qtr RR-P-ll H-10 V Qtr RR-P-Il N NA NA
& Qtr RR-P-5 i RR-P-Il IE41-C001 High Pressure Coolant H-16333 2 Pd NA NA Injection E-8 (Centrifugal) Q Qtr RR-P-7 RR-P-ll V Qtr RR-P-10 RR-P-11 N Qtr RR-P-ll
& Qtr RR-P-6 RR-P-11 IE51-C001 Reactor Core Isolation H-16335 2 Pd NA NA (Note 3) Cooling D-6 (Centrifugal) Q Qtr Note 5 V Qtr NA N Qtr NA
& Qtr Note 4 5-2 Rev. O
O O O HNP-1 PUNP TESTING TABLES P&lD/ Code Test Test Puse ID Description Coord Class Parameter Freeuency RRMtemarks IP41-C001A Plant Service Water D-11001 3 Pd NA NA (Vertical Line Shaft) F-2 IP41-C0018 D-Il001 Q Qtr RR-P-Il F-5 IP41-C001C D-Il001 Y Qtr RR-P-4 F-3 RR-P-Il IP41-C001D D-Il001 N MA NA F-6 AP Qtr Note 2 RR-P-11 1Y52-C001A Diesel Fuel 011 H-11037 NA Pd MA NA Transfer NA 1Y52-C0016 (Vertical line shaft) H-11037 Q Qtr Note 7 (Note 6) NA lY52-C001C H-11037 Y Qtr Note 8 NA 1Y52-C101A H-11037 N NA NA NA lY52-C101B H-11037 AP Qtr Note 7 NA lY52-C101C H-11037 NA 5-3 Rev. 0
l O O . O MP-2 PUNP TESTIM TABLES l P&lD/ Code Test Test j Pup ID Description Coord Class Parameter Freeuenc.Y RR/ Remarks 2C41-C001A Standby Liquid Control H-26009 2 Pd Qtr RR-P-ll (Positive Displacement) F-5 2C41-C001B H-26009 Q Qtr Note 1 G-5 RR-P-ll V Qtr RR-P-1 RR-P-Il l N M M l l AP NA NA I 2 Ell-0002A Residual Heat Removal H-26015 2 Pd NA RR-P-2 l (Vertical Line Shaft) H-8 2 Ell-C0028 H-26014 Q Qtr RR-P-3 H-3 RR-P-Il 2E11-C002C H-26015 V Qtr RR-P-ll H-9 2 Ell-C0020 H-26014 N NA NA H-2 AP Qtr RR-P-2 RR-P-Il 2 Ell-C001A RHR Service Water H-21039 3 Pd NA NA (Vertical Line Shaft) B-4 2 Ell-0001B H-21039 Q Qtr RR-P-11 F-4 l 2 Ell-C001C H-21039 Y Qtr RR-P-4 D-3 RR-P-11
- 2E11-C001D H-21039 N NA NA l
G-3 ( AP Qtr Note 2 . RR-P-Il 6-1 Rev. 0 '
O O O HNP-2 PUNP TESTING TABLES P&lD/ Code Test Test Pwqs ID Description Coord Class Parameter Freeuency RR/ Remarks 2E21-C001A Core Spray H-26018 2 Pd NA NA f, Vertical Line Shaft) F-7 2E21-C001B H-26018 Q Qtr RR-P-Il F-9 Y Qtr RR-P-Il N NA NA
& Qtr RR-P-5 RR-P-Il 2E41-C001 High Pressure Coolant H-26021 2 Pd NA NA Injection D-7 (Centrifugal) Q Qtr RR-P-7 RR-P-Il V Qtr RR-P-10 RR-P-ll N Qtr RR-P-ll
& Qtr RR-P-6 RR-P-ll ,
2E51-C001 Reactor Core Isolation H-26024 2 Pd NA NA (Note 3) Cooling C-6 (Centrifugal) Q Qtr Note 5 V Qtr NA N Qtr NA
& Qtr Note 4 6-2 Rev. 0
l t O O O l M P-2 PUNP TESTING TABLES l l P&ID/ Code Test Test j Pump ID Description Coord Class Parameter Frequency RIURemarks 2P41-C001A Plant Service Water H-21033 3 Pd NA NA l (Vertical Line Shaft) B-2 2P41-C001B H-21033 Q Qtr RR-P-Il E-2 2P41-C001C H-21033 V Qtr RR-P-4 C-2 RR-P-ll 2P41-C001D H-21033 N NA NA G-2
- AP Qtr Note 2
( RR-P-11 l ! 2P41-C002 Standby Diesel Gen. H-21033 3 Pd NA NA l Service Water J-2 i (Vertical Line Shaft) Q Qtr RR-P-ll l V Qtr RR-P-8 i RR-P-Il N NA NA l l AP Qtr Note 2 RR-P-11 2Y52-C001A Diesel Fuel 011 Transfer H- NA Pd NA NA (Vertical Line Shaft) 2Y52-C001C (Note 6) H- Q Qtr Note 7 2Y52-C101A H- V Qtr Note 8 2YS2-C101C H- N NA NA AP NA Note 7 6-3 Rev. 0
4 7.0 PUNP RELIEF Brmr4 LOG Relief Reauest Status
- 4 RR-P-1 RR-P-2 Submitted for approval i RR-P-3 Submitted for approval
- RR-P-4 Submitted for approval '
RR-P-5 Submitted for approval RR-P-6 Submitted for approval 4 RR-P-7 Submitted for approval RR-P-8 Submitted for approval RR-P-9 Submitted for approval RR-P-10 Submitted for approval RR-P-11 Submitted'for approval
' Submitted for approval ',
i i {
- Status as a result of 3rd Interval IST Program submittal , Revision 0 l
- l lO i
l 1 l i i 1 i i lO 7-1 i Rev. 0 i
f ! . PUMP RELIEF REQUEST RR-P-1 SYSTEM: Standby Liquid Control (IC41 & 2C41) PUMPS: IC41-C001A & B (Positive Displacement Pumps) 2C41-C001A & B (Positive Displacemer.t Pumps) [ CLASS: 2 # i
- TEST REQUIREMENT: ISTB 4.6.l(f) -
The frequency response. range of the vibration ! i ~ measuring . transducers and their readout system shall be from one- i third minimum pump shaft' rotational speed to at least 1000 Hz. ; BASIS FOR
'ELIEF: The Standby Liquid Control (SBLC) Pumps operate at 370 RPM (6.2 Hz), .
therefore the instrument frequency response range of the Plant Hatch ! IST Program instrumentation does not satisfy the code requirement. l In lieu of the requirements of ISTB 4.6.l(f), the vibration i i ' measuring instrument frequency response range utilized for the Standby Liquid Control Pumps will be as described below.
- 1
- 1. An I.R.D. Model 810 with accuracy of *5% over a frequency
! response range of 5.8 - 10,000 Hz or a CSI Model 2100 analyzer with ; accuracy of tS% over a frequency response range of 3 - 5000 Hz ! (displacement) is utilized for IST.
- 2. These lower frequency response limits result from high-pass {
4 filters which eliminate low-frequency elements associated with the i i input signal from the integration process. These filters prevent ;
- low frequency electronic noise from distorting vibration readings thus any actual vibration occurring at low frequencies is filtered
, out. ! 3. The SBLC pumps are Union Pump Company reciprocating pumps. The i subject pumps utilize roller bearings instead of sleeve bearings. , Sleeve bearings can exhibit vibration at subsynchronous frequencies when a condition of oil whirl is present. However, oil whirl does not occur in roller or ball bearings. t i 4. Roller and ball bearing degradation symptoms typically occur at IX (6.2 Hz) shaft rotational frequency and greater. Therefore, ; vibration measurements at frequencies less than shaft speed would t ) not provide meaningful data relative to degradation of the pump bearings. ,
- 5. The SBLC pumps are standby pumps only. They are only operated ;
during Technical Specification Surveillance and Inservice Testing which results in very little run time. In the unlikely event that
- i the system is required to perform its safety function, the pump run ;
time would be from 19 to 74 minutes to exhaust the volume of the 2 i sodium pentaborate storage tank. l 4 1 7-2a Rev. O ; t
h l RR-P-I (cont) l 6. 'In addition to the IST vibration monitoring program, these pumps are included in the site maintenance department vibration program. , ( This program has the capability to perform spectral analysis with equipment which would satisfy the frequency response range : requirement of the ISTB 4.61(f). The maintenance vibration ' monitoring may not be performed at a frequency equivalent to that i required for IST, but based on the infrequent operation of these pumps, the likelihood that a vibration problem would go undetected i , by both programs is minimal. The maintenance vibration program will also be utilized to analyze any IST vibration data which placed the pumps in the ALERT or ACTION Ranges. The need for any corrective actions would be based on evaluation of IST and maintenance testing i program data.
; 7. Based on the pump bearing design, the combination of vibration monitoring implemented and the limited operation time, it seems unlikely that a vibration problem not detectable by the equipment being utilized would prevent these pumps from fulfilling their design safety function.
ALTERNATE , TESTING: None, use of the existing vibration monitoring equipment which is calibrated to at least 25% full scale over a frequency response range of 5.8 -2000 Hz or 3 - 5000 Hz (SBLC pump nominal shaft speed 6.2 Hz) should provide sufficient data for monitoring the
- mechanical condition of the SBLC pumps. This equipment will provide
; accurate vibration measurements over the frequency range in which ; typical roller bearing vibration problems occur. This monitoring
- . program should meet the intent of the code and will relieve the l utility from the burden and expense involved with procurement, calibration, training and administrative control of new testing
- equipment which seems unjustified for assessing the mechanical
] condition of the subject pumps. -O 7-2b Rev. 0 l l l
~ . . - - - - . . . . - - . . - . . . - ~ --. . - -
l PUMP RELIEF REQUEST ! j RR-P-2 I SYSTEM: Residual Heat Removal (IEll & 2 Ell) PUMPS: IEll-C002A,B,C,D (Centrifugal Pumps) i 2 Ell-C002A,B,C,D (Vertical Line Shaft Pumps) i CLASS: 2 ' l i TEST
- REQUIREMENT: ISTB 4.6.l(1) requires that the full-scale range for each analog ;
- instrument shall not be greater than three times the reference <
' value. RHR pump pressure indicators 1(2) Ell-PI-R003A-D exceed this Code allowable range limit. 1 BASIS FOR ! ! RELIEF: The original installed instrumentation associated with these pumps i was not designed with the instrument range limits of OM Code ISTB i 4.6.1(1) taken into consideration. The actual instrument ranges are l . itemized below. INSTRUMENT BNEE TEST RANGE ALLOWABLE RANGE ACCURACY , ' IEll-PI-R003A-D 0-600 psig = 182 psig 0-546 psig 2% 2 Ell-PI-R003A-D t ! 0-600 psig = 186 psig 0-558 psig
- 2%
} ALTERNATE - , TESTING: None, use installed instrumentation. 5
- Even though 1(2) Ell-PI-R003A-D exceed the Code allowable range limit
' of three times the reference value, this additional gage range only ' i-results in approximately 1 psig maximum variance form the Code allowable in the measured parameter (i.e. 02 x 546 - 11 psig versus
- .02x600=12psig). Using other instrumentation to account for a ;
i 1 psig improvement in measurement accuracy is not justifiable i considering the cost associated with such a requirement. These ' pressure indicators should provide data that is sufficiently accurate to allow assessment of pump condition and to detect degradation. t 4 i
- o 7-3 Rev. 0 4
PUNP RELIEF REQUEST
- RR-P-3 SYSTEM: Residual Heat Removal (IEll & 2 Ell)
PUMPS: IEll-C002A,B,C,D (Centrifugal Pumps) 2 Ell-C002A,B,C,D (Vertical Line Shaft Pumps) , l TEST
- REQUIREMENT
- ISTB 4.6.l(1) requires that the full-scale range for each analog
, instrument shall not be greater than three times the reference value. RHR pump flow indicators 1(2) Ell-FI-R603A&B exceed this Code j allowable range limit. l BASIS FOR RELIEF: The original installed instrumentation associated with these pumps -
- was not designed with the instrument range limits of OM Code ISTB j 4.6.l(1) taken into consideration. The actual instrument ranges and
] loop accuracies are itemized below. l INSTRUMENT EMBE TEST RANGE ALLOWABLE RANGE ACCURACY 1 Ell-FI-R603A&B 0-25000 gpm = 7700 gpm 0-23100 gpm 1.66%
- 2E11-FI-R603A&B 0-25000 gpm = 7850 gpm 0-23550 gpm 1.22%
i
- COMPONENT / CONPONENT/ CONPONENT/ LOOP ACCURACY 2
ACCURACY ACCURACY ACCURACY PER ISTB 1.3 1 lEll-FT-N015A,B IEll-K600A,B IEll-FI-R603A,B 1.66 % 0.5 % 0.5 % 1.5 % i 2 Ell-FT-N015A,B 2 Ell-K600A,B 2 Ell-FI-R603A,B 1.22 %
- 0.5 % 0.5 % 1%
1(2) Ell-FI-R603A(B) exceed the Code allowable full scale range limit i of three times the reference value. The indicator range includes
- consideration for LPCI flow rate (17,000 gpm for two pumps), whereas the IST pump flow rate is 7,700 gpm fpr Unit I and 7,850 for Unit 2.
.i The Code maximum allowable variancein measured flow rate would be 4 462 gpm (i.e. .02 x 23,100) for Unit I and 471 gpm (i.e. 02 x i 23,550) for Unit 2. Whereas the actual maximum variance in measured flow is 425 gpm (i.e. 017 x 25,000) for Unit I and 325 gpm (i.e. J .013 x 25,000) for Unit 2. Therefore, the actual accuracy of the e installed flow indicators is greater than allowed by the Code, thus 1 the range of the indicator exceeding the Code limit of three times J the reference value is of no consequence.
- ALTERNATE TESTING
- None, use installed instrumentation.
j Even though 1(2) Ell-FI-R603A&B exceed the Code allcwable range limit of three times the reference value, the overall loop accuracy is
! greater than required by the Code. Therefore, the measured '
parameter is more accurately displayed than the Code requires. 7-4 Rev. O
l PUMP RELIEF REQUEST RR-P-4 { i SYSTEM: Residual Heat Removal Service Water (IEll &'2 Ell)
- q. Plant Service Water (IP41 & 2P41) l PUMPS: IE11-C001A,B,C,D (Vertical Line Shaft Pumps) !'
l 2 Ell-C001A,B,C,0 (Vertical Line Shaft Pumps) , IP41-C001A,B,C,D (Vertical Line Shaft Pumps) : 2P41-C001A,B,C,D (Vertical Line Shaft Pumps) ; i ,. TEST i-
' REQUIREMENT: ISTB 4.6.4(b) requires that vibration measurements on vertical line t shaft pumps be taken on the upper motor-bearing housing in three orthogonal directions, one of which is in the axial direction. ;
BASIS FOR ! j RELIEF: The Code required vibration measurements on the upper motor-bearing ! housing on these vertical line shaft pumps are impractical because i ) of the following reasons. i q i
- 1. Plant design did not include permanent scaffolding or ladders j which provide access to the top of the motors for the subject pumps. -
- - 2. Physical layout of the pumps and interference with adjacent components does not allow for the installation of temporary scaffolding or ladders which are adequately safe for routine use.
- 3. There is a relatively thin cover plate bolted to the top-center i of each motor which prevents measurements in line with the motor ,
i bearing. Measurement on the edge of the motor housing would be '
- influenced by eccentricity and may not be representative of actual t axial vibration.
- 4. Special tools (extension rod) for placing the vibration transducers are not practical because placement would not be sufficiently accurate for trending purposes, i i
i 5. Research within the industry has indicated that vibration ' j monitoring of vertical line shaft pumps has been of limited benefit l
- for detecting mechanical degradation due to problems inherent with i
pump design. The OM Code imposes more stringent hydraulic ; acceptance criteria on these pumps than for centrifugal or positive :
; displacement pumps. These more stringent hydraulic acceptance ;
2 criteria place more emphasis on detection of degradation through , hydraulic test data than through mechanical test data. '
, ALTERNATE j i TESTING: Vibration measurements will be taken in three orthogonal directions, 4
one of which is in the axial direction in the area of the pump to l motor mounting flange. This is the closest accessible location to l a pump bearing housing and this location is easily accessible for : test personnel which should ensure repeatable vibration data and l should provide readings which are at least as representative of pump j
, mechanical condition as those required by the Code. j i
i' 1
; 7-Sa Rev. O
i RR-P-4 (cont) I Therefore, application of the OM Code hydraulic testing criteria ; along with radial and axial vibration monitoring in the area of the ! pump to motor mounting flange should provide adequate data for ; 1 assessing the condition of the subject pumps and for monitoring J' degradation, i t i 1 . J h t l 1 . f, i i $ i l 1 i i \ I< J l i \ i l l 1 i i i l T i 1 l l i 1 q- ) i l i 1~ 7-Sb Rev. 0 1
PUNP RELIEF REQUEST RR-P-5 ' 1 SYSTEN: Core Spray (IE21 & 2E21) PUNPS: IE21-C001A&B (Centrifugal Pumps) i 2E21-C001A&B (Vertical Line Shaft Pumps) l TEST
- REQUIRENENT: Table ISTB 4.6.1-1 requires a total instrument loop accuracy for
! pressure indicators of 2% of full scale. ! BASIS FOR ' l RELIEF: Pressure indicators 1(2)E21-PI-R600A(B) exceed the maximum code i allowable total loop accuracy of 2% full scale. The actual ! instrument ranges and loop accuracies are itemized below. 1 i INSTRUNENT RANGE TEST RANGE ALLOWABLE RANGE ACCURACY ;
+
i IE21-PI-R600A&B 0-500 psig = 290 psig 0-870 psig 2.06% l 2E21-PI-R600A&B 0-500 psig = 308 psig 0-924 psig
- 2.06%
i COMPONENT / COMPONENT / COMPONENT / LOOP ACCURACY l ACCURACY ACCURACY ACCURACY PER ISTB 1.3 i j IE21-PT-N001A&B IE21-PI-R600A&B NA 2.06 % j 0.5 % 2% NA i
- 2E21-PT-N001A&B 2E21-PI-R600A&B NA 2.06 % <
j 0.5 % 2% NA i The indicators used have full scale ranges less than that allowed by i the Code. The maximum code allowable variance in measurement is 17 i psig (.02 x 870) for unit I and 18 psig for unit 2 (.02 x 924). By i using an indicator with a range less than allowed, the actual l maximum variance is 11 psig (.021 x 500) which is more accurate than
- required by the Code. Therefore, the actual accuracy of the instruments is within the code allowable.
ALTERNATE {
- TESTING
- None, the installed instruments are more accurate than required by j the Code for the range of application.
i 1 i 4 i
;O i
7-6 Rev. O i 1
PUMP RELIEF REQUEST RR-P-6 8 SYSTEM: High Pressure Coolant Injection (1E41 & 2E41) PUMP (S): 1(2)E41-C001 (Centrifugal Pumps) CLASS: 2 TEST REQUIREMENT: ISTB 4.6.l(1) requires that the full-scale range for each analog instrument shall not be gre'ater than three times the reference value. HPCI pump pressure indicators 1(2)E41-PI-R004 exceed this Code allowable range limit. BASIS FOR RELIEF: 1(2)E41-PI-R004 exceed the range limit of three times the reference value. The actual instrument ranges are itemized below. The indicators are calibrated to 1 % full scale accuracy which results in the final variance being within the maximum allowable by the code (i.e. I psig versus 1.6 psig for unit I and 1 psig versus 1.8 psig for unit 2). INSTRUMENT 88 TEE TEST RANGE ALLOWABLE RANGE ACCURACY 1E41-PI-R004 15"Hg-100 psig = 27 psig 0-81 psig *1% 2E41-PI-R004 15"Hg-100 psig = 30 psig 0-90 psig 1% ALTERNATE TESTING: None, the installed pressure indicators provide measurements which are within the Code allowable accuracy. l l 7-7 Rev. O I
l PUMP RELIEF REQUEST RR-P-7 SYSTEM: High Pressure Coolant Injection (IE41 & 2E41) PUMP (S): 1(2)E41-C001 (Centrifugal Pumps) , CLASS: 2 TEST REQUIREMENT: Table ISTB 4.6.1-1 requires a total instrument loop accuracy for pressure indicators of 2% of full scale. HPCI Flow indicators 1(2)E41-FI-R612 do not meet this requirement. BASIS FOR RELIEF: total loop accuracy). The Flowactual indicators 1(2 E41-FI-R612 instrument exceed loop accuracies are the m itemized below. The indicator used has a full scale range less than that allowed. Therefore, the maximum variance allowable by the Code is 255 gpm (.02 x 12750) whereas the actual maximum variance is 106 gpm (.0212 x 5000). Therefore, the actual accuracy of the instrument loop is better than that allowable by the Code. INSTRUNENT B&M61 TEST RANGE ALLOWABLE RANGE ACCURACY lE41-FI-R612 0-5000 gpm = 4250 gpm 0-12750 gpm 2.12 % 2E41-FI-R612 0-5000 gpm = 4250 gpm 0-12750 gpm
- 2.12 %
COMPONENT / COMPONENT / COMPONENT / LOOP ACCURACY ACCURACY ACCURACY ACCURACY PER ISTB 1.3 IE41-FT-N008 IE41-K601 IE41-FI-R612 2.12 % 0.5 % 0.5 % 2% 2E41-FT-N008 2E41-K601 2E41-FI-R612 2.12 % 0.5 % 0.5 % 2% ALTERNATE ! TESTING: None, the installed flow indicators within the Code allowable accuracy. provide measurements which are O 7-8 Rev. 0 1
PUMP RELIEF REQUEST RR-P-8 SYSTEM: Standby Plant Service Water (2P41) PUMP: 2P41-C002 (Vertical Line Shaft Pump) TEST REQUIREMENT: ISTB 4.6.4(b) requires that vibration measurements on vertical line shaft pumps be taken on the upper motor-bearing housing in three orthogonal directions, one of which is in the axial direction. ! BASIS FOR RELIEF: The Code required vibration measurements on the upper motor-bearing housing on this vertical line shaft pump are impractical because of the following reasons. ,
- 1. The motor has a cooling fan mounted at the top which is attached to the rotating shaft. The fan is protected by a relatively thin cover plate which prevents access to the motor housing for vibration measurements. Removing the cover does not provide for transducer placement since the rotating fan would still be in the way.
- 2. Research within the industry has indicated that vibration monitoring of vertical line shaft pumps has been of limited benefit for detecting mechanical degradation due to problems inherent with pump design. The OM Code imposes more stringent hydraulic acceptance criteria on these pumps than for centrifugal or positive Q
C/ displacement pumps. These more stringent hydraulic acceptance criteria place more emphasis on detection of degradation through hydraulic test data than through mechanical test data. ALTERNATE TESTING: Vibration measurements will be taken in three orthogonal directions, one of which is in the axial direction in the area of the pump to motor mounting flange. This is the closest accessible location to a pump bearing housing and this location is easily accessible for test personnel which should ensure repeatable vibration data and should provide readings which are at least as' representative of pump mechanical condition as those required by the Code. i Therefore, application of the OM Code hydraulic testing criteria along with radial and axial vibration monitoring in the area of the pump to motor mounting flange should provide adequate data for assessing the condition of the subject pumps and for monitoring degradation. O L) l 7-9 Rev. 0 f
i PUMP RELIEF REQUEST : 1 RR-P-9 i SYSTEM: All system pumps included in IST Program ; PUMPS: All included in IST Program ) 4 CLASS: 2 and 3 I i TEST 4 REQUIREMENT: Table ISTB 5.2-2a requires the vibration measurements (V) be compared to a multiple of the initial reference value (Vr) to determine in the pump is acceptable or is in the ALERT Range (2.5Vr)'
- or ACTION Range (6Vr).
BASIS FOR
- RELIEF: Small absolute changes in vibration for a smooth running pump (i.e.
] a reference value s.075 in./sec or 2 mils) would potentially result in ALERT and Required ACTION Ranges being declared for exceeding the
- 2.5Vr or 6Vr limits even though the pump is still operating satisfactorily. Pumps with very small reference values may
} experience some degradation and yet still be operating acceptably, i Therefore, it is unwarranted to place such pumps in the ALERT or j ACTION Range based on this very small increase in measured vibration , magnitude.
- ALTERNATE ;
i TESTING: In lieu of the requirements of TABLE ISTB 5.2-2a, ranges for 1O 'V. vibration acceptance criteria for pumps with reference values s.075 in/sec or 2 mils (smooth running pumps) will be as outlined below. The ALERT Range for smooth running pumps will be > 0.19 in/sec to , 0.45 in./sec. or 6 mils to 14 mils, and the Required ACTION Range starts at any value above 0.45 in./sec or 14 mils. 1 , I 1 i j I
- O i ;
k i 7-10 Rev. 0 l
.- . - - ~ . .. - - - - . . . -.. - .. . . - - - . . ._ ..,
I { PUMP RELIEF REQUEST RR-P-10 ' QO. 1 SYSTEM:' HPCI (IE41 and 2E41) , PUMPS: 1E41-C001 - 2E41-C001-CLASS: 2 I TEST- l REQUIREMENT: - Table ISTB 5.2-2 establishes the vibration alert range for ;
- centrifugal pumps that operate at a
- 600 rpm at > 2.5Vr to 6Vr or. j
>0.325in./sec. -
BASIS FOR j- RELIEF: The HPCI pump design resulted in a structural casing resonance at ) very near the recommended running speed. This results in a peak i , vibration value on- the main pump . inboard bearing housing in the ; i vertical direction that routinely exceeds the 0.325 in./sec maximum i value thus placing the HPCI pump in the Alert Range. _i l'
- Review of spectral data for the pumps results in the largest peak i j vibration values at IX (usually unbalance), 2X (usually 4
misalignment), 5X (vane pass) and 7X (vane pass). Of these peaks, i the highest occurs at IX. This IX peak also fluctuates as the speed : , of the HPCI pump is varied. l ! The HPCI pump IST is performed by setting the flow and the turbine I speed at the reference values and then monitoring the differential ; pressure. The turbine speed and flow rate are set as close as can be read on the instrumentation, however, the HPCI flow controller c varies the turbine speed within some range to maintain the selected
- flow rate. Thus some change in speed does occur.
l ' The nominal turbine speed for the HPCI pump IST is 3,800 rpm (63.3 , Hz). A dead blow hammer test of the HPCI pump casing resulted in a ' natural frequency of 65.9 Hz. During a trial test, the vibration i magnitude of the inboard bearing doubled (0.11 in./see to 0.22 in./sec) when the turbine speed was increased from 62.94 Hz (3,776 i d rpm) to 64.8 Hz (3,880 rpm). While this amplitude is not sufficient i to place the pump in the Alert Range, when added to that of some ' i nominal unbalance (IX) or amplitudes occurring at frequencies from ! l other sources, the vibration data sometimes exceeds the 0.325 j in./sec allowable by the Code resulting in an increase in test i i frequency for the pump. This phenomenon occurs randomly which indicates that it is not indicative of mechanical degradation. Spectral vibration analysis by the maintenance engineering 1 department indicates that there are no mechanical concerns with HPCI ' ' pump operation. Shaft vibration data obtained from proximity probes revealed very low amplitudes at the IX operating speed .with vibration being 0.4 mils. This shaft data did not - detect any .
- . natural frequencies associated with the shaft which indicates that~ ;
2-the natural frequencies identified for the bearing housing are l structural related with no participation from the shaft. L ,- 7-Ila Rev. O i
i RR-P-10 (cont) Based on testing data taken to date, and evaluation by the maintenance engineering department, there is no apparent trend for mechanical degradation and no apparent justification for increasing , the HPCI pump test frequency when the vibration level randomly I exceeds the 0.325 in./sec Code allowable value. ALTERNATE TESTING: The Alert Range for the HPCI Pump will be set at 2.5Vr to 6Vr or 0.4 i in./see to 0.7 in//sec. In addition to the normal HPCI pump IST, i the maintenance engineering department will routinely perform 1
- spectral analysis of the vibration data to ensure that no trend to 1 mechanical degradation goes undetected. This nominal increase in the lower limit for the Alert Range should not affect the overall ;
operability of the HPCI pump and the maximum allowable vibration limits for the Required Action Range are being maintained. O l 1 ) i 4 4
]
7-11b Rav. O
PUMP RELIEF REQUEST RR-P-11 SYSTEM: All included in IST Program PUMPS: All included in IST Program CLASS: 2 and 3 TEST REQUIREMENT: ISTB 6.1.- If deviations fall within the required action range of Table ISTB 5.2-2, the pump shall be declared inoperable until the cause of the deviation has been determined and the condition corrected. BASIS FOR RELIEF: The ASME Section XI Code, subsection IWP-3230(c) stated that; l
" Corrective action shall be either replacement or repair per IWP-3111, or shall be an analysis to demonstrate that the condition does not impair pump operability and that the pump will still fulfill its function. A new set of ,
reference values shall be established after such analysis." l The OMc-1994 Addenda (ISTB 6.2.2) and the OM 1995 Edition (ISTB l 6.2.2) both state that; "If the measured test parameter values fall within the 3 O required action range of Table 5.2.1-1, Table 5.2.1-2, Table 5.2.2-1, or Table 5.2.3-1, as applicable, the pump shall be declared inoperable until either the cause of the . deviation has been determined and the condition is ! corrected, or an analysis of the pump is performed and new j . reference values are established in accordance with ISTB : i 4.6." l The Code applicable for the second interval IST Program and the 1 latest issued Code both provide for analysis of pump test data in ! lieu of repair or replacement of the pump if the test parameters 4 fall within the required action range. The OM Code-1990 Edition did
- not include such provisions. Communications with members of the OM
! Code Committee indicate that this was an oversight and that it was
- never intended to delete the ability to analyze the test data and
- determine if the pump is still capable of performing its intended
- safety function.
i 4 ALTERNATE
- TESTING
- Should pump test parameters fall within the required action range of Table ISTB 5.2-2 (OM Code 1990 Edition), then the OM Code 1995
! Edition, subsection ISTB 6.2.2 will be utilized. Since subsection l ISTB 4.6 in the 1995 Code Edition references ISTB 6.2.2, subsection l ISTB 4.6 form the OM Code 1995 Edition will also be applied. l I 7-12 Rev. 0 l
8.8 INSERVICE TESTING OF VALVES 8.1 GENERAL, This IST Program was developed to comply with the testing provisions of 10 CFR O 50.55a(f) which delineate the testing requirements for ASME Class 1, 2, and 3 valves. The code of record applicable to meet these provisions is the ASME OM Code 1990 Edition with the exception of Appendix I. Appendix I of the ASME OM Code 1995 Edition was utilized instead of the 1990 version. The supplemental guidance of NRC Generic Letter 89-04 and Supplement 1 (NUREG-1482) have been applied to the extent practicable. In cases where specific Code requirements cannot be met, relief has been requested from these requirements. Valves in the program are listed by MPL Number in Tables 10 and 11 for Units 1 and 2, respectively, and will be tested in accordance with the Code unless otherwise specified in this program. ! 8.2 1G0ff : Safety-related ASME Class 1, 2', and 3 valves covered by the Regulatory Position of Regulatory Guide 1.26 are included within the scope of this program and are tested using the provisions of the ASME OM Code. Containment isolation valves located in non-safety related systems are considered safety-related for - containment purposes and are, therefore, tested under the provisions of the OM Code and 10 CFR 50, Appendix J as applicable. In cases where Code requirements are impractical or an alternate testing method is considered an improvement over OM Code requirements, a relief request'has been developed. Valve relief requests are located under a separate tab. 5 i It is recognized that 10 CFR 50 Appendix A, GDC-1, and Appendix B, Criterion XI intend that all valves necessary for. safe operation of the plant be tested to O demonstrate that they will perform satisfactorily in service. This testing is required to be performed at a level commensurate with the safety function of the i valve, and is generally performed per the requirements of the plant Technical l Specifications or other regulatory requirements. , RCIC System flE51 and 2E51) i , No credit is taken in any of the accident analyses for the RCIC system. RCIC i System valves that do not perform a containment isolation function are still l considered to be important and thus require a certain level of testing and have, i therefore, been included in this program. This testing will be performed in a I manner similar to the OM Code testing 'and should adequately detect degradation. e The testing of these valves is included in this program only to provide a readily
- accessible, documented method of testing. Subsequently, relief requests are not considered to be required. '
Diesel Generator Fuel Oil Transfer System flR43 and 2R43) f j The Diesel Generator Fuel 011 Transfer and Air Start System valves are considered to be essential valves requiring a high level of testing and have, therefore, been included in this program. However, these valves are not ASME Class components and are not included in the scope as defined in Regulatory Guide 1.26. Testing of
- these velves will be performed in a manner similar to that found in the OM Code, which should adequately detect degradation in these particular valves. While similar to OM Code testing requirements, the testing of these valves is included i
- O in this program only to provide a readily accessible, documented method of testing. Subsequently, relief requests are not considered to be required.
8-1 Rev. 0 l _.,y ~ 9-. _ _
Soent Fuel Pool Coolina (1G51 and 2G51) The Spent Fuel Pool Cooling System valves have not been included in this Program because they are not considered to be safety-related. Credit is taken in the FSAR O for Plant Service Water as the safety-grade makeup source for the spent fuel pool, and the RHR system is utilized as the backup cooling source. Jockey Pumo System (IE21 and 2E21) The Core Spray Jockey Pump System valves have not been included in this Program because they are not considered to be safety-related. Safety related instrumentation provides an alarm in the main control room if water inventory is , depleted in the RHR and core spray system Therefore, testing of the jockey pump system valves is not warranted. piping. . Control Rod Drive System (CRD IC11 and 2C11) As described in Position 7 of Generic Letter 89-04, certain individual CRD Valves will be tested to the extent practical. All subject valves except the scram ; discharge volume vent and drain valves will be tested using the technical ! specification frequency. Specific frequencies for each valve and the bases for ' the frequency are given in each referenced relief request. B The scram discharge volume vent and drain valves do not operate independently of one another. One switch operates all six valves and the valves are required to operate in a particular sequence to provide closure of all valves within a . Technical Specification allowable time. Therefore individual stroke time testing ' of these valves is not practical. As an alternative test, these valves will be exercised quarterly but not timed. The total valve sequence response time will ; be verified to be within Technical Specification requirements each refueling O outage. See Relief Request RR-V-3. ! The scram insert and withdraw valves are solenoid valves that full-stroke rapidly. l Measuring the full-stroke required by the code is impractical for these valves; therefore, verification that the associated control rod meets the required scram insertion time will be used as the alternate method to detect degradation of these i valves. ! ! The scram discharge volume check valves are required to open to fulfill their
- safety function. Required flow is achieved through these valves during the :
i technical specification control rod drive insertion tests. ! The charging water HCU check valves are required to open and to close to fulfill
- their safety function. Forward flow operability is proven during Technical j Specification testing and reverse flow closure will be proven by a leakage /
i pressure decay test. ;
- The cooling water header.HCU check valves and the drive water insert and withdraw [
valves are exercised to their safety-related position (closed) during weekly CRD j i exercise testing. ; ! Nitroaen'Inertina System (IT48 and 2T48)
'The only. portions of the 1(2)T48 system (Nitrogen Inerting System) which are l considered to be within the scope of inservice testing are those associated with t
- primary containment and vacuum relief. The HNP-1 primary containment is inerted l during normal 3peration to minimize the potential of a hydrogen combustion for a !
y LOCA, where hydrogen is produced due to the zirconium and steam reaction. However, l 8-2 Rev. 0 l l t _ 1
-_ - -. -. -- - - - . - . - -- -_- . _ ~ . - - . - - _ - _ .
- this function is considered to be cutside the scope of censideration for inservice
-testing.
An evaluation is included in:this IST Plan for certain components which do not O provide a containment isolation or vacuum relief function due to the nature of the particular component. These evaluations .are included for convenience and information. Architect Engineer (SCS) review of the boundaries for ASME Section XI scope > resulted in inclusion of components only associated with containment isolation. Therefore, since components associated with nitrogen purge, venting, and nitrogen, , makeup were not included in the ASME XI ISI boundaries, containment isolation and vacuum relief are considered to be the only safety related functions for IST. l 8.3 PRESSURE ISOLATION VALVES (PIV) : Pressure isolation valves (PIVs) are defined as two normally closed valves in i series that isolate the Reactor Coolant System (RCS) .from the attached low pressure system. Event V pressure isolation valves (Wash 1400) are defined by ; Generic Letter 89-04 as "two r,har,k valves in series at a low pressure /RCS ' interface whose failure may result in a LOCA that bypasses containment." At Plant Hatch, there are no normal operating conditions in which two check valves function ; as the.RCS/ low pressure interface, therefore, Event V PIVs are not applicable. ! Pressure isolation valves are not listed in the Technical Specifications, therefore, they were selected using the above definition. Each pressure isolation valve is designated "PIV" in the~" Leakage" column. Some valves function as both ; pressure and containment isolation valves, and are designated as "PIV/CIV." Instrumentation to monitor the leakage downstream of each pressure isolation valve during power operation was not a design requirement of Plant Hatch. Also, while it is practical to test several of the valves individually, the ability to isolate ' and test each valve separately was not a design consideration. Subsequently, all valves cannot be practically tested on an individual basis. A pressure test will be performed each refueling outage as follows. 3 p a. A valve that serves only as a pressure isolation valve is tested at operating differential pressure or at a reduced pressure as allowed by i ISTC 4.3.3(b)(4), using water as a test medium. The leakage observed i during a reduced pressure test is then adjusted to a " function maximum ! pressure differential value" as required by ISTC 4.3.3(b)(4). The l allowable leakage at operating differential pressure for RCS/ low pressure piping interface valves is 0.5 gpm (1892 cc/ min) per inch of valve size j up to a maximum of 5 gpm. The allowable leakage for the Feedwater
- interface valves, optionally included as PIVs, is specified by GPC for j each specific valve.
l
- b. An RCS/ low pressure piping interface valve that also functions as a containment isolation valve (CIV) is Appendix J. Type C tested using CIV
- acceptance criteria since these criteria are more stringent. Acceptable leakage for these valve is always less than the PIV criterion of 1892 cc/ min per inch of valve size, even when the adjustment to the " function maximum pressure differential value" is performed. A Feedwater/ low pressure piping interface valve that also functions as a containment i
isolation valve (CIV) is Appendix J, Type C tested using CIV acceptance criteria. 8-3 Rev. 0 y.,
8.4 CONTAINMENT ISOLATION VALVES (CIV) All containment isolation valves that receive a Type C, Appendix J test are included in this Program and are identified as "CIV" under Leakage in Tables 10 and 11. Any changes in the Appendix J, Type C testing scope will be reflected in this document with appropriate changes to the tables. Georgia Power Company conforms to the requirements of ISTC 4.3.3(e) to the extent practical by assigning a specific leakage limit to each valve or penetration assembly. Limits are based on the type and size of each valve, the number of valves within the test boundary, and historical leakage data. As a rule, test configurations have the least number of boundary valves practical to perform the Type C test; however, the piping arrangement at Plant Hatch generally requires the pressurization of a combination of CIVs and block valves simultaneously. In these cases a leakage limit is applied to each penetration test configuration. During the testing of the penetration, if the measured leakage exceeds the limit for the penetration, causes are investigated and repairs made to specific valves as necessary. The intent of OM Code to detect degradation (and repair if necessary) of each valve due to service related conditions is therefore met. t
,8.5 LEAK TIGHT VALVES (LTV)
These excess flow check valves have been categorized by Georgia Power Company as i needing testing to ensure adequate closure to prevent gross amounts of leakage. l They do not have a specific leakage rate assigned to them and as a result are not required to be Category A or AC valves; however, per 1987 commitment with the NRC l the excess flow check valves are categorized as AC. ) O
- V
- 8.6 FAIL-SAFE VALVES 1
Unless otherwise specified in the program tables, additional fail-safe testing ' will not be performed. Stroking the valve full cycle during normal testing causes loss of power to the actuator as required by ISTC 4.2.6. Therefore, additional testing to provide the fail-safe capability is not required. l 8.7 PASSIVE POWER OPERATED VALVES A passive power operated valve does not perform a mechanical motion during the course of accomplishing a system safety function. These valves are identified as such in the " Function Description" in Tables 10 and 11. Per Table ISTC 3.6-1, passive Category B valves do not require any exercise testing and verification that actual valve position is indicated by remote position indication lights every two years is the only testing required. 1 i J l 8-4 Rev. O
! l , VALVE NOTES i 1. Exercise frequency is per Technical Specifications and is described in l Refueling Outage Justification ROJ-V-7. l 3
- 2. Typical of 137 Control Rod Drive mechanisms.
i
- 3. The CRD cooling water check valves are exercised to their safety-related j position (closed) during weekly CRD exercise tests (notch in/ notch out). ,
4 Insertion of the CRD verifies that the required pressure boundary is intact i and the check valve is closed. l l i
- 4. This containment isolation valve is not leak rate tested due to the line it i
- is on terminating below the water level of the torus. No leakage test is !
j necessary to satisfy Appendix J requirements as the torus is postulated to j always remain water filled.
- 5. Relief valve testing is performed in accordance with the OM Code-1995 Edition, Appendix 1.
l
- 6. Closure of this pump discharge check valve is proven during pump 4 surveillance testing. There are two pumps on each train; therefore, when l one pump is being tested the other is not operating. For the pump being l l tested to pass the required hydraulic parameters, the discharge check valve l
) on the non-operating pump must close to prevent diverted flow. If the valve
- remained open, the pump test would be unsuccessful.
l 7. This check valve is exercised to the position required to perform its safety function in the open direction during quarterly surveillance testing or ! during normal operation of the associated pump.
- 8. This is a passive valve which does not require quarterly exercise testing.
! At least once every two years, the actual valve position is confirmed to j agree with the remote position indicating lights. ! 9. Full-stroke exercising of this check valve cannot be proven during normal l surveillance testing; thersfore, valves will be disassembled in accordance ! with G.L. 89-04, Position 2. Valve will be full or partial exercised with j flow after reassembly where practical. l 10. Valve is equipped with a counter weighted lever arm which is used to partial
- exercise the valve disc after re-assembly.
l
- 11. The hand wheel on this stop check valve will be exercised once per quarter to verify closure of the valve. The open position is not. safety-related.
l 12. This check valve is verified to be in the c',osed position at least every 31 l days by the technical specification requirement to confirm that the pump
- discharge piping is completely filled.
- 13. There are no test connections provided to facilitate any measurements during pump testing. Therefore, partial flow exercising after re-assembly will be confirmed by indirect means such as monitoring pipe wall temperature changes, using acoustic monitoring equipment or observing flow induced vibration and noise.
9-1 Rev. O u
i l t Valve Notes (cont) !
- 14. Non-reclosing pressure relief devices (ruputre disks) are visually inspected l l and periodically replaced in accordance with the OM Code-1995 Edition, 1 j Appendix 1. :
, 15. Forward flow operability is proven quarterly during pump surveillance i testing. Closure is proven each refueling outage by leakrate testing. j 16. This component is not within the required scope of ASME OM Code testing. j This component has been included in the IST Program to provide a readily l accessible, documented method of testing.
- 17. This stop check valve is locked open during normal operation and is not i provided with any remote indicating lights. Therefore due to the i
possibility of a mispositioned valve, it will not be exercised quarterly
- with the manual handwheel. Closure will be proven as defined in applicable 1 Refueling Outage Justification.
4 j 18. Valve closure is confirmed during quarterly HPCI pump surveillance testing i by monitoring the barometric condenser level. )
- 19. This valve will be disassembled and inspected on a frequency determined to i provide adequate assurance that the valve is operable.
- 20. These RCIC valves will be tested in a comparable manner to the test required j by ROJ-V-25 for comparable function HPCI valves.
i 21. These valves are air operated valves without indicating lights or control l switches. Measurement of stroke times will be performed by observation of , j the stem movement when the RCIC room cooler is placed into service. , ! 22. Forward flow operability of this check valve will be verified quarterly , during pump testing by observation of free flow through the sight glass located downstream of the check valve. The closed position is not i j safety-related. ! 23. Each diesel fuel oil transfer pump is tested quarterly using an ultrasonic , l flow instrument to monitor flow. The flow rate required for the valve to i fulfill its safety-related open function will be verified during quarterly l pump testing. The discharge piping from each Diesel Fuel Oil Transfer Pump , is supplied with two check valves in series. There are two pumps located in each 40,000 gallon storage tank which discharge into a single line to the ' l associated Day Tank. Satisfactory performance of a fuel oil transfer pump ! i test also proves closure of at least one of the in-series check valves on l l the associated idle transfer pump. ; i !
- 24. Stroke times cannot be measured for these valves because there are no ,
position indicators and visual observation is not possible due to the valve I design. These valves will be tested as part of the Diesel Generator Air l Start Test. Acceptable diesel generator start during monthly manual start j tests will be used to verify valve operability. Stroke time will be j verified to be acceptable semi-annually and each refueling outage by system l timing during diesel generator auto start testing. ! 25. The air receiver inlet check valves are tested quarterly for reverse flow j ! closure using a gross leakage test and each refueling outage using a pressure decay test. 9-2 Rev. O
, . . Valve Notes -(cont) l 26. This testable check valve is exercised quarterly to the open position using the test switch. Each refueling outage the valve is visually inspected and
'O the force required to open the disk is measured to ensure operability and monitor degradation. i l 27. This is a passive containment isolation valve, Cateaory AP. This valve is I never opened except for quarterly exercising of the associated torus to I drywell vacuum breaker (l(2)T48-F323s). Therefore quarterly exercising and stroke timing of these solenoid valves is not required. ) 28. At least one of these valves (IP52-F261, IP52-F262) will be leak rate tested i each refueling outage to ensure that its leakage rate is s 0.4 SCFH. i i
- 29. . At least one-third (1/3) of these valves (IP52-F263, IP52-F264, IP52-F265, j IP52-F266 and IP52-F267) will be tested each refuelinq outage to prove that the valves close and maintain their associated accumu' ator air pressure for
) a minimum of ten (10) minutes. ! 30. These valves are not within the scope of valves required to be tested by the l ASME OM Code. These valves are included in the IST Program to provide a
- 1. method of tracking the testing commitment. Valves were included in the IST l Program per HNEL commitment to NRC Generic Letter 88-14. (Letter Reference j HL-1187)
! 31. At least one of these valves (2P52-F346, 2P52-F349) will be leak rate tested j sach refueling outage to ensure that its leak rate is s 0.4 SCFH.
- 32. At least one-third (1/3) of these valves (2P52-F416, 2P52-F419, 2P52-F458, i 2P52-F461, 2P52-F681 and 2P52-F971) will be tested each refueling outage to
- prove that the valves close and maintain their associated accumulator air j
pressure for a minimum of ten (10) minutes. 1 l 33. Vacuum breaker testing is perfomed in accordance with the ASME OM Code, 1995 Edition, Appendix 1. i 34. Since this relief valve is not within the required scope of the IST Program, i the ASME OM Code-1995 Edition, Appendix I, will be used to the extent !. practical for guidance. 1 l 35. Reverse flow closure is confimed by monitoring the SBDG service water pump j (2P41-C002) discharge pressure (IP41-PI-R613 or 2P41-PI-R613) when the pump is idle. The discharge piping is provided with aa keep-fill line and if the j check valve is not closed the discharge pressure will decrease to zero. I 1 i i l
!O i
9-3 Rev. 0 1
U( t v Match Nucteer Plant Unit 1 IST Program 'Page No. 1 of 58 Valve Test Table 10 - Revision 0
-Vetve PRID/ Exercise Leakage ST Romerks ID CC Cet Description
) A/P Coord Function MP SP Frog . Test Re# RR/CSJ/ROJ l
.1821-F0104 1 AC 18" CV A N-16062 FW Inbrd CIV O 0/C .DNO/R0 CIV NA ROJ-V-1 l t -
1821-F0108 1 AC 18" CV A M-16062 FW Ir6rd CIV O 0/C DN0/R0 CIV NA ROJ-V-1 , D-3
.1821-F013A 1 C 6" RV A M-16062 Main Steam C O/C Note 5 NA No NA C-6 Safety /Retief 1821 F0133 1 SC 6" RV A W-16062 Main Stees ADS C O/C Note 5 NA Yes ROJ-V C-6 l 1821-F013C 1 C 6" RV A M-16062 Main Steam C O/C Note 5 NA No NA F-6 Safety / Relief i
l' 1821-F0130 1 BC 6" RV A M-16062 Main Steam A05 C O/C Note 5 ' NA Yes ROJ-V-2 F-6 1821-F013E 1 BC 6" RV A M-16062 Main Steam AOS C 0/C Note 5 NA Yes ROJ-V-2 F-6 1821-F013F 1 BC 6" RV A M-16062 Main Steam ADS C 0/C Note 5 NA Yes ROJ-V-2 F-6 1821-F013G 1 C 6" RV A M-16062 Main Steam C O/C Note 5 NA No NA F-6 Safety / Relief 1921-F013M 1 C 6" RV A N-16062 Main Steam C O/C Note 5 NA No NA G-6 Safety /Retief 1821-F013J 1 BC 6" RV A M-16062 Main Steam ADS C O/C Note 5 NA Yes ROJ-V-2 G-6 1821-F013E 1 BC 6" RV A M-16062 Main steam ADS C O/C Note 5 NA Yes ROJ-V-2 F-6
w N~ b . v }. Netch Nucteer Plant Unit.1 IST Program Page No '2 of $8 valve Test Tebte 10 - Revision 0 volve PSID/ Emercise Leekage ST Reserks ID CC Cet Description A/P Coord F metion MP SP ' Freq Test Reqd RR/CSJ/ROJ 1821-F013L 1' SC 6" RV A N-16062 Main Steam ADS C O/C Note 5 NA .ves' ROJ-V-2 F-6 1821 F015A 1 AC 1" EFCV A M-16062 Inst EFCV O C R0 ' .LTV NA ROJ-V-3 D-8 1821 F0150 ' 1 AC 1" EFCV A N-16062 Inst EFCV O- C RO LTV NA ROJ-V-3 C-8 1821-F015C- 1 AC 1" EFCV A M-16062 Inst EFCV O C R0 LTV NA- ROJ-V-3 D-8 1921-F0150 1 AC 1" EFCV A N-16062 Inst EFCV O C RO LTV - NA ROJ-V-3 C-8 1821-F015E 1 AC 1" EFCV A M-16062 Inst EFCV O C RO LTV NA ROJ-V-3 0-8 1821-F015F. 1 AC 1" EFCV A N 16062 Inst EFCV O C RO LTV NA ROJ-V-3 C-8 1821-F015G 1 AC 1" EFCV A H-16062 Inst EFCV 0 C R0 LTV. NA ROJ-V-3 0-8 1821 F015H 1 AC 1" EFCV A H-16062 Inst EFCV O C RO LTV NA ROJ-V-3 C-8 l 1821 F015J 1 AC 1" EFCV A M-16062 Inst EFCV O C RO LTV NA ROJ-V-3 D-8 1921-F0154C 1 AC 1" EFCV A M-16062 Inst EFCV O C RO LTV NA ROJ-V-3 C-8 1521-F015L 1 AC 1" EFCV A H-16062 Inst EFCV O C RC LTV NA ROJ-V-3 j D-8 i I
O ('% G Match Nucteer Plant Unit 1 Isf Program Pope No. 3 of 58' Vetve Test Table 10 - Revision 0 Vetve PRID/ Emercise Leekage si Reserks ID CC Cet Description A/P Coord Function NP SP Freq Test- Recyl RR/CsJ/ROJ 1821-F015N 1 AC 1" EFCV A M-16062 Inst EFCV o C to . LTV NA ROJ-V-3 C-8 It21 F015N 1 AC 1" EFCV A M-16062 Inst EFCV O C R0 LTV NA ROJ-V-3 0-8 1821-F015P 1 AC 1" EFCV A M-16062 Inst EFCV O C R0 LTV- NA ROJ-V-3 C-8 1821-F015R 1 AC 1" EFCV A M-16062 Inst EFCV O C RO LTV NA ROJ-V-3 0-8 1921-F015s 1 AC 1" EFCV A M 16062 Inst EFCV O C RO LTV NA ROJ-V-3 C-8 1921-F016 1 A 3" M0 GV A M-16062 Mein 5t;u *.8ne C C etr CIV Yes RR-V-1 E-8 Drn Irtrd CIV 1821-F019 1 A 3" M0 GV A M-16062 Main steen Line C C etr CIV Yes NA E-9 Orn Outbrd CIV 1821 F022A 1 A 24" A0 GLV A M-16062 MSIV 0 C CS CIV Yes RR-V-2 C-7 CsJ V-1 1821-F0228 1 A 24" A0 CLV A M-16062 MsIV 0 C Cs CIV ves RR-V-2 E-7 CsJ-V-1 1821-F022C 1 A 24" A0 GLV A H-16062 MSIV O Cs C CIV Yes RR-V-2 F-7 CsJ-V-1 1821 F0220 1 A 24" A0 GLV A M-16062 MSIV O C CS CIV Yes RR-V-2 G-7 CsJ-V-1 1821-F028A 1 A 24".A0 GLV A M-16062 MSIV O C Cs CIV Yes RR-V 2 C-9 CsJ V-1 i
m (m-O("*% Match Nucteer Plant Unit 1 IST Progreur Page No. 4 of 58 Velve Test Table 10 - Revision 0 Velve PRID/ Emercise Leeksge ST Reimerts - I) CC Cet Description A/P Coord Ftsiction NP SP Freq Test Reqd RR/CsJ/ROJ
.1821-F028B 1 A 24" A0 GLY A M-16062 MSIV O C CS CIV Yes RR-V-2 E-9 .CSJ-V-1 1821-F028C 1 A 24" A0 GLV A M-16062 MSIV O C CS CIV Yes RR-V-2 F-9 CSJ-V-1 1821-F0280 1 A 24" A0 GLV A M-16062 MstV o C CS CIV Yes RR-V-2 G-9 CsJ-V-1 1s21-F032A 1 AC 18" CV A M-16062 FW Outbrd CIV O C RC CIV NA ROJ-V 4 F-2 1821-F0328 1 AC 18" CV A M-16062 FW Outbrd CIV 0 C R0 CIV ' NA ROJ-V-4 F-1 te21-F036A 2 C 1" CV A M-16299 MSRV Aceta Air 0/C C Ro NA NA ROJ V-5 M-16062 supply CV D-3 1821-F036s 2 C 1" CV A M-16299 MSRV Acc m Air 0/C C RO NA NA ROJ-V-5' M-16062 Steply CV 0-3 1821-F036C 2 C 1" CV A M-16299 MsRV Acesa Air 0/C C RO NA NA ROJ-V-5 M-16062 supply CV D-3 1821-F0360 2 C 1" CV A M-16299 MSRV Aceta Air 0/C C to NA NA R0J-V-5 M-16062 Supply CV 0-3 1821-F036E 2 C 1" CV A M-16299 MsRY Acesse Air O/C C Ro NA NA ROJ-V-5 M-16062 supply CV D-3 L . _ . _ _ . _ . _ . _ , _ _ _ . . . . . _ . _ _ _ , . . . _ _ _ __ , _ _ _ _ . - - . . _ _ _ . . _
O (.~)
%s G Match Nucteer Flent Unit 1 IST Program Pese'No. 5'of 58 Velve Test Table 10 - Revision 0 Velve PRIDI Exercise Leekepe ST Remarks ID CC Cet Description A/P Coord Function NP SP Freq Test Reqd RR/CSJ/ROJ 1921-F036F' 2 C 1" CV A M-16299 MSRV Aceta Air 0/C C RO NA NA ROJ-V-5 M-16062 Supply CV -
E-4 1821-F036c 2 C 1= CV A M-16299 MSRV Accus Air 0/C C RO NA' M4 ROJ-V-5 M-16062 Supply CV E-4 it21-F036N 2 C 1" CV A M-16299 MSRV Accus Air 0/C C RO NA NA ROJ-V-5 M-16062 Sigpty CV E-4 1821-F036J 2 C 1" CV A M-16299 MSRV Accus Air 0/C C RO NA NA ROJ-V-5 M-16062 Steply CV E-4 1821-F036K 2 C 1" CV A M-16299 MSRV Accue Air 0/C C RO NA NA ROJ-V-5 M-16062 Supply CV D-3 1821-F036L 2 C 1" CV A M-16299 RSRV Accus Air 0/C C to NA NA ROJ-V-5 M-16062 Supply CV E-4 1821-F037A 3 C 6" V5 A M-16062 V8 MSRV Disch C O/C R0 NA NA Note 33 M-6 1821-F0375 3 C 6" VB A M-16062 V5 MSRV Disch C O/C R0 NA NA Note 33 M-6 1821-F037C 3 C 6" VB A M-16062 VS MSRV Disch C O/C RO NA NA Note 33 M-6 1521-F037D 3 C 6" Ve A M-16062 VB MSRV Disch C O/C RO NA NA Note 33 M-6
, . _ _ ,_. . . .. . - ~~ .- - - - . - -- - - -- - - - -
+, -
,(sv% '
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4 Match Nucteer Plant Unit 1 IST Program Page No. 6 of 58 Vetve Test Table 10 - Revision O Velve P&lD/ Exercise Leeksee ST Romerks ID CC Cet . Description A/P Coord Ftmetion NP SP Freq Test Re# M/tSJ/ROJ 1821-F037E 3 C 6" VS A M-16062 V8 MSRV Disch C 0/C RO NA NA Note 33 N-6 1821-F037F 3 C 6" VB A M-16062 vs MS?V Disch C O/C R0 NA NA Note 33 M-6 1821-F037G 3 C 6" VS A M-16062 V8 MSRV Disch C O/C RO NA NA Note 33 M-6 9 1821-F037N 3 C 6" Vs A H-16062 Vs MSRV Disch C O/C Ro NA NA Note 33 M-6 1821-F037J 3 C 6" Vs A M-16062 Vs MSRV Disch C O/C RO NA NA Note 33 M-6 1821-F037E 3 C 6" vs A M-16062 Vs MSRV Disch C O/C Ro NA NA Note 33 M-6 1521-F037L 3 C 6" V5 A N-16062 Vs MSRV Disch C O/C Ro NA NA Note 33 M-6 1821-F041 1 AC 1" EFCV A H-16063 Inst EFCV o C RO LTV NA ROJ-V-3 i 8-5 i 1821-F043A 1 AC 1" EFCV A H-16063 Inst EFCV O C RO LTV NA ROJ-V-3 C-5 l 1521-F0438 1 AC 1" EFCV A M-16063 Inst EFCV O C RC LTV NA R0J V-3 C-9 1821-F045A 1 AC 1" ETCV A H-16063 Inst EFCV O C RC LTV NA ROJ-V C-5 1821-F0455 1 AC 1" EfCV A H-16063 Inst EFCV O C RO LTV NA ROJ-V-3 C-9
O O Match Nucteer Plant Unit 1 IST Program Page No. 7 of 58 C) Velve Test Table 10 - Revision 0 i Vetve . PSIO/ Emercise Leekage ST Romerts - t O- CC Cet Description A/P Coord Fisiction NP SP Freq Test Regel RR/CSJ/ROJ l' 1821 F047A 1 AC 1" EFCV A H-16063 Inst EFCV O C R0 .LTV M4 ROJ-V-3 [ F-5 1821-F0473 1 AC 1" EFCV A M-16063 Inst EFCV 0 C RO LTV NA ROJ-V-3 F-9 1821-F049A 1 AC 1" EFCV A N-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 F-5 1821-F0495 1 AC 1" EFCV A N-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 F-9 1821 F051A 1 AC 1" EFCV A M-16063 Inst EFCV O C R0 LTV NA ROJ V-3 N-16145 M-5 1821-F0518 1 AC 1" EFCV A M-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 M-16145
'l n-5 1821-F051C 1 AC 1" EFCV A u-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 .
N-16145 n-5 4
' 1821-F051D 1 AC 1" EFCV A N-16063 Inst EFCV O C RO LTV NA ROJ-V-3 n-16145 N-5 1921-F053A 1 AC 1" EFCV A M-16063 Inst EFCV 0 C R0 LTV NA ROJ-V-3 n-16145 J-5 1821-F0538 1 AC 1" EFCV A M-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 n-16145 J-5
. m f%[
Match Nucteer Plant thit 1 IST Program Page No. 8 of 58 vetve Test Table 10 - Revision 0 + Velve P&lD/ Emercise LeekeDe - ST. 'Ramerks 3D CC Cet Description A/P Coorti Function WP SP Freq Test Reqd RR/C5J/ROJ 1921-F053C 1 AC 1" EFCV A M-16063 Inst EFCV O C. R0 'LTV NA ROJ-V-3 M-16145 . J-5 1821-F053D 1 AC 1" EFCV A M-16063 Inst EFCV O C RO LTV NA ROJ-V 3 N-16145 J-5 It21-F055 1 AC 1" EFCV A H-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 J-5 1821-F057 1 AC .1" EFCV A M-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 J-5 1821.r!)59A 1 AC 1" EFCV A M-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 M-16145 H-9 1821-F059s 1 AC 1" EFCV A M-16063 Inst EFCV O C RO LTV NA R0J-V-3 M-16145 j N-9 l l 1821-F059C 1 AC 1" EFCV A H-16063 Inst EFCV O C RO LTV NA ROJ-V-3 l H-16145 H-9 1821-F0590 1 AC 1" EFCV A H-16063 Inst EFCV O C RO LTV NA ROJ-V-3 N 16145 H-9 1921-F059E 1 AC 1" EFCV A H-16063 Inst EFCV O C R0 LTV NA ROJ-V H-16145 H-9 1821-F059F 1 AC 1" EFCV A H-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 H-16145 H-9
. _ . _ . _ . . .= . - .. . . . . _ . . . _ .. . .m. _ _ . . _ _ . . _ _ _ _ _ _ _ - .
Match Nucteer Plant Unit 1 IST Program Page No. 9 of 58 Valve Test Table 10 - Revision 0 Velve P8ID/ -Exercise Leekage ST Remarts D CC ' Cet. Description A/P Coord Fametion WP SP Freq Test Reqd RR/CSJ/ROJ 1521-F059G 1 AC 1" EFCV A N-16063 Inst ETCV O C- RO LTV NA ROJ-V-3 N-16145' N-9 1821-F059N 1 AC 1" EFCV A N-16063 Inst EFCV 0 C RO. LTV NA ROJ-V-3 N-16145 N-9 1821*F059L 1 AC 1" EFCV A N-16063 Inst EFCV O C RO LTV NA ROJ-V-3 N-16145 N-9 1821-F059M 1 AC 1" EFCV A N-16063 Inst EFCV O C RO LTV NA ROJ-V-3 N-16145 N-9 1821-F0594 1 AC 1" EFCV A N-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 N-16145 l N-9 1821 F059P 1 AC 1" EFCV A M-16063 Inst EFCV 0 C R0 LTV NA ROJ-V-3 N-16145 N-9 1921-F059R 1 AC 1" EFCV A M-16063 Inst EF W 0 C RO LTV NA ROJ-V-3 N-16145 N-9 It21 F059s 1 AC 1" EFCV A N-16063 Inst EFCV O C RO LTV NA ROJ-V-3 N-16145 N-9 1821-F059T 1 AC 1" EFCV A N-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 , N-16145
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t I -
. _ . - _ . - . _ . . . _ _ .-,- ,_ .. , . _ . - . . , . . _ . -. . - . . . ._ ._. _ . . . . _ ~ . . . . . . .. . . _ . . _ . ..
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\I Natch Nucteor Plant (MI? 1 IST Program Page No. 10 of 58' Velve Test Table 10 - Revision 0 Velve P&ID/ Exercise Leekage ST~ Remarks ID CC Cat. Description A/P Coord Function - WP SP Freq Test Reqd RR/CSJ/ROJ 1821-F059U_ 1 AC 1" EFCV A N-16063 Inst EFCV O C R0 . LTV NA ' ROJ-V-3 '
N-16145 M-9 i Is21-F061 1 AC 1" EFCV A M-16063 Inst EFCV O C R0 LTV NA ROJ-V-3 J-9
-1821-F110A 3 C 10" VS A H-16062 Vs MSRV Disch C O/C Ro NA .NA Note 33 M-7 1821-F110C 3 C 10" VB A M-16062 VB MSRV Disch C O/C RO NA ' NA Note 33 M-7 1821-F1106 3, C 10" V5 A N-16062 Vs MSRV Disch C O/C to NA NA Note 33 N-7 It21-F110M 3 C 10" VB A H-16062 VS MSRV Disch C O/C RO NA NA Note 33 l N-7 1821-F111 2 A la Ao CV A M-26384 PA$s Sample Vtv c c etr CIV Yes WA E-2 1821-F112 2 A 1" AO CV A M-26384 PASS Sample Vtv C C Str CIV Yes NA E-2
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Match Nucteer Plant Unit i IST Program Page No. 11 of 58 Velve Test Table 10 - Revision 0 Velve P&ID/ Emercise Leekage ST Resorts ID CC' Cet Description A/P Coord Fmetfori NP SP Freq- Test Reqd at/CSJ/ROJ 1931-F003A 1 AC 1" EFCV A N-16066 Inst EFCV O C RO LTV NA ROJ-V-3 G-2 ' is31-F0038 1 AC 1" EFCV A M-16066 Inst EFCV O C R0 LTV NA ROJ-V-3 G-2 1831-F004A 1 AC 1" EFCV A N-16066 Inst EFCV O C RO LTV NA ROJ-V-3 G-2 1:31-F0068 1 AC 1" EFCV A N-16066 Inst EFCV O C R0 LTV NA ROJ-V-3 G-2 1s31-F009A 1 AC 1" EFCV A M-16066 Inst EFCV O C RO LTV NA ROJ-V-3 C-10 1831-F0098 1 AC 1" EFCV A M-16066 Inst EFCV O C RO LTV NA - ROJ-V-3 E-10 1931-F009C 1 AC 1" EFCV A H-16066 Inst EFCV O C RO LTV NA ROJ-V-3 0-10 1831 F009D 1 AC 1" EFCV A N-16066 Inst EFCV O C R0 LTV NA ROJ-V-3 F-10 1831 F010A 1 AC 1" EFCV A N-16066 Inst EFCV O C ' RO LTV NA ROJ-V-3 D-10 [
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1831 F0108 1 AC 1" EFCV A H-16066 Inst EFCV O C RO LTV NA ROJ-V-3 E-10 1831 F010C 1 AC 1" EFCV A H-16066 Inst EFCV O C RO LTV NA ROJ-V-3 0-10 i 1531 F0100 1 AC 1" EFCV A H-16066 Inst EFCV 0 C RO LTV NA ROJ-V-3 F-10
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- Match Nuclear Plant tinit 1 Isf Program Page No. 12 of 58-Velve Test Tabte 10 - Revision 0 Velve P&ID/ Exercise Leekage ST' Reserks ID ' CC Cet . Description A/P Coord Function WP SP Freq Test Reqd RR/CsJ/ROJ i-1831-F011A 1 AC 1" EFCV A M-16066 Inst EFCV O C R0 LTV #4- ROJ-V-3 !
l D-10 l l 1931-F0118 1 AC 1" EFCV A N-16066 Inst EFCV O C R0 LTV NA - ROJ-V-3 E 10 1831-F011C 1 AC 1" EFCV A M-16066 Inst EFCV O C RO LTV NA' ROJ-V-3 E-10 l 1831-F0110 1 AC 1" EFCV A N-16066 Inst EFCV O C R0 LTV- NA ROJ-V-3 ( F-10 1 1 1531-F012A 1 AC 1" EFCV A M-16066 Inst EFCV O C RO LTV NA ROJ-V-3 i D-10 l l 1831-F0128 1 AC 1" EFCV A N 16066 Inst EFCV O C RO LTV NA R0J-V-3 l F-10 t l l It31-F012C 1 AC 1" EFCV A M-16066 Inst EFCV O C RC LTV NA ROJ-V-3 E-10 1831-F0120 1 AC 1" EFCV A H-16066 Inst EFCV O C R0 LTV NA ROJ-V-3 l F-10 ' l 1931-F013A 1 AC 3/4" CV A H-16066 Recir Ptsp Seal O C RO CIV NA ROJ-V-6 f F-3 Wtr CIV i 1531-F0138 1 AC 3/4" CV A N-16066 Recir Ptsp Seal O C R0 CIV NA ROJ-V-6 F-3 Wtr CIV
- 1831-F017A 1 AC 3/4" CV A N-16066 Recir Pump Seat 0 C RO - CIV NA ROJ-V-6 F-2 utr CIV 1931-F0173 1 AC 3/4" CV A H-16066 Recir Ptsp Seat 0 C RO CIV NA ROJ-V-6 j F-2 Wtr CIV i
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f% Netch Nucteer Plant Unit 1 IST Program Page No. 13 of 58 Vetve Test Table 10 - Revision 0 Velve P&lD/ Exercise Leekage ST Remarks ID CC Cat -Description A/P Coord Function NP. SP Freq Test Recpl RR/CSJ/ROJ t 1931 F019 1 A 3/4" A0 GLV A M-16066 Rm Sample Sys O C Otr CIV Yes NA D-3 Ir6rd CIV it31-F020 1 A 3/4" AO GLV A M-16066 Rx Sample Sys O C Str CIV Yes NA D-1 Outbrd CIV 1831-F031A 1 s 28" NO GV A M-16066 Rectre Pump 0 C CS NA Yes CSJ-V-2 G-7 Disch Iso 1331-F0318 1 B 28" NO GV A M-16066 Recirc Puup 0 C CS NA Yes CSJ-V-2 N-7 Disch iso 1831-F0404 1 AC 1" EFCV A M-16066 Inst EFCV O C RO LTV NA ROJ-V-3 G-8 1s31-F0408 1 AC 1" EFCV A M-16066 Inst EFCV O C R0 LTV NA ROJ-V-3 M-8 1531-F040C 1 AC 1" EFCV A M-16066 Inst EFCV O C RO LTV NA ROJ-V-3 G-8 1531-F040D 1 AC 1" EFCV A M-16066 Inst EFCV O C RO LTV NA ROJ-V-3 M-8 e I
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.v N Match Nucteer Plant Unit 1 IST Program Page No. 14 of 58 Velve Test Table 10 - Revision 0 .
Velve PSIO/ Exercise Leekage ST Resorts ID ~ CC Cet Description A/P Coord Function MP SP Freq Test Reqd RR/CSJ/ROJ 1C11-F0104 2 a 1" A0 GLV A M-16065 SOV Vent viv 0 0/C etr/R0 #A Yes - M-V-3 A-5 1C11-F010s 2 3 1" A0 GLV A N-16065 50V vent vtv 0 0/C etr/R0 NA Yes M-V-3 A-6 1C11-F011 2 e 2" A0 GLV A M-16065 SOY Drain Viv 0 O/C Str/R0 NA Yes M-V-3 0-8 1C11 F035A 2 s 1" A0 GLV A H-16065 SOV Vent Viv 0 0/C Str/R0 NA Yes RR-V-3 A-5 1C11-F035s 2 s 1" A0 GLV A n-16065 50V Vent Viv 0 0/C etr/R0 NA Yes M-V-3 A-6 1C11-F037 2 8 2" A0 GLv A M-16065 SDV Drain Viv 0 O/C Str/R0 NA Yes M-V-3 C-4 1C11-NCU-114 2 C 3/4" CV A M-16064 50V HCU CV C 0 RO NA NA ROJ-V-7 A-6 Note 1,2 ( 1C11-NCU-115 2 C 1/2" CV A N-16064 Charging Water C C RO NA NA ROJ V-8 C-6 NCU CV Wote 2
.1C11-NCU-126 1 8 1" A0 GLV A H-16064 Scram Insert C 0 R0 NA No ROJ-V-9 8-4 HCU Control Vlv Note 1,2 1C11-NCU-127 1 5 3/4" A0 GLV A M-16064 Scram Disch MCU C 0 R0 NA NA ROJ-V-9 A-4 Control VLv Note 1,2 1C11-HCU-138 1 C 1/2" CV A H-16064 Cooling Water C C Wkly NA No Notes 2,3 C-4 Header MCU CV
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Natch Nucteer Piant Unit 1 IST Program Page No. 15 of 58 valve Test Tabte 10 - Revision 0 ' Vetve PSID/ Exercise Leekage ST Resorts. 10 CC .Cet Description A/P Coord Ftmetion NP SP Freq Test Reqd' RR/CSJ/ROJ , 1C41 F004A 2 0 1-1/2" Empt Act A M-16061 SLC Empt Act C 0 ISTC 4.6 ' NA NA NA i' 0-3 i .- 1C41 F0048 2 0 1-1/2" Empt Act A N-16061 SLC Expt Act C 0 ISTC 4.6 NA NA ' NA F-3 1C41-F006' 1 AC 1-1/2* CV A M-16061 SLC Outbrd CIV C O/C RO CIV ' WA ROJ-V-10~ i E-2 ' l' j IC41-F007 1 AC 1-1/2" CV A N-16061 SLC Inbrd CIV C O/C RO CIV NA ROJ-V-10 E-2 1C41-F029A 2 C 1" RV A N-16061 SLC Pump Disch C O/C Note 5' NA
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NA NA 0-6 RV i 1C41*F029s 2 C 1" RV A M 16061 SLC Ptap Disch C O/C Note 5 NA . NA NA G-6 RV 1C41 F033A 2 C 1-1/2" CV A N-16061 SLC Ptap Disch C 0 Otr NA NA NA E-5 s 1C41-F033e 2 C 1-1/2" CV A M-16061 SLC Puup Olsch C 0 Otr NA ilA NA G-5 6
Match Nucteer Plant Unit i IST Program Page No. 16 of 58' Velve Test Tabte 10 - Revision 0 Velve PRID/ Exercise Leekoge ST Remarks 10 CC Cet Description A/P Coord F metion WP. SP Freq Test Reqd .RR/CSJ/ROJ 1C51-Ball A 2 A Bett SOV A N-16070 TIP Irtrd CIV O C Otr CIV Yes ~ NA' C-3 IC51-Batt B 2 A Belt 50V A N-16070 TIP Ir6rd CIV O C Str CIV Yes NA C-3 1C51-Batt C 2 A - Bett SOV A N-16070 TIP Inbrd CIV O C etr CIV Yes NA C-3 j 1C51-sett 0 2 A Belt SOV A N-16070 TIP Irbrd CIV O C utr CIV Yes NA C-3 1C$1-F3012 2 A SOV A N-16561 TIP N2 Purge O C Qtr/R0 CIV NA RR-V-4 C-8 CIV IC51-F3017 2 AC CV A N-16561 TIP N2 Purge O R0 C CIV WA ROJ-V-11 C-8 CIV 4 1C51-Sheer A 2 AD Expl Sheer A N-16070 TIP Outbrd CIV O C ISTC 4.6 NA NA RR-V-5 C-3 1C51-Sheer a 2 AD Expl Sheer A N-16070 TIP Outbrd CIV O C ISTC 4.6 NA NA RR-V-5 C-3 IC51-Sheer C 2 AD Expl Sheer A N-16070 TIP Outbrd CIV O C ISTC 4.6 NA NA RR-V-5 i C-3 1C51-Sheer D 2 AD Expl Sheer A N-16070 TIP Outbrd CIV O C ISTC 4.6 NA NA RR-V-5 C-3 l i
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O O J Netch Nucteer Plant Unit 1 IST Programi Pope Oo 17 of 58 Valve Test Tatde 10 - Revision 0 Vetwe PRID/ -Emercise Leekoge - ST Remarks ! ID CC Cat Description -A/P Coord Fmetion NP SP Freq Test stegf RE/CSJ/20J. ! 1011-F050 2 A 1" SOW A N-1615 F!ssion Prod 0 C Str CIV Yes M_ ' E-4 Mon CIV D11-F051 2 A 1" SOW A H-1615 Fission Prod 0 C Str CIV Yes M C-5 Man CIV r 1011-F052 2 A 1" SUV A M-1615 Fission Prod 0 C Str CIV Yes M i E-5 Mon CIV l 1011-F053 2 A 1" SOY A N-1615 Fission Prod 0 C Otr CIV Yes 'M' C-6 Mon CIV . L l l l t i I- ; 1 , l I
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Match Nucteer Plant Unit 1 IST Program Pese No. 18 of 58 Velve Test Table 10 - Revision 0 Velve PEID/ Exercise Leeksge ST Remarks 1 ID CC Cet Description A/P Coord Function WP SP Freq Test Regd m/CSJ/ROJ 1E11-F003A 2 5 16" MO GV A M-16330 tm Ms Shett 0 0 Str NA Yes M D-4 Side Outtet 1E11-F003s 2 3 16" MO GV A M-16329 Rm Mx Shett 0 'O Otr NA Yes MA D-9 Side Outlet 1E11-F004A 2 e 24" MO GV A M-16330 R m Pump Suct 0 O/C Str NA Yes Note 4 F-10 Torus Iso 1E11-F004e 2 8 24" MO GV A M-16329 Rm Ptmp Suct 0 O/C Str NA Yes Note 4 ' F-3 Torus Iso i 1E11-F004C 2 8 . 24" MO GV A M-16330 R M Ptap Suct 0 0/C Str NA Yes Note 4 l F-10 Torus Iso i 1E11 F004D 2 5 24" MO GV A M-16329 RM Ptsup suct 0 0/C Str NA Yes Note 4 ( F-3 Torus Iso
- 1E11-F0054 3 C 14" CV A D-11004 RMSW Pump C O/C Str NA NA Notes 6,7 A-7 Disch CV IE11 F005e 3 C 14" CV A D-11004 R MSW Ptap C O/C Str NA NA Notes 6,7 D-7 Disch CV l
1E11-F005C 3 C 14" CV A D-11004 RNRSW Pimp C O/C Str NA NA Notes 6,7 , C-7 Disch CV i 1E11-F005D 3 C 14" CV A D-11004 R MSW Pt g C O/C etr NA NA Notes 6,7 E-7 Disch CV 1E11-F0064 2 8 20" MO GV A N-16330 R m SOC Suct c 0 Otr WA Yes NA F-8 i 1E11-F006s 2 B 20" MO GV A M-16329 RM SDC Suct C 0 Otr NA Yes WA - F-4 i
a Netch Nucteer Plant (Jnit 1 IST Program Pese No. 19 af 58 Velve Test Tebte 10 - Revision 0 Velve , P&ID/ Esercise Leekage ST . Remarks ID CC Cet Description A/P Coord Ftmetion NP SP Freq Test Reqd RR/CSJ/ROJ 1E11-F006C 2 5- 20" MO GV A N-16330 RNR SDC Suct C 0 Str NA Yes NA - F-11
- 1E11 F0060 2 s 20" MO GV A N-16329 RM SOC Suet c 0 Otr NA ' Yes NA
-F-2 1E11-F007A 2 3 4" MO GV A H-16330 RM Ptsup Min 0 0/C Str NA Yes Note 4 E-T Flow Torus Iso 1E11 F0075 2 3 4" Mo GV A H-16329 RM Ptsp Min 0 0/C Str NA Yes Note 4 D-6 Flow Torus Iso
.1E11-F008 1 A 20= no GV A H-16329 RNR SDC Outbrd C O/C CS PIV/CIV Yes CSJ-V-3 0-2 CIV 1E11-F009 1 A 20" MO GV A H-16329 RM SDC Irbrd C O/C CS PIV Yes CSJ-V-3 D-2 PIV 1E11-F011A 2 3 4a no CV A H-16330 RNR Cond Disch C C Str NA Yes Note 4 D-3 to Torus 1E11-F0118 2 8 4= no GV A M-16329 RNR Cond Disch C C etr NA Yes Note 4 D-10 to Torus 1E11-F015A 1 A 24" MO GV A H-16330 LPCI Outbrd CIV C O/C CS PIV/CIV Yes CSJ-V-4 C-8 1E11-F0158 1 A 24= no GV A H-16329 LPCI Outbrd CIV C O/C CS PIV/CIV Yes CSJ-V-4 C-5 1E11-F016A 2 A 16= M0 GLV A N-16330 Crat Spray C O/C etr CIV Yes NA B-9 Outbrd CIV 1E11-F0168 2 A 16" MO GLV A N-16329 Cmt Spray O/C C Str CIV Yes NA 8-5 Outbrd CIV
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a Match Nucteer Plant Unit 1 IST Program Pege No. 20 of 58 l L-Velve Test febte 10 - Revision 0 l Velve. PSID/' Exercise Leekage ST . Romerts l .ID CC Cet Description A/P Coord Fmetion WP SP Freq Test Reqd - Rt/CSJ/a0J l l 1E11-F017A 1 B 24" MO GLv A M-16330 LPCI o 0 otr NA .Yes. NA C-8 1E11-F0173 1 -3 24" MO GLV A' M-16329 LPCI O O Otr NA Yes 'NA - i C-5 1E11-F021A 2 3 16" MO GV A n-16330 Cret Spray C O/C etr M Yes NA 3-11 l 1E11-F0218 2 8 16" MO GV A M-16329 Crat Spray C O/C Str NA Yes NA l e-3
- 1E11 F0244 2 8 16" MO GLV A N-16330 SPC C O/C etr NA Yes Note 4 i C-7
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- 1E11-F0248 2 5 16" MO GLV A M-16329 SPC C O/C Str NA Yes Note 4 i
C-7 I i 1E11-F025A 2 C 1" RV A N-16330 LPCI RV C O/C Note 5 NA NA Note 4 ! C-8 1E11-F0258 2 C la RV A n-16329 LPCI RV C c/C Note 5 NA NA Note 4 9-5 l 1E11-F026A 2 3 4" MO GV A M-16330 Cond Disch to C C Otr NA Yes Note 4 D-3 RCIC 1E11-F0268 2 5 4" MO GV A M-16329 Cond Disch to C C Otr NA Yes Note 4 D-11 RCIC
.1E11 F027A 2 a 6* MO GLV A N-16330 S g Peot Spray C O/C Str NA Yes NA C-8 '
1E11-F0275 2 B 6" MO GLV A M-16329 S w Poot Spray C O/C etr NA Yes #4 C-5
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bh hm U Match Nucteer Flant Unit 1 IST Program Page No. 21 of 58 Valve Test Tabte 10 - Revision 0 vetve P&ID/ Exercise Leakege ST Remarks
'10 CC Cet Description A/P Coord Ftmetion NP SP Freq Test Reqd M/CSJ/ROJ 1E11-F0284 2 A .16" MO GV A M-16330 Sapp Pool spray C O/C Str CIV Ves NA l B-8 Outbrd CIV t
! 1E11-F028e 2 A 16" MO GV A H-16329 SLpp Poot Spray C O/C Str Civ Yes MA B-6 Outbrd CIV IE11 F029 2 C 1" RV A N-16329 R M Ptap Suc RV C O/C Note 5 NA NA Note 4 E-1 1E11-F030A 2 C t= RV A n-16330 RMR Ptap Sue RV C O/C Note 5 NA NA Note 4 F-9 1E11-F030s 2 C 1" RV A u-16329 anR Puup Sue RV C O/C Note 5 NA NA Note 4 F-4 1E11-F030C 2 C 1" RV A H-16330 RNR Puup Sue RV C O/C Note 5 NA NA Note 4 F-11 1E11-F0300 2 C 1" RV A M-16329 RNR Ptsp Sue RV C O/C Note 5 NA NA Note 4 F-2 TE11-F031A 2 C 20" CV A n-16330 RMR Ptsp Olsch C O/C Otr NA NA Notes 6,7 N-6 1E11-F031B 2 C 20" CV A H-16329 RNR Ptsp Disch C O/C Otr NA NA Notes 6,7 n-7 1E11-F031C 2 C 20" CV A H-16330 RM Ptsp Disch C O/C Str NA NA Notes 6,7 N-10 1E11-F031D 2 C 20" CV A H-16329 RMR Pump Disch C O/C Str NA NA Notes 6,7 M-3 1E11-F040 2 8 4" MO GLV P H-16329 RNR to RW Drain C C NA NA No Note 8 E-5
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7 Metch Nueteer Piont Unit 1 IST Proerse Page me. 22 of 58-Velve Test Table 10 - Revision 0 Vetve' PSIO/ Exercise Leekage ST Reserks ID CC Cet Description A/P Coord Ftmetion NP SP Freq- . Test Reqd RR/CSJ/WOJ 1E11-F046A - 2 C. 3" CV A M-16330 Rm Min Flow DIE - C O/C NA m Notes 9,13 M-7 Line - ROJ-V-12
'1E11-F0468 2 C. 3" CV A N-16329 RNR Min Ftou O/C C DIME NA NA Notes 9,13 - [
M-6 Line ROJ-V-12 1E11-F046C 2 C 3" CV A n-16330 RnR Min Flow C DIE O/C NA NA Note 9 N-11 Line ROJ-V-12 ' 1E11-F046D 2 C 3" Li A N-16329 R m Min Flow C O/C DIME - NA NA . Note 9 N-3 Line ROJ-V-12 1E11-F047A 2 a 16" M0 GV A N-16330 Rm 4x Shett o o otr NA Yes NA t E-6 Side Intet ' l 1E11 F047B 2 a 16= MO GV A n-16329 mm um Shelt o o otr NA Yes NA ' E-T Side Intet i 1E11*F0484 2 8 24" MO GLV A M-16330 Rm Mx Shett o o/C etr NA Yes NA [ 0-6 Side typass t IE11-F048s 2 8 24" MO CLV A M-16329 Rm Mx Shett 0 0/C etr NA Yes NA i 0-7 Side Bypess 1E11-F049 2 a 4" no GLV P M-16329 RM to RW Drn C C NA NA No Note 8 l E-5 1E11-F0504 1 AC 24" CV A M-16330 LPCI PIV C O/C See RR-V-6 PIV NA RR-V-6 C-10 1E11-F0508 1 AC 18" CV A M-16329 LPCI PIV C O/C.
- See RR-V-6 PIV NA RR-V-6 l C-4 -
l 1E11-F055A 2 C 4= RV A H-16330 mm nu Shett RV C o/C- Note 5 NA NA Note 4 F5 l I
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4 ._ _ . ._ . _ . . . . . . . _ . . . .. . . . . . . . . ... . . L o Match Nucteer Plant Unit 1 IST Program O Page No. 23 ef 58 O Velve Test Table 10 - Revision 0 Vetwe P8tD/ Exercise Leekage. ST Reiserfts ID CC Cet Description A/P Coord Ftmetion NP SP Freq Test Reqd- RR/CSJ/WOJ ! 1E11-F055e 2 C 4" RV A M-16329 R m Mx Shett RV C O/C Note 5 NA NA ' Note 4 E-9 l 1E11-F065A 2 8 24" A0 SFV P M-16330 Rm Puup Suet 0 0 NA NA No Note 8 E-10 Maint , IE11-F0658 2 a 24= A0 eFV P M-16329 RMR Pump Suet 0 0 NA NA No . Note 8 F-3 Maint IE11-F065C 2 5 24" A0 8FV P M 16330 R m P g Suet 0 0 NA NA No Note 8 E-10 Maint 1E11-F0650 2 8 24" Ao sFV P M-16329 RNR Puup Suct 0 0 NA NA No Note 8 F-3 Melnt 1E11-F0684 3 3 10" MO sett viv A H-16330 km Mx Ser Wtr C O/C etr NA Yes NA M-6 Disc i 1E11-F0688 3 5 10" MO Bett Vtv A M-16329 R m Ma Ser Wtr C O/C Str NA Yes NA H-8 Disc 1E11-F073A 2 0 10" MO GV A M-16330 k m SW to R m C O/C etr NA Yes NA G-2 Crosstle I 1E11-F0738 2 B 10" MO GV A M-16329 RMR$v to RM C O/C Otr NA Yes NA G-9 Crosstle 1E11 F075A 2 a 10 MO GV A M-16330 RMSU to Rm C 0/C etr NA Yes NA j G-4 Crosstle IE11-F0755 2 B 10" M0 GV A M-16329 RMR$W to RM C O/C etr NA Yes NA G-9 Crosstle l 1E11-F078A 2 C 10" Test CV A M-16330 RMRSv to R M C O/C DIME NA NA Note 9,10 D4 Crosstle , l
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l O O O {' Match Nucteer Plant Unit 1 IST ' Program -Page No,'24 of 58 Velve Test Tabte 10 - Revision 0 - Wolve' P&t0/ Exercise Leekage ST Remarks ID CC .- Cet Description A/P Coord Fmction WP - SP Freq Yest Reqd RR/CSJ/WOJ 1E11-F0785 2 C 10" Test CV A N-16329 RlutSW to Rfut . C O/C DIME NA NA Note 9,10 D-9 Crosstle 1E11-F091A 2 3 6" MO GLV P. N-16330 Steen Line to C C NA NA No Note 8 E-2 RINt Na Shutdom 1E11-F0918 2 5 6" MO GLV P N-16329 Steen Line to C C NA NA No Note 8 E-11 Rfut Na Shutdown 1E11-F097 2 C 3" RV A N-16329 Steen Line RV C O/C Note 5 NA NA Note 4 D-11 1E11 F103A 2 B 1" MO GLV A N-16330 Rent Na vent Iso C C Str NA Yes Note 4 E-5
' 1E11-F1038 2 8 1" MO GLV A N-16329 RINt Nx Vent Iso C C Str itA Yes Note &
E-9 1E11-F122A 1 A 1" A0 Plus P N-16330 Passive PIV C C NA PIV No Note 8 D-10 TE11-F1223 1 A 1" A0 Plug P M-16329 Passive PlV C C NA PIV No Note 8 D-4 1E11-F1264 2 C 2" Stop CV A N-16328 Maintain RINt 0/C C Otr NA NA Note 11 E-6 Water Level 1E11-F1268 2 C 2" Stop CV A N-16328 Maintain RNR 0/C C etr NA NA Note 11 E-4 Water Levet a
O O . J Match Nucteer Plant Imit 1 IST Program Page No. 25 of 58 Velve Test Table 10 - Revision 0 i Vetve P&ID/ Exercise Leekoge ST Remarks ID CC Cet Description A/P Coord Tunction WP SP Freq Test Reqd~ RR/CSJ/H0J 1E21-F001A 2 5 16" MO GV A M-16331 CS Puup Suct 0 O/C - Str NA Yes Note & T R-8 Iso 1E21-F0013 2 3 16" MO GV A M-16331 CS Puup suct 0 0/C Str NA Yes ' Note 4 J-8 Iso 1E21 F003A 2 C 12" CV A M-16331 CS Ptap Disch Otr C O/C NA NA Note 7,12 F-9 1E21 F0038 2 C 12" CV A N-16331 CS Ptap Disch O/C ' C Str NA- NA Note 7,12 F-11 1E21-F004A 1 B 10" MO GV A M-16331 CS outbrd 0 0 Str NA Yes . NA I E-7 Injection 1E21-F0048 1 3 10" MO GV A N-16331 CS Outbrd O O Otr NA Yes NA j E-T Injection 1E21-F005A 1 A 10" MO GV A H-16331 CS Inbrd C 0/C CS PIV/CIV Yes - CSJ-V-5 E-6 Injection 1E21-F0058 1 A 10" MO GV A M-16331 CS Irbed C O/C CS PIV/CIV Yes CSJ-V-5 B-6 Injection 1E21-FC06A 1 AC 10" CV A M-16331 CS Injection C O/C RO PIV NA ROJ-V-13 D-4 1E21-F0068 1 AC 10" CV A H-16331 CS Injection C O/C RO PIV NA ROJ-V-13 l C-4 , 1E21-F012A 2 C 2" RV A H-16331 CS Ptsp Disch C O/C Note 5 NA NA NA D-9 RV 1E21 F0128 2 C 2" RV A M-16331 CS Ptsp Disch C O/C Note 5 NA NA NA E-10 RV
s Match Nucteer Plant Unit.1 IST Program - . Pese No. 26 of 58 Velve Test Table 10 - Revision 0 - Volve P&lD/ Exercise Leekage ST Reserks ID CC. Cat Description A/P Coord Function NP SP Freq Test Reqd RE/CSJ/ROJ 1E21-F015A 2 s 10= MO GLV A M-16331 Core Spray Test C C Str NA Yes. ' Note 4 0-8 Bypass Iso 1E21-F015s 2. 5 10" M0 GLV A M-16331 Core Sprey Test C C' Otr NA Yes' . Note'4 C-8 Bypess Iso 1E21-F0184 1 AC 1" EFCV A M-16331 Inst EFCV O C RO LTV . NA ROJ-V-3 A-4 1E21 F0188 1 AC 1" EFCV A N-16331 Inst EFCV O C RO LTV NA ROJ-V-3 . A-4 i 1E21-F018C 1 AC 1" EFCV A M-16331 Inst EFCV O C R0 LTV NA ROJ-V-3 A-4 1E21-F019A 2 5 16" A0 BFV P N-16331 Cs suct 0 0 NA NA No Note 8 M-6 1E21-F019e 2 8 16" Ao eFV P M-16331 CS suct 0 0 NA NA No Note 8 J-6 1E21-F031A 2 8 3" Mo CV A M-16331 CS Puup Min 0 O/C Str- NA Yes NA F-9 Flow IE21-F031e 2 a 3" Mo GV 4 N-16331 CS Puup Min 0 O/C Qtr NA Yes WA F-10 Flow 1E21-F032A 2 C 1" RV A u-16331 CS Suct RV C O/C Note 5 NA NA NA M-9 1E21-F0328 2 C 1" RV A n-16331 Cs suet RV C O/C Note 5 NA NA NA .. M-11 1E21-F036A 2 C 3" CV A H-16331 CS Min Flow Iso C O/C DIME NA NA Notes E-9 4,9,13 ROJ-V .-
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Natch &seteer Plant Unit 1 IST Program Pope No. 27 of 58 Velve Test Table 10 - Revision 0 Volve P810/ Exercise- - Leekage ST - Reserks - l 10 . CC : Cet- Description A/P -Coord Function . NP SP Freq Test Regd RR/CSJ/ROJ 1E21-F0368- 2 C 3" CV A N-16331 CS Min Flow Iso C- O/C DINE NA NA Notes E 4,9,13-ROJ-V-28 l 1E21-F037A 1 A 1" A0 Plug Vlv P N-16331 Possive C C NA ' PIV - No- Note 8 L 0-4 Isolation 1E21-F0373 1 A la A0 Plug Viv - P N-16331 Passive C C NA - PIV No Note 8 5-4 Isotation-l 1E21 F0404 2 C 1-1/2" Stop CV A N-16328 Neinteln CS 0/C C Str NA NA Note 11 E-6 Water Level 1E21-F040s 2 C 1-1/2" Stop CV A N-16328 Neintain CS O/C' C Otr NA NA Note 11 E-4 Water Level 1E21-F044A 2 C 2" Stop CV A N-16328 Jockey Ptap O C RO NA NA ROJ-V-14 F-5 sypeos Iso Note 4 1E21-F0448 2 C 2" Stop CV A N-16328 Jockey Pump O C RO NA NA ROJ-V-14 F-5 typass Iso Note 4 i 9 I - 4 l _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ . . _ _ , - 2 -_ - a :-- - - - _ - , w . - - = _c__---_--_ _e_-_-- - - _ . -__ - - - . _
o 0-( ( Netch Nucteer Plant tinit 1 IsT Progree Pese No. 28 (f 58
~ Velve Test Tetde 10 - Revision 0
.volve - PSIO/-- Exercise. La"heys ST' ' Reenrks.
10 - CC Cet Description A/P Coord Fametion NP - SP 1 . Frog- Test ~ kegd f ER/tSJ/90J 1E41-D003- 2 9 '16" a0 A N-16333 Turbine Enhaust C- 0/C' Note 14 NA' NA : NA - F-7 m
'1E41-3004 .2 ~ 9' 16" AD A N-16333 Turbine Emhouet C :O/C' - Note'14 ~ NA NA NA1 G-7 RO i 1
1E41 F001- 2 3 10" M0 GV A N-16332 steen sippty C 0 Otr- NA- Yes - NA - E Shutoff
, 1E41-F002 1 A .10" MO GV A N-16332 steen sigpty 0 0/C CS - CIV Yes RR-V-1 C-3 tribrd CIV CsJ-V-6 1E41-F003 1' A .10" MO GV A N-16332 steen supply 0 0/C Str CIV Yes NA C-4 Outbrd CIV 1E41*F004 2 B 16" MO GV A N-16332 Pump suc from 0 0/C Str NA Yes m 0-9 Coruf stor 1E41-F005 2 - AC 14" CV A N-16332 Puup Disch C O/C - Otr PIV- NA Note 1$'
E-6 1E41-F006 2 A 14" MO GV A N-16332 Pump tribrd O/C Otr . C PIV/CIV Yes- . MA - E-5 Disch Iso-
- 1E41-F007 2 'B 14" MO GV A N-16332 Pimp outbrd 0 0 Str NA Yes NA E-5 Disch 1E41-F008 2 B 10" MO GLV A N-16332 Ptap Test C- C Str NA Yes NA.
D-7 Bypass 1E41-F011 2 B 10" No GV A M-16332 Pimp Test ' C C ~ Otr NA ~ Yes Note 16 - C typees 1E41-F012 2- 3 4" MO GLV A N-16332' Ptap Min Flow C O/C Str ' NA Yes -Note 4-F-7 Irtrd Iso
O O Natch Nutteer Plant Unit 1 IST Program O Page No. 29 cf 58 . Velve Test Table 10 - Revision O Vetve P&lD/ Exercise Leekoge ST Resorts ID CC Cet Description A/P Coord Fimetion' NP SP Freq Test Reqd RR/CSJ/ROJ 1E41-F019 2 C 16" CV A H-16332 Pump Sue Cond C 0 etr NA NA Note 7 D-9 Stg 1E41-F020 2. C 2x1" RV A H-16332 Pump Suct RV C O/C Note 5 NA NA NA D-8 1E41-F021 2 C 12" Stop CV A N-16332 Turb Exh Irbrd C O/C Note 15 NA NA 90J-V-15 G-3 Iso Notes 4,17 1E41-F022 2 C 2" Stop CV A N-16332 Turb Exh Drn C O/C DIME NA NA ROJ-V-16 G-4 Iso Notes 4,9,17 1E41-F024A 1 AC 1" EFCV A H-16332 Inst EFCV O C R0 LTV NA ROJ-V-3 C-4 1E41-F0248 1 AC 1" EFCV A N-16332 Inst EFCV O C RO LTV NA ROJ-V-3 0-4 I i 1E41-F024C 1 AC 1" EFCV A H-16332 Inst EFCV O C RO LTV NA ROJ-V 3 C-4 1E41-F024D 1 AC 1" EFCV A H-16332 Inst EFCV O C R0 LTV NA ROJ-V-3 D-4 1E41-F028 2 5 1" A0 GLV P H-16332 Drain Pot Drain 0 0 NA NA No Note 8 G-13 1E41-F029 2 s 1" A0 GLV P N-16332 Drain Pot Drain 0 0 NA NA No Note 8 G-13 1E41-F040 2 C 2" CV A M-16332 Turb Enh Drn C O/C DIME WA NA R0J-V-17 G-5 Iso Notes j- 4,9,15 1E41-F041 2 5 16" MO GV A H-16332 Puup Suc Styply C 0 Otr NA Yes WA D-8 _ _ _ _ _ _ _ _ _ . _ _ ._______________________ ________________ _ __ _________ ________ ______ _____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -- __ _J
O O O Match Nucteer Plant Unit 1 IST Program : Pope No. 30 of 58 volve Test Table 10 - Revision 0 vetve P&lD/ Exercise Leekage ST Romerks-ID CC Cet Description A/P Coord F mction WP .SP Freq Test Reqd RR/CSJ/ROJ 1E41-F042 2 -B 16" NO GV A M-16332 Pup Sue Torus C O/C etr NA- Yes Note 4 J-5 Outbrd too 1E41 F045 2 C 16" CV A M-16332 Pig Suct C 0 DINE NA NA RR-V-7 J-7 Note 9 1E41-F066 2- C 4" CV A M-16332 Pu p Min Flow C O/C DINE NA NA ROJ-V-1P F-8 Outbrd Iso Notes 4.9
-1E41-F068 2 C 2* CV A M-16333 Lube 011 C. 0 OINE NA NA Note 9 M-9 Cooting Wtr Return CV 1E41 F069 2 C 20" CV A H-16332 Turb Enh Outbrd C O/C Note 15 NA NA ROJ-V-19 G-4 Iso Note 4 1E41-F050 2 C 2* RV A M-16333 Lube 011 Cooter C O/C Note 5 NA NA NA M-8 RV IE41-F051 2 B 16" A0 BFV A H-16332 Pwp Suc forus 0 0/C etr NA Yes Note 4 J-4 Irted Iso 1E41 F052 2 C 2" CV A M-16333 serametric cond C C Str NA NA Note 18 M-10 Ptsp Disch 1E41-F057 2 C 2" CV A H-16333 Lthe oil C 0 DINE NA NA Note 9 M-10 Cooting Wtr Return CV 1E41-F059 2 8 2" NO GLV A M-16333 Turb Lthe 011 C 0 Otr NA Yes NA F-8 Cooling 1E41 F102 2 C 1" CV A H-16332 Vacuus RV C O/C RO NA NA ROJ-V-25 G-2 1E41-F103 2 C 1" CV A M-16332 Vacuun RV C C/C RO NA NA ROJ-V-25 G-2
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_ _ . _. . _ . _ . . _ . _ . _ _ _ _ _ _ . _ . . . . _ . _m_ . . . j i i l Natch Nucteer Plant Unit.1 IST Program Page No. 32 of 58 ! Valve Test Tetde 10 - Revision 0 - l [ Volve PEID/ Emercise Leeksge Si Romerks l ID CC Cet Description A/P Coord Function MP SP Freq Test Reqd RR/CSJ/ROJ l 1E51 F001 .2 C 10" Stop CV A M-16334 Turb Enh Ir6rd C O/C Note 15 NA NA ROJ-V-20 G-5 Iso Notes 4,17 1E51-F002 -2 C 2" Stop CV A M-16334 Turb Enh Drn C O/C RO NA NA ROJ-V-21 G-6 Torus Iso Notes 4,17 1E51 F003 2 3 6" A0 SFV A N-16334 Po p Suct Torus 0 0/C Otr NA Yes Note 4 J-6 Irbrd Iso 1E51-F007 1 A 4" M0 GV A H-16334 Steen Supply 0 C CS CIV Yes RR-V-1 C-5 Irbrd CIV CsJ-V-6 1E51-F008 1 A 4" MO GV A M-16334 Steen Supply 0 C Str CIV Yes NA C-6 Outbrd CIV 1E51 F010 2 8 6" M0 GV A M-16334 Ptap Suc from 0 O/C Otr NA Yes Note 16 C-8 Cond Stor l 1E51-F011 2 C 6" CV A N-16334 Pump Suc from C 0 Otr NA NA Note 16 D-8 Cond Stor 1E51-F012 2 B 4" M0 CV A H-16334 Ptap Outbrd 0 0 Otr NA Yes Note 16 E-8 Disch 1E51-F013 2 A 4" MO GV A H-16334 Ptsp Irbrd C O/C Otr PIV/CIV Yes NA E-6 Disch Iso 1E51-F014 2 AC 4" CV A M-16334 Puup Disch C O/C Otr PIV NA Note 15 E-T 1E51-F017 2 C la RV A H-16335 Ptsp Suct RV ' C O/C Note 5 NA NA Note 16 C-6 r 1E51-F019 2 8 2" M0 GLV A M-16334 Ptap Min Flow C O/C Otr NA Yes Note & F-7 Irbrd Iso 3
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3 V O*N Om,- Natch Nucteer Plant Unit 1 IST Program Pese No. 33 of 58 Vetve Test Table 10 - Revision 0 Vetve P&lD/ Exercise Leeksge ST Dauerks ID CC Cet Description A/P Coord Function WP SP Freq Test Reqd RR/C5J/ROJ. 1E51 F021 2 C 2" CV A N-16334 Puup Min Floer C O/C DIME WA NA ROJ-V-22 F-8 Outbrd Iso . Notes 4,9 1E51-F022 2 B 4" MO GLV A N-16334 Puup Test C C Otr NA Yes Note 16 C-6 Bypees 1E51-F028 2 C 2" CV A N-16334 Turb Exh Drn C C RO NA NA ROJ-V-23 G-7 Note 4 1E51-F029 .2 5 6" MO GV A N-16334 Puup suc C 0/C Str WA Yes Note 16 D-8 shutoff 1E51-F030 2 C 6" CV A N-16334 Puup Suct C 0 DINE NA NA Notes 16, J-7 19 1E51 F031 2 8 6" MO GV A N-16334 Pump Suct focus C O/C Str NA Yes Note 4 J-6 Outboerd Iso 1E51-F040 2 C 10" CV A M-16334 Turb Exh Outbrd C O/C Note 15 NA NA ROJ-V-24 G-5 Iso Note 4 1E51 F044A 1 AC 1" EFCV A N-16334 Inst EFCV O C R0 LTV 'A N ROJ-V-3 B-5 1E51-F0448 1 AC 1" EFCV A N-16334 Inst EFCV O C R0 LTV NA ROJ V-3 D-5 1 1E51-F044C 1 AC 1" EFCV A M-16334 Inst EFCV O C R0 LTV NA ROJ-V-3 3-5 1E51-F0440 1 AC 1" EFCV A N-163M Inst EFCV O C RO LTV NA ROJ-V-3 D-5 r 1E51 F045 2 3 4" MO GLV A M-16335 Steam supply C O/C etr NA Yes Note 16 D-11 Shutoff i i - - _ _ . - _ _ _ - _ . _ _ - _ _ = _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - - - - _ _ _ - _ _ . - . - . . . , . . . . . - , -. - - . - . - - - . - - .
I - ( s-Natch Nucteer Plant thit 1 IST Program Pope No. 34 of 58 l Velve Test Tabte 10 - Revision 0 l [ Vetve PSID/ Emerclee Lookege - ST' Remarks l 10 CC Cet Description A/P Coord Function . WP SP Freq Test Respi RR/CSJ/90J
'1E51-F066' 2 g 2* MO GLV A N-16335 Turt Like 011 0 C etr NA Yes Note 16 E-6 Cooling 1E51-F067. 2 C 2* CV A N-16335 Like 05L C C DIME WA NA Notes 16, G-8 Cooting Utr 19 Peturn CV 1E51-7102 2 C 1 1/2" CV A N-16334 vacuun RV C O/C 90 NA NA Notes 16, F-5 20 1E51 F103 2 C 1 1/2" CV A N-16334 vacuun RV C O/C Ro NA NA notes 16, F5 20 1E51 F104 2 A 1 1/2" M0 GV A N-16334 vec RV outbrd 0 0/C etr CIV Yes WA G-5 Torus CIV 1E51-F105 2 A 1 1/2* MO GV A M-16334 Vec RV Inbrd 0 0/C etr CIV Yes NA G-5 forus CIV
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p m . L) ' Netch mucteer Plant Unit 1 IST Program Pese No. 35 of 58 Velve Test Table 10 - Revision 0 , Velve PSID/ Exercise Leekage ST Reserks. ID CC - Cet Description A/P Coord Function WP SP Freq Test Reqd RR/C5J/ROJ 1811-F003 2 A 3" A0 CV A M-16176 W Ftr Drns CIV O C Str CIV Yes M 5-3
'L 1G11-F006 2 A 3" A0 GV A M-16176 W Ftr Drns CIV O C Str CIV Yes NA I
. B-3 .l 1G11-F019 2 A 3" A0 GV A M-16176 W EgJip Drns O C Str CIV Yes MA E-3 CIV 1G11-F020 2 A 3" A0 CV A M-16176 W Equip Drne O C Str CIV Yes un E-4 CIV
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G- , - Netch Nucteer Plant Unit 1 IST Program Pope lee. 36 of 58 Velve Test Table 10 - Revision 0 Velve PSID/ Exercise Leekage ST Romerks f ID CC Cat ' Description A/P Coord ' Function IIP SP -Freq - Test _ Respi RR/CSJ/ROJ-1s31-F001 1 A 6" 310 GV A N-16188 RWCU Pimp Suc 'O C CS CIV Yes. CSJ-V-7 S-2 Irted CIV ' 1G31 F004 1 A 6" MO GV A N-16188 RWCU Pi g Suc 0 C CS CIV Yes CSJ-V-7 B-3 Outbrd CIV 1G31-F039 1 AC 4" CV A N 16188 RUCU Disch CIV 0 C R0 CIV No ROJ-V-26 A-4 1G31-F203 1 AC 3" CV A M-16188 RWCU Disch CIV O C R0 CIV No ' ROJ-V-26 ; A-4
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L O . O Netch Nucteer Plant thilt 1 IST Program Page No. 37 of 58 Velve Test Tabte 10 - Revision 0 Velve PalD/ Emerefoe. Leekage ST Resorts 10- CC Cet Description A/P Coord . Ftsiction NP. SP Freq Test ~ Negi m/CSJ/NoJ 1G51 F011 2 5 3* Ao cont Viv P N-16135 Passive Cont C C m m No Note 4,8 C endy 1G51-F012 2 5 3* Ao cent vtv P N-16135 Passive Cont C C m m No Note 4,8 C-5 andy
.1G51-F013_ 2' B 3* Ao cent viv P N-16135 Possive cent c c m m No Note 4,8 c-2 andy 1G51-F021 2 3 3* Ao cent Viv P N-16135 Passive cent c c m m No Note 4,8 C-1 andy i
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N i i Natch Nucteer Plant Unit 1 IST Progree -Page No. 38 of 58 ' valve Test Tebte 10 - Revision 0
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.Velve' PSID/ Emercise Leekage
;y ST Reemrks ID CC Cet Description A/P Coord F mction WP SP Freq Test Reqd RR/CSJ/ROJ TP21-F353 2 A 2" Men GV P n-16015 Possive CIV LC C NA CIV No M f F-7 r
e IP21 F420 2 A 1-1/2" Men CV P N-16015 Passive CIV LC- C P!A CIV No NA F-8 i I b 9 9 9 t r f r n 5 v i i I l i [ i 6 I i
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_ _ . . -._ m ._. . . . . . . . _ . . m . . _ _ _ _ .. _ _ Match Nucteer Plant IMit 1 IST Program 2 Pese No. 39 of 58 Velve Test Tabte 10 - Revision 0 Vetwe . PRID/ Exercise Leekeye- ST- Remarks
'ID CC Cet Description A/P Coord Ftmetton IIP SP Freq Test Reqd RR/CSJ/ROJ
. 1P33-F002 2 A 1" A0 GLV A n-16276 N2 8 02 Analy 0 0/C -CIV etr Yes M B-4 CIV 1P33-F003 2 A 1" A0 GLV A M-16276 M2 & 02 Anoty C O/C etr CIV Yes MA D-4 CIV 1P33-F004 2 A 1" AO GLV A M-16276 M2 & 02 Analy 0 0/C otr Civ Yes NA E-4 CIV 1P33-F005 2 A 1/2" SO GLV A N-16276 N2 & 02 Ansty 0 0/C ' otr CIV Yes MA C-4 CIV
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- 1P33-F006 2 A 1" A0 GLV A M-16276 N2 & 02 Anoty C O/C etr CIV Yes MA G-4 CIV 1733-F007 2 A 1" A0 GLV A H-16276 M2 & 02 Anoty 0 0/C otr CIV Yes mA-M-4 CIV
'1333-F010 2 A 1" A0 GLv A n-16276 N2 & 02 Analy 0 0/C Otr CIV Yes MA s-5 CIV i
1P33-F011 2 A 1" A0 GLV A M-16276 H2 & 02 Analy C O/C etr CIV Yes NA 0-5 CIV 1P33-F012 2 A 1" A0 GtV A H-16276 H2 & 02 Analy 0 0/C Str CIV Yes' NA E-5 CIV 1P33-F013 2 A 1/2" SO GLV A M-16276 M2 & 02 Analy 0 0/C etr CIV Yes MA C-4 CIV 1P33-F014 2 A 1" AO GLV A H-16276 H2 & 02 Analy C O/C Otr CIV Yes MA G-5 CIV 1P33-F015 2 A 1" A0 GLV A M-16276 H2 & 02 Anoty 0 0/C Otr CIV Yes NA H-5 CIV
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J . Netch NucIeer Ptont Unit 1 IST Prograut- Page No. 40 of 58 ' Velve Test Table 10 - Revision 0 volve P&ID/ Exercise Leekage i ST Romerks ID CC Cat Description A/P Coord Function NP SP Freq Test Reqd RR/CSJ/ROJ 1P41-F035A 3 5 2" A0 GLV A n-16011 MPCI Ptap Re C 0 Str NA Yes M-V-8 B-9 Cooter 1P41-F0358 3 3 2" AO GLV A M-16011 MPCI Pump to 0 C Str NA -Yes M-V-8 C-9 Cooler 1P41-F0364 3 5 3" A0 GLV A n-1601i RM & CS Ptap C 0 Otr NA Yes RR-V-8 D-9 Pm Cooter i 1P41-F0368 3 5 3" A0 GLV A M-16011 R M & CS Ptap C 0 Otr NA Yes RR-V-8 D-9 Re Cooler 1P41 F037A 3 8 1-1/2" A0 GLV A M 16011 RM Pig Cooler C 0 Otr NA Yes M-V-8 M-8 ' 1P41-F0375 3 e 1-ii2" A0 GLV A N-16011 RM Ptap Cooter C 0 Otr NA Yes RR-V-8 E-9 1P41 F037C 3 5 1-1/2" A0 GLV A N-16011 RM Pimp Cooter C 0 Str NA Yes RR-V-8 J-8 1P41-F037D 3 8 1-1/2" A0 GLV A H-16011 R M Pump Cooter C 0 Otr NA Yes RR-V-8 E-9 1P41-F039A 3 5 3" A0 GLV A M-16011 R M & CS Ptap C 0 Otr NA Yes RR-V G-8 Rm Cooler s 1P41 F039s 3 5 3" A0 GLV A N-16011 R M & CS Pump C 0 Otr NA Yes RR-V-8 G-8 Rm Cooter 1P41-F040A 3 e 1 1/2" A0 GLV A M-16011 RCIC Pump Rm C 0 Otr NA Yes Notes 16 M-2 Cooler Cont 21 IT41-F040s 3 5 1 1/2" A0 GLV A N-16011 RCIC Ptmp Rm C 0 Otr NA Yes Notes 16 n-2 Cooler Cont 21
_ . _ _ . - . -- - -+ mW O O - Match Nucteer Plant tinit 1 IST Program Pese No. 41 of 58 Velve Test Tetde 10 - Revision 0 Velve P&lD/ Exercise Leekage ST Remarks
~10 CC Cat Description A/P Coord Fametion WP SP Freq
. Test Reqd RR/CSJ/WOJ 1P41-F049 2 A 8" MO GV A N-16011 Dryvet! Air o C CS CIV Yes CSJ-V-8 F-6 Cooler CIV
- 1P41-F050 2 A 8" MO GV A M-16011 Drywett Air 0 C I
CS CIV Yes CSJ-V-8 D-2 Cooter CIV IP41-f064 3 C 6= CV A M-16011 Division 2 W 0 0 DIME NA NA ~ Note 9 F-10 Sigpty 1P41-F065 3 C 8" CV A M-16011 Division 1 W 0 0 DIME NA NA Ilote 9 G-10 Sagply l 1P41-F066 3 3 6" A0 SFV P N-16011 W to ESF 0 0 NA NA No Note 8 F-10 Cooler too l 1P41-F067 3 5 8" A0 BFV P N-16011 W to ESF 0 0 NA NA No Note 8 l- G-10 Cooler iso i 1P41-F1074 3 C 4" CV A M-11609 Cont Rm MVAC 0 0/C DIME NA NA Note 9 E-1 1P41-F1075 3 C 4" CV A N-11609 Cont Rm MYAC 0 O/C DIME NA NA Note 9 E-1 1P41-F3104 3 8 30* MO OFV A H-11600 W to Turbine O C CS NA Yes CSJ-V-9 D-6 8tdg shutoff 1P41-F3?0s 3 8 30" M0 BFV A N-11600 W to Turbine O C CS NA Yes CSJ-V-9 F-5 stds Shutoff 1P41 F310C 3 8 30" M0 BFV A M-11600 W to Turbine O C CS NA Yes CSJ-V-9 D-6 stds Shutoff 1P41-F3100 3 8 33" MO BFV A M-11600 W to Turbine O C- CS NA Yes CSJ V-9 F-5 51dg Shutoff l
p ~ Netch Nucteer Plant tinit 1 IST Program Page No. 42 of 58 Vetve Test Tabte 10 - Revision 0 Velve PRIDI Exercise LeekoBe ST Romerks ID CC Cet Description A/P Coord Ftmetion No SP Freq Yest Reqd RR/C5J/ROJ
= - -
1P41-F311A 3 C_ 18" CV A D-11001 W Pump 0/C O/C Str NA NA Note 6 D-2 Discherge 1P41 F3118 3 C 18" CV A D-11001 W Pump 0/C O/C Otr NA NA Note 6 D-5 Discherse 1P41-F311C 3 C 18" CV A D-11001 W Pts p 0/C O/C Str NA NA Note 6-D-3 Discharge 1P41-F3110 3 C 18" CV A D-11001 W Puup 0/C O/C etr NA NA Note 6 D-6 Discharge 1P41-F312 3 8 30" MO BFV P D 11001 W Dilution Iso C C NA NA No Note 8 A-3 1P41-F401A 3 5 8" MO BFV P H-11600 W to DG Iso C C NA NA No Note 8 C-5 1P41-F402A 3 5 8" MO BFV P M-11600 W to DC Iso C C NA NA No Note 8 C-5 1P41-F4028 3 8 6" MD 8FV P M-11600 W to DG Iso C C NA NA No Note 8 C-4 1P41-F4038 3 8 6" MO BFV P H-11600 W to DG Iso C C NA NA No Note 8 C-4 1P41-F420A 3 8 2 1/2" MO GV P H-11609 Cent Rm NVAC 0 0 NA NA No. Note 8 C-1 Iso 1P41-F4208 3 8 2 1/2" M0 GV P H-11609 Cont Rm NVAC C C MA NA No Note 8 > 8-2 Cross-tie
.1P41 F4214 3 8 2 1/2" MO GV P H-11609 Cent Re MVAC 0 0 NA NA No Note 8 C-2 Iso k
, . , , . e n ,- - a ,- ~ _
I % Netch Nucteer Plant Unit 1 IST Program ' Page No. 43 of 58 ' vetw Test Table 10 - Revision 0 Velve PSID/ Enercise Leekage ST Romerks
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ID l CC Cet Description A/P Coord Ftriction NP SP Freq Test Reqd at/CSJ/ROJ IP41-F421s 3 s 2 1/2" NO GV P N-11609 Cent Rm MVAC C C- NA NA No Note 8 C-2 Cross tie 1M1-F422A 3 s 2 1/2" No GV P N-11609 Cent Rm wAC 0 0 NA NA No Note 8 B-2 Iso . 1M1-F4223 3 B. 2 1/2" NO GV P M-11609 Cent Rm WAC 0 'O NA NA No Note 8 5-3 Iso 1P41-F438A 3 .C 1 1/2" CV A D-11001 SW Ntr Cooting o 0 otr NA NA Note 22 B-3 Utr CV i 1P41-F4385 3 C 1 1/2" CV A D-11001 SW Mtr Cooting 0 0 Otr NA NA Note 22 A-6 Utr CV
- 1P41-F552A 3 C 6" CV A N-11600 DG 1A SW 0 0 PE0/ DINE NA - NA ROJ-V-27 ;
R-7 Discharge Note 9 i ! (' 1P41 F552C 3 C 6" CV A N-11600 DG 1C SW 0 0 PEG / DINE NA NA ROJ-V ; s-2 Discharge Note 9. I t
+
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- . ~ . - - . . . . . , - . . - . . _ - . . - . _ - . . ~ . . . - - - . - ,
1- )- Ratch mucteer Plant Unit-1 Iki Program Pope no. 44 of 58 Velve Test Table 10 - Revision 0 valve P&lD/ Exercise Leekage ~ ST Resorts i 3D CC Cet Description A/P Coord Fmction WP SP Freq Test Reqd HR/CSJ/ROJ 1P42-F051 2- A. 4" MD GV 'A M-16009 ROCCW to Recir 0 C CS CIV Yes CSJ-V-10 5-9 Civ 4
'1P42-F052 2 A 4" M0 CV A N-16009 RSCCW to Recir O C CS CIV Yes CSJ-V-10 E-9 CIV r
b 1P42-F063' '2 C 3/4" RV A M-16009 Thermal RV C O/C Note 5 NA no mA D-6 f
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_ _ . _ _ _ _..._m . . . . . _ . . . _ . . . .- s Natch mucteor Plant Unit 1 IST Program .Page No. 45 of 58 valve Test Table 10 - Revision 0 Velve PRID/ Ezereise .Leekage ST Remarks. 10 CC Cet. Description A/P Coord Ftmetion WP SP Freq . Test Reqd . RRICSJ/ROJ
.1P51 F513 2 A 2* Men GLV P N-16013 Possive CIV LC C None -CIV. No NA F-3 1P51 F514 2 A 2* Men GLV P N-16013 Possive CIV LC C None CIV No NA F-3 l
l l 1 i t
O O ' Match Nucteer Plant Unit 1 IST Progress Page No. 46 of 58 Velve Test Tabte 10 - Nevision 0 Velve PSID/ Exercise Leekage ST Neuraks ID CC Cet Description A/P Coord Function NP SP Freq Test Negd NR/3J/N0J 1P52-F261' -C 1" CV A N-11M7 Accus A014 0/C C NA Note 28 NA Note 30 C7 Intet CV 1P52-F262 - C 1" CV A N-11667 Accun A015 .0/C C WA Note 28 NA Note 30 C-7 Intet CV 1P52-F263 - C 1" CV A N-11667 Accum AC32 0/:: C NA Note 29 NA - Note 30 C-4 Intet CV 1P52-F264 - C 1" CV A N-11667 Accum A033 0/C C NA Note 29 NA Note 30
- i. C-4 Intet CV j~ 1P52-F265 ~ -
C 1" CV A N-11667 Accun A035 O/C C NA Note 29 NA Note 30 { C4 Intet CV 1P52-F266 - C 1" CV A N-11667 Accus A034 O/C C WA Note 29 NA Note 30 C-4 Intet CV i IP52-F267 - C 1" CV A N-11667 Accum A036 O/C C NA Note 29 NA Note 30 C-4 Intet CV l I e
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i O O Match Nucteer Plant Unit 1 IST Program O . Page No. 47 of 58 - i Velve Test Table 10 - Revision 0 vetwe PRID/ Exercise . Leekage. Si temerks 10 CC Cet Description A/P Coord Ftnction- WP SP Freq Test Regf RR/CSJ/NOJ 1P70-F002 2 A 18 AO GLV P N-16286 W Pnetmetic c c NA CIV Yes Note 8 s F-8 CIV . I 1P70-F003 2 A 1" A0 GLV P M-16286 W Pneuuntic C CIV. C NA Yes . Note 8 F-8 CIV t IP70 F004 2 A 2* SOV A N-16286 W Pneuentic 0 C etr Civ Yes NA B-8 CIV , j 1P70-7005 2 A 2" MW A N-16286 W Pnetmetic 0 .C Str CIV Yes NA B-8 CIV i 1P70-F066 2 A 2* SOV A N-16286 W Pneuentic 0 C Str Civ ' Yes NA . D-8 Civ 1P70-F067 2 A 2a SOV A M 16286 W Pneuantic 0 C Str Civ Yes NA D-8 CIV t l _ - . _ . . . - . _ . - _ . . ~ , _ -- . . _ - , _ _ _ .____ . _
p
. U J Netch Nucteer Plant Unit 1 IST Program Page No. 48 of $8 Velve Test Table 10 - Revision 0 volve ~ P8tD/ Exercise Leekage ST Romerts D CC Cet . Description A/P Coord Ftmetion WP SP Freq Test Reqd RR/CSJ/ROJ 1R43-F0094 - C 2" CV A N-11037 DG Fuet Oil C O/C Str NA M Notes C-2 Pisy Disch CV 16,23 1R43-F0095 -
C 2" CV A N-11037 DG Fuet Oil C O/C Str NA NA Notes C-2 Pupp Disch CV _16,23 1943-F009C - C 2" CV A N-11037 DG Fuet Oil Day C O/C Str NA NA Notes A-10 Tank Intet CV 16,23 1R43-F009D - C 2" CV A N-11037 DG Fuet Oil Day C O/C Otr NA NA Notes A-9 Tonk Intet CV 16,23 1R43-F0104 - C 2" CV A N-11037 DG Fuel Olt C O/C Otr NA NA Notes D-2 Pimp Disch CV 16,23 1R43-F0105 - C 2" CV A N-11037 DG Fuet oft C O/C Str NA - NA Notes D-2 Pump Disch CV 16,23 1R43-F010C - C 2" CV A N-11037 DG Fuet Olt Day C O/C Otr NA NA Notes A-8 Tank Intet CV 16,23
~
1;43-F010D - C 2" CV A N-11037 DG Fuet 011 Day C O/C Otr NA NA Notes A-8 Tank Intet CV 16,23 I 1R43-F0114 - C 2" CV A N-11037 DG Fuet oit C O/C Otr NA ' NA Notes B-2 Pump Disch CV 16,23 l 1943 F011e - C 2" CV A N-11037 DG Fuet 011 C O/C Str NA NA Notes B-2 Pimp Disch CV 16.23 1R43-F011C - C 2" CV A N-11037 DG Fuet oft Day C 0/C Str M NA Notes A-11 Tank Intet CV 16,23 1R43-F0110 - C 2" CV A N-11037 DG Fuet Olt Dey C O/C Otr NA NA Notes i A-11 Tank Intet CV 16,23
__ _ _ _ . . . __ . . _~ ._. ._ . . . _ _ . . . . _ _ _ _ _. . . O ) G \ . v Match Nucteer Plant Unit 1 IST Program Page No. 49 of 58 Velve Test Table 10 - Revision 0 Velve P&lD/ Exercise Leskoge ST Reserks ID CC Cet Description A/P Coord Ftmetion WP SP Freq Test Regti RRICSJ/ROJ IR43-F015A - 8 1 1/2" SOV A M-11631- DG Air Start C O/C Otr NA Yes Notes M-11 Viv 16,24
- 1R43-F0158 -
5 1 1/2" SOV A M-11638 DG Air Start C O/C etr NA Yes Notes M-11 Viv 16,24 1R43 F015C - 8 1 1/2" SOV A M-11631 DG Air Start C O/C Otr NA Yes Notes M-11 Viv 16,24 1R43-F016A - 8 1 1/2" SOV A M-11631 DG Air Start C O/C etr NA Yes Notes 16, M-11 Viv 24 1R43 F0165 - 5 1 1/2" SOV A M-11638 DG Air Stort C O/C etr NA Yes Notes 16, J 11 Viv 24 1R43 7016C - B 1 1/2" $0V A M-11631 DG Air Start C O/C Str NA Yes potes 16, M-11 Vlv 24 1R43 F3034A - C 3/4" CV A M-11631 Air Receiver C C Note 25 NA NA Note 16 E-11 Intet CV 1R43-F30348 - C 3/4" CV A M-11638 Air Receiver C C Note 25 NA NA Note 16 E-11 Intet CV 1R43-F3034C - C 3/4" CV A M-11631 Air Receiver C C Note 25 NA NA Note 16 F-11 Intet CV 1R43-F3035A - C 3/4" CV A M-11631 Air Receiver C C Note 25 NA NA Note 16 E-10 Intet CV 1R43-F30358 - C 3/4" CV A M-11638 Air Receiver C C Note 25 NA NA Note 16 E-10 Intet CV 1R43-F3035C - C 3/4" CV A M-11631 Air Receiver C C Note 25 NA NA Note 16 E-10 Intet CV
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.b i Match Nucteer Plant Unit.1 IST Program Page No. 50 of 58.
Velve Test Tebte 10 - Revision 0 - Wolve PSID/ ' Exercise Leekspe ST Remorts ID CC Cet Description A/P Coord Fmetion WP. SP Freq Test Reqd RR/CSJ/ROJ 1R43 F3036A - C. 1/2" RV A M-11631- Air Receiver RV C O/C Note 34 NA NA - Note 16 ' E-12 . 1R43-F30360 - C 1/2" RV A M-11638 Air Receiver RV C O/C Note 34 NA NA Note 16 F-12 1R43-F3036C - C 1/2" RV A M-11631 Air Receiver RV C O/C Note 34 NA NA Note 16 E-12 i 1R43-F3037A - C 1/2" RV A M-11631 Air Receiver RV C O/C Note 34 NA NA Note 16 E-8 1 1R43-F30375 - C 1/2* RV A M-11638 Air Receiver RV C O/C Note 34 NA NA - Note 16 F-9 1R43-F3037C - C 1/2" RV A M-11631 Air Receiver RV C O/C Note 34 NA NA Note 16 E-8 i r I i i t 3
._ . -. . . . - --...m .- . _ . . . . . _ . . . - - .. . . - . _ _ . . . . . . . ..--.- . . _ . . . _ - . . . . _ . . . _ _ . . . _ = . _ --. .. .-.. . .
p Metch NucIeer PIent Unit 1 IsT Proeram Page No. 51 of 58 - Velve Test Taide 10 - Revision 0 -;
- Volve P8ID/ Emercise Leekage ST Remarks IS CC Cet Description A/P Coord Ftmetton MP SP Freq Test Reqd RR/CSJ/ROJ-1723-F996 2 A 3/4" Men GLV P M-16060 Possive CIV M C C CIV No M D-3 1T23-F995 2 A 3/4" Men CLV P. M 16060 Passive CIV C C M CIV No NA-D-3 t
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c O O , Natch Nucteer Plant Unit 1 IST Program Page Iso. 52 ef 58. Velve Test Totde 10.- Revision 0 Velve PSID/ Emercise. Leekage_. ST Remarks
-ID . CC Cat Description A/P Coord Fametion WP SP Frog Test Reqd IMt/CSJ/ROJ 1T M-F001A 3 8 18" A0 BFV A M-16020 Fitter Bed C 0 Str IIA Yes teste 16 C-1 Intet from Rx StdB 1T M-F0018 3 5 18" A0 SFV A N-16020 Filter ted C 0 Str IIA Yes Note 16 G-1 Intet from Rx BldB 1T M-F002A 3 8 18" Ao BFV A N-16174 SGTS Filter C 0 Otr IIA Yes Note 16 C-6 Outlet from Rx BldB ,
i U 1TM F002B 3 5 18" A0 BFV A N-16174 SGTS Filter C 0 Otr IIA -Yen Note 16 F6 Outlet from Rn 5tdB ! t i m__________________________________.__._.___ _ _ _ _ . ___ _ ._ _ _ _ . . _ - . . ~ . _ - . . _ , . _ . . . . _ _ _ _ .._ _ _ .
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O Match Nucteer Plant Unit 1 IST Program . Pese No. 53 ef 58 volve Test Tebte 10 - Revision 0 Velve PRIDI Exercise Leekage ST Romerts
.O CC Cet Description A/P Coord Ftsiction MP SP Freq . Test Reqd RRICSJ/WOJ 1748-F103 2 A 6" A0 BFV A N-16000 W & Torus CIV C C - Otr CIV Yes M
.i' F-2 1T48-F104 2 A 1" A0 GLV A K-16000 W & Torus CIV C C 9tr CIV Yes MA G-4 1748-F113 2 A 2* A0 GLV A M-16000 W Inerting C C etr CIV Yes N4 F-7 Outbrd CIV 1T48-F114 2 A 2* A0 GLV A M-16000 W Inerting C C etr CIV Yes MA F-8 Irbrd CIV 1T48-F115 2 A 2* A0 GLV A M-16000 W Inerting C C etr CIV Yes mA G-7 Outbrd CIV IT48-F116 2 A 2" A0 GLV A M-16000 W Inerting C Otr C CIV Yes un G-S Inbrd CIV i 1T48-F1184 2 A 1= SOV A M-16000 W neket, Inbrd C C Otr CIV Yes mA G-5 CIV 1T48-F1188 2 A 1" SOV A M-16000 Torus Makeup C C etr CIV Yes uA G-5 Irtrd CIV l
1T48-F307~ 2 A 18* A0 SFV A M-16024 W Purge Inlet C C Otr CIV Yes NA l C-9 Inbrd CIV l i 1T48-F308 2 A 18" A0 BFV A M-16024 W Purge Inlet C C Otr CIV Yes MA C-10 Irtrd CIV 1T48 F309 2 A 18" A0 BFV A M-16024 Torus Purge C C Str CIV Yes WA E 10 Inlet Irtrd CIV IT48-F310 2 A 20" A0 BFV A M-16024 Tort:s Purge Vec C 0/C Str CIV Yes NA F-10 Brker CIV
C Match Nucteer Plant Unit 1 IST Program O O Pope No. 54 of 58 Velve Test Table 10 - Revision 0 Volve PSID/ Exercise Leekage ST Romerks-ID CC Cet Description A/P Coord Function WP SP Freq Test Regti At/CSJ/ROJ - 1T48-F311 2 A 20" A0 SFV A M-16024 Torus Purge Vec C O/C Str CIV Yes NA F-9 Brker Civ 1T48-F318 2 A 18" A0 BFV A M-16024 Torus Purge -C C Str CIV Yes NA G-4 Outlet Irbrd CIV 1748-F319 2 A 18" AO BFV A M-16024 W Purge Outlet C C Str CIV Yes NA D4 Irbrd CIV 1748-F320 2 A 18" A0 SFV A M-16024 W Purge Outlet C C Str CIV Yes NA D3 Outbrd CIV 1748-F321- 2 A 2" A0 GLV A M-16000 DW Inerting C C Str CIV Yes NA J7 Outbrd CIV iT48-F322 2 A 2" A0 GLV A M-16000 . W Inerting C C Otr CIV Yes NA j J-8 Irerd CIV IT48-F323A- 2 C 20" A0 Test CV A M-16024 W to Torus vs C O/C Str/R0 NA NA Notes 16,
- M-8 26, 33 1T48-F323s 2 C 20" A0 Test CV A M-16024 W to Torum vs C O/C Str/R0 NA NA Notes 16, M-8 26, 33 IT48-F323C 2 C 20" A0 Test CV A M-16024 Du to Torus vs C O/C Otr/R0 NA NA Notes 16 M-8 26, 33 IT48-F3230 2 C 20" A0 Test CV A M-16024 DW to Yorus vs C O/C Str/R0 NA NA Notes 16, M-8 26, 33 1748-F323E 2 C 20" A0 Test CV A M-16024 DW to Torus vs C O/C Str/RO NA NA Notes 16, M-8 26, 33 IT48-F323F 2 C 20" A0 Test CV A M-16024 DW to Torus v5 C O/C Otr/RO MA - NA Notes 16, ;
M-8 26, 33 _ _ . . - _ _ - _ .- - _ _ - _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ - _ . _ . _ _ . - _ . _ _ _ - . _ _ _ - _ _ - - - - . _ _ __ .-__--_ -_ - -__ - - _ --_-- - - - - _ _ - - . . - + -. .m--- u +- e. --
Netch Nucteer Plant Unit 1 IST Program Page No. 55 of 58 Valve Test Table 10 - Revision 0 Velve : P&lD/ Exercise Leekage ST Remarks
. ID CC Cet Description A/P Coord Function WP SP .Freq Test Reqd .RR/CSJ/ROJ.
1T48-F323G 2 C 20" AD Test CV A M-16024 W to Torus V5 C O/C Otr/R0 NA NA Notes 16, N-8 26, 33 1T48-F323N 2 C 20" A0 Test CV A R-16024 OW to Torus V5 C ' 0/C Str/R0 NA NA Notes 16, M-8 26, 33 IT48-F323I 2 C 20" A0 Test CV A M-16024 W to Torus V5 C O/C Otr/R0 NA NA Notes 16, M 26, 33 1T48-F323J 2 C 20" A0 Test CV A H-16024 W to Torus VS C O/C Otr/R0 NA NA Notes 16, N-8 26, 33 IT48-F323K 2 C 20" A0 Test CV A M-16024 W to Torus VS C O/C etr/R0 NA -NA Notes 16, M-8 26, 33 - l 1T48-F323L 2 C 20" A0 Test CV A N-16024 W to Torus V8 C O/C Str/R0 NA NA Notes 16, l M-8 26, 33 l 1T48-F324 -2 A 18" A0 BFV A N-16024 Torus Purge C C Str CIV .Yes . NA I 0-10 Intet Outbrd CIV 1T48-F325 2 A 2" A0 GLV A H-16000 Torus Inerting C C Str CIV Yes NA H-7 Outbrd CIV i 1T48-F326 2 A 18" A0 SFV A H-16024 Torus Purge C C Otr CIV Yes NA G-3 Outlet Outbrd 'i CIV 1748-F327 2 A 2" A0 GLV A N 16000 Torus Inerting C C Otr Civ Yes NA H-8 frbrd CIV ' 1748-F328A 2 AC 20" A0 Test CV A n-16024 Ex Stdg to Supp C O/C Str/R0 CIV NA Note 26, G-10 Cham vs Civ 33 i 1T48-F3288 2 AC 20" A0 Test CV A H-16024 Rx Stdg to Supp C 0/C etr/R0 CIV NA Note 26, G-9 Cham VS CIV 33 _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ __ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _._~ ___ _________ _ ________ _ ___ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
. a- ~ . . . -...~.. ~. ., . . . . - - . . . . -
. Match Ilucteer litant thit.1 IST Progren . Page no. 56 of 58 Valve Test Table 10 - Revision 0 -
- Vetwe PRID/' Exercise . Leekage . ST . Romerts-ID CC Cet Description A/P Coord Fametion - WP SP - Freq Test Reqd RR/CSJ/NOJ 1T48-F3324- 2 A - 2" A0 EV . A N-16024 Torus Purge 'C C Str CIV' Yes. NA E-3 Outtet outbrd CIV --
1748-F332s 2 ' A 2" AG CLV 'A N-16024 Torus Purge C C Otr CIV Yes- u4 ' F-3 Outtet Outbrd +< CIV 1748-F333A 2 A 2" A0 GLV A M-16024 forus Purge C C Str CIV ' Yes MA . + E-4 Outtet Irbrd CIV " 1T48-F3338 2 A 2" A0 GLV A N 16024 Torus Purge C C etr ' ~ CIV Yes IIA F-4 Outlet Irbrd i CIV 1T48-F334A 2 A 2" A0 GLV A N-16024 DW Purge outlet C C Otr CIV ' ! Yes MA B-3 Outbrd CIV
= 1T48-F3348 2 A 2" A0 GLV A N-16024 ou Purge outlet C' C Str CIV Yes MA '
C-3 Outbrd CIV IT48-F335A 2 A 2" A0 GLV A N-16024 DW Purge Outlet C C Str CIV Yes MA - B-4 Irbrd CIV t 1T48-F3353^ 2 A 2* A0 GLV A N-16024 DW Purge Outlet C C Otr CIV Yes MA C-4 Inbrd CIV
-1T48-F338 2 -A 2" SOW A- M-16024 Bypess-Outbrd C C Str CIV Yes ' NA N-2 CIV I
1T48-F339 2 A 2" 50V A N-16024 - typass-Irbrd .C C CIV ' Otr Yes. w NA M-3 CIV i i 1748-F340 2 A 2" sov A N-16024 Bypass-cutbrd C C Otr CIV ' Yes MA 0-4 CIV l li i i w +-wr+--w w-.e 1 w -e-+ 1 _ - ___ w _. _ _ _ _ --_.w _ 4w-__ - E_ -_-- __-__mm_-_---__s_._- _ _ . _ _ _ __ _ _______ -__ _ _ _ _ _- _ _ _ _-._.
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O O O . Natch mucteer Plant imit 1 IST Program . Page No. 57 of 58 Valve Test Tabte 10 - Revision 0
-Velve PEID/ -Exercise Leekage ST Remarks '
ID CC Cet Description A/P Coord Function NP SP Freq Test Reqd Rt/CSJ/WOJ 1748-F341 2 A 2" SOV A N-16024 Bypass-Irtrd C C etr CIV Yes ' NA . D-4 CIV 1748-F342A 2 AP 1/2" SOV P H-16024 Torus to N VB C CIV C NA Wo Note 27 M-8 Test CIV 1T48-F3428 ~ 2 AP 1/2" SOV P M-16024 Torus to DW V8 C C CIV NA No Note 27 H-8 Test CIV IT48-F342C 2 AP 1/2" $0V P N-16024 Torus to DW VS C C CIV NA No Note 27 M-8 Test CIV 1T48-F342D 2 AP 1/2" SOV P M-16024 Torus to DW VB C C NA CIV No Note 27 M-8 Test CIV 1T48-F342E 2 AP 1/2= SOV P n-16024 Torus to DW Vs C C NA CIV No Note 27 N-8 Test CIV I IT48-F342F 2 AP 1/2" SOV P H-16024 Torus to DW VB C C NA CIV No Note 27 M-8 Test CIV f I IT48-F342G 2 AP 1/2" SOV P M-16024 Torus to DW V8 C C NA CIV ' No Note 27 H-8 Test CIV i 1T48-F342M 2 AP 1/2" SOV P H-16024 Torus to DW V8 C C
~
MA CIV No Note 27 H-8 Test CIV 1748-F3421 2 AP 1/2" SOV P H-16024 Torus to DW V8 C C NA CIV No Note 27 , M-8 Test CIV 1T48-F342J 2 AP 1/2" SOV P H-16024 Torus to DW V8 C C NA CIV No Note 27 M-8 Test CIV 1T48-F342K 2 AP 1/2" SOV P H-16024 Torus to DW Ys C C NA CIV No Note 27 H-8 Test CIV L
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v . Retch Nutteer Plent thit 2 IST Progree Pese me. 5 of de , Vetve Test TeMe 11 - Revielen 0
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2021-F053A' 1 AC 1" EFCV A N-26001 Inst EFCV O- C RO LTV M ROJ-V-3 N-5
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Netch Nucteer Plant Unit 2 IST Progree c , O Page to. 4 ef 40-Vetve Test Telde 11 - Revielen 0
~ Velve PSID/ Emerclee Lookoge ST Reserks ID CC Cet Descriptlen A/P Coord Functlen WP SP Frog Test Reg 6 RR/CSJ/ROJ 2B21-F0535 1 AC 1" EFCV A N-26001 Inst EFCV C.
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s Netch Nucteer Plant thlt 2 IST Program Pese no. T of 60 Velve Test Teide 11 - Revision 0 Velve PSID/- Exercise Leekage ST Reserks ID CC Cet Deecription A/P Coord Fametton WP RP Frog Test Reqd RR/CSJ/ROJ 2821 F059N 1 AC 1" EFCV A N-26001 Inst EFCV O C RO LTV NA ROJ-V 3 M-9 2321-F059L 1 AC 1" EFCV A M-26001 Inst EFCV O C RO LTV M ROJ-V-3 M-9 2821-F059N 1 AC 1" EFCV A N-26001 Inst EFCV 0 C RO LTV NA ROJ-V-3 N-9 2321-F059N 1 AC 1" EFCV A N-26001 Inst EFCV O C R0 LTV NA ROJ-V-3 N-9 2821 F059P 1 AC 1" EFCV A N-26001 Inst EFCV O C RO LTV NA ROJ-V-3 N-9 2B21-F059R 1 AC 1" EFCV A N-26001 Inst EFCV O C R0 LTV NA ROJ-V-3 M-9 2821-F0595 1 AC 1" EFCV A N-26001 Inst EFCV O C RO LTV NA ROJ-V-3 N-9 2321 F059T 1 AC 1" EFCV A N-26001 Inst EFCV O C RO LTV NA ROJ-V-3 l N-9 l 2821-F059U 1 AC 1" EFCV A M-26001 Inst EFCV O C RO LTV NA ROJ-V-3 N-9 I 2s21-F061 1 AC 1" EFCV A M-26001 Inst EFCV O C RC LTV NA ROJ-V-3 J-9 2B21 F0704 1 AC 1" EFCV A N-26000 Inst EFCV O C RO LTV NA ROJ-V-3 D-9 2821-F0705 1 AC 1" EFCV A N-26000 Inst EFCV O C R0 LTV NA ROJ-V-3 0-9 h I
_ . _ _ _ .. _ .._ ~ ...-. .._. _ -. . _ __-.__ . ... _ . _ . _ ._.. , . o O Netch mucteer Plant imit 2 IST Program Page me. O of 6e l Velve Test Totde 11 - Revlelen 0 vetve P&lD/ Emercise Leekage - ST Resorts It CC Cet Description A/P Coord Functlen WP SP Frog Test Regd RR/C5J/ROJ 2821-F07DC 1 AC 1" EFCV A N-26000 Inst EFCV O C RO LTV M ROJ-V-3 D-9 2321 F07tl0 1 AC 1" EFCV A N-26000 Inst EFCV O C RO LTV M ROJ-V-3 D-9 2B21-F071A 1 AC 1" EFCV A N 26000 Inst EFCV O C R0 LTV WA ROJ-V-3 B-9 2321-F0718 1 AC 1" EFCV A N-26000 Inst EFCV O C R0 LTV NA ROJ-V-3 3-9 ! It21 FOTIC 1 AC 1" EFCV A N 26000 Inst EFCV O C RO ' LTV NA ROJ-V-3 - B-9 2821-F0710 1 AC 1* EFCV A N-26000 Inst EFCV O C RO LTV NA ROJ-V-3 3-9 2B21-F0724 1 AC 1" EFCV A N-26000 Inst EFCV O C RO LTV NA ROJ-V-3 5 B-9 2821-F0728 1 AC 1" EFCV A N-26000 Inst EFCV O C RO LTV NA ROJ-V-3 5-9 2321 F072C 1 AC 1" EFCV A N-26000 Inst EFCV O C RO LTV M ROJ-V-3 3-9 2821-F072D 1 AC 1" EFCV A N-26000 Inst EFCV O C RO LTV NA ROJ V-3 5-9 2921-F073A 1 AC 1" EFCV A N-26000 Inst EFCV O C RO LTV NA ROJ-V-3 ! B-9 ' i 2B21 F0735 1 AC 1" EFCV A N-26000 Inst EFCV O C RO LTV NA ROJ-V-3 B-9 i
__ __ ._ _ _ _ .__ _ . _ , _ . . . . - _ _ . ._.... .--._. .._ .- m . ._. m..._m.. _. . . . _ _ _ _ _ . . . . D Netch hueleer Pterit teilt 2 IST Progree Page me. 9 of 60 , Velve Test Teide 11 - Revielort 0 Velve PSID/ Exercise Leekage ST 'Remarke O CC Cet Description A/P Coord F e etfori NP Freq SP Test Regd RR/CSJ/90J i 2821-F073C 1 AC 1" EFCV A N-26000 I w t EFCV O C RO LTV IIA A0J-V-3 8-9 2821 F0TD 1 AC 1" EFCY A N-26000 Inst EFCV O C R0 LTV IIA ROJ-V-3 B-9 2321-F0784 2 C 18" A0 CV A N-26000 FW CV O C CS NA NA CSJ-V-11 E-2 2e21-F0765 2 C 18" A0 CV A M-26000 FW CV o C CS IIA IIA CSJ-V-11 E-2 j 2921-F077A 1 AC 10" A0 CV A N-26000 FW Outbrd CIV O 0/C DN0/CS CIV NA CSJ-V-12 E-3 2921-F0775 1 AC 18" A0 CV A N-26000 FW Outbrd CIV o ' O/C DWO/CS CIV IIA CSJ-V-12 { E-3 2821-F1105 3 C i? V5 A N-26000 VB NORY Diech C O/C RO IIA IIA i Note 33 N-T ' 2521-F1100 3 C 10" VW 2 M-26000 VB IIERV Diech C O/C RO NA IIA Note 33 N-T 2821-F110F 3 C 10" VB A M-26000 V5 MSRV Disch C O/C RO IIA IIA Note 33 N-T 2021-F110G 3 C 10" VS A N-26000 VB NSRV Disch C O/C 11 0 IIA NA Note 33 ? N-T 2821-F111 2 A 1" A0 SV A N-26306 Pass Seepte Vtv c c etr CIV Tee IIA E-10 l i .2821-F112 2 A 1* A0 SV A N-26384 Pass Sm yte Vtv C C Str "tV Tee NA I E-10
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2331 F0048 1 AC 1" EFCV A N-2n003 Inst EFCV O C 30 LTV NA ROJ-V-3' G-2 2531-F009A 1 AC 1" EFCV A N-26003 Inst EFCV O s C RO LTV NA ROJ-V-3 0-9 2531-F0098 1 AC 1" EFCV A N-26003 Inst EFCV O C 20 LTV NA ROJ V-3 E-9 2531-F009C 1 AC 1" EFCV A N-26003 Inst EFCV O C RO LTV NA ROJ-V-3 E-9 1 2831-F009D 1 AC la EFCV A N-26003 Inst EFCV 0 C RO LTV NA 20J-V-3 F-9 2531-F0104 ! 1 AC 1" EFCV A N-26003 Inst EFCV O C RO LTV NA ROJ-V-3 09 1 2331-F010s 1 AC 1" EFCV A N-26003 Inst EFCV O C RO LTV NA ROJ-V-3 F-9 2331-F010C 1 AC 1" EFCV A M-26003 Inst EFCV O C RO LTV NA ROJ-V-3 E-9 , i 2531-F010D 1 AC l' EFCV A N-26003 Inst EFCV ' O C RO LTV NA ROJ-V-3 - F-9
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A N-26003 Inst EFCV C C RO LTV NA ROJ-V-3 D-9 2531-F0118 1 AC la EFCV A N-26003 Inst EFCV O C M LTV M ROJ-V-3 F-9 M31-F011C 1 - AC 1* EFCV A N-26003 Inst EFCV 0 C 20 LTV M ROJ-V 3 E-9 2531-F0110 1 AC 1" EFCV A N-26003 Inst EFCV O C R0 LTV E ROJ-V-3 G-9 2331 F012A 1 AC l' EFCV A N-26003 Inst EFCV O C RO LTV NA ROJ-V-3 E-9 2331-F01h 1 AC 1" EFCV A R-26003 Inst EFCV O C RO LTV M ROJ-V-3 F-9 2331-F012C 1 AC 1" EFCV A N-26003 Inst EFCV 0 C RO LTV NA ROJ-V-3 E-9 2531-F013 1 AC 1" EFCV A N-26003 Inst EFCV O C RO LTV M ROJ-V-3 G-9 2331-F013A 1 AC 3/4" CV A N-26003 Reefr Puup Seat 0 C R0 CIV NA ROJ-V-6 7 G-3 Utr Civ 2531-F0135 1 AC 3/4" CV A N 26003 Reefr Pump Seet 0 C A0 CIV NA ROJ V-6 G-3 Utr CIV 2531-F017A 1 AC 3/4" CV A N-26003 Recir Po p Seet 0 I C RO CIV NA ROJ-V-6 G-2 Wtr CIV 2031-F0173 1 AC 3/4" CV A R-26003 Recir Pu p Seet 0 C RO CIV NA ROJ-V-6 G-2 Utr Civ
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O Notch Nutteer Plant imit 2 IST Program
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U(N Page me. 12 ef de Velve Test Table 11 - Revision 0 1 ! Velve ' PRIS/ Enercise Leekage ST Remarks 19 CC - Cet Description A/P Coord Function NP SP Frog Test Respi RR/C5J/NOJ 2531-F019 1 A 1".A0 SLV A N-26003 Rx semple Sys O C etr CIV Yes R4 E-4 Ir6rd CIV ' l 2331-F020 1 A 1" A0 SLV A R-26003 Rx senple Sys o C Str CIV Yes m E-2 Outbrd CIV 2931 F031A 1 B 28" MO SW A R-26003 Rectre Po p o C CS m Yee CsJ-V-2 i G-7 DIsch too 2831-F031s 1 a 29" M0 SV A N-26003 Reelr1: Pg a i C Cs u Yee tsJ-V-2 a-7 Disch Iso l l 2531-F0404 1 AC 1" EFCV A R-26003. Inst EFCV O C R0 LTV NA ROJ-V-3 i G-9 l gg31.F0608 1 AC 1" EFCV A N-26003 Inst EFCV O C R0 LTV NA ROJ-V-3 G-9
~ 2s31-F040C 1 AC 1" EFCV A N-26003 Inst EFCV O C R0 LTV NA ROJ-V-3 G-9 2531-F042 1 AC 1" EFCV A N-26003 Inst EFCV O C 90 LTV NA ROJ-V-3 i N-9 ,
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i t Netch Nueteer Plant Unit 2 IST Program pese No. 13 of de Vetve Test Tetde 11 - Revielen 0 Vetve PSID/- Esercise Leeksee ST Resorte ID CC ' Cet Description A/P Coord Ftmetion MP SP Freq Test Respi RR/CSJ/ROJ 2C11 F0104 2 3 1" A0 RV A N-26007 SDV Vent Viv 0 O/C etr/R0 M Yes RR V-3 A-5 i 2C11-F0108 2 B 1" AS EV A N 26007 50V Vent Vlv 0 O/C etr/R0 m Yes M-V-3 A-5 2C11-F011 2 3 2" AS EV A N-26007 EDV Drein vtv 0 0/C etr/R0 m Yes NR-V-3 3-3 2C11 F035A 2 0 1" A0 E V A N-26007 SDV Vent Vlv 0 O/C etr/R0 M Yes RR-V-3 A-5
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2C11 F03T 2 5 2" A0 EV A N-26007 WV Dreln Viv 0 0/C Str/RO NA Yes NR-V-3 B-3
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2C11-NCU-114 2 C 3/4" CV A N-26006 SDV NCU CV C 0 RO NA NA ROJ V-7 ! A-6 Note 2 l 2C11-NCU 115 2 C 1/2" CV A N-26006 theroine Water C C RO NA NA ROJ-V-8 i C-6 M CV Note 2 l 2C11-NCU-126 1 0 1" A0 EV A N-26006 Scram Insert C 0 RO NA No ROJ-V-9
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O Netch Nutteer Plant Unit 2 IST Program J Page No.14 of 40 J vetve Test Tetde 11 - Revielen 0 Velve P&lD/ Emercise Leekage ST Reemrte ID CC Cet Description A/P Coord Fametton WP SP Frog Test. Rogd- M/CSJ/ROJ 2C41-F004A 2 8 1-1/P Empt Act A N-28009 RC Empt Act 0 ISTC 4.6 M C NA- M E-2 2C41-F0040 '2 9 1-1/2" Empt Act A N-26009 R C Empt Act C 0 ISTC 4.6 m M- NA l ( F-2 l t l 2C41-F006 1 AC 1-1/2" CV A N-26009 RC Outbrd CIV C O/C RO CIV NA NOJ-V-10 E-2 2C41-F00T 1 AC 1-1/2" CV A N-26009 RC Ir6 sed CIV C O/C NO CIV NA ROJ-V-10 ! F-2 ! 2C41-F0294 2 C 1" RV A N-26009 RC Pup Disch ~ C O/C Note 5 ' NA NA NA E-5 RV l 2C41-F0295 2 C 1" RV A N-26009 R C Pu p Bloch C. 0/C Note 5 NA NA NA N-5 RV ' 2C41-F033A 2 C 1-1/2" CV A N-26009 R C Pe p Disch C 0 Otr NA NA NA F-4 2C41-F0335 2 C 1-1/2" CV A N-26009 RC Puup Disch C 0 etr NA NA NA G-4 i _ _ _ . ,- c- # , . , - y , . - - - . - , .w. ,- .y _
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Netch Nucteer Plant Ikilt 2 IST Progree Pese No. 15 of de Velve Test Tabte 11 - Revision 0 Velve PSID/ Emercise Leekepe ST. Reserke ID CC Cet teocription A/P Coord Functlen WP SP Frog Test Reqd RR/CSJ/NOJ-2C51-Sett A 2 A Bet 1 SOV A N-26995 TIP Isted CIV O C etr CIV Yes NA C-3 i 2C51-sett 5 2 A Bett 90V A N-26995 TIP Irtrd CIV O C Str CIV Yes NA C-3 ! l 2C51-Dett C 2 A Seit SOV A N-26995 TIP Irtrd CIV . O C etr CIV Yee m C-3 2C51-Sett D 2 A Bell SUV A N-26995 TIP Ir6rd CIV O C etr CIV Yes #4 C-3 2t51-F3012 2 A 30V A N-26995 TIP N2 Purge O C Str/R0 CIV . Yes AR-V-9 F-13 CIV ! 2C51-F3017 2 AC CV A N-26995 TIP N2 Purge o C to CIV m n0J-V-11 E-13 CIV -i 2C51 Sheer A 2 m Empt sheer A N-26995 TIP Outbrd CIV O C ISTC 4.6 m #4 at-V C-3 2C51-Sheer 5 2 AS Empt Sheer A N-26995 TIP Sutbrd CIV O C ISTC 4.6 NA NA at-V-5 C-3 - 2C51 sheer C 2 AS Empt sheer A N-26995 TIP Outbrd CIV O C ISTC 4.6 m #4 mR-V-5 C-3 2C51 Sheer 9 2 AS Empt Sheer A N-26995 TIP Outbrd CIV O C ISTC 4.6 m NA at-V-5 C-3 t f l-l l !
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Netch tueleer Plant imit 2 IST Program Page me.14 of de ' ' vetve Test Telde 11 - Revielen 0 volve PGID/ Emercise Leekage ST Resorte
-t3 CC Cet Deecriptlen A/P Coord .Feetten MP Frog SP Test togd RR/ttJ/a0J
. 3 11-F050 2 A la A0 Centrol A R-26014 Fleelen Prod 0 C Str CIV Yes m D-5 non CIV .
- 3 11 F051- 2 A 1* A0 Centrol A R 26016 Fleelen Pred 0 C Str CIV Yes m F-5 Men CIV B 11 F952 2 A la A0 Centrol A N-26014 Fleelen Pred 0 C etr CIV Yes IIA D-6 Non CIV B11 F953 2 A la A0 Centrol A E-26016 Fleelen Prod 0 C Str CIV Yee m F-6 Men CIV 8 11 F050 2 A 18 Men OLV P R 26014 Pesolve CIV LC C m CIV no m 8-4 311 F065 2 A la Men SLV P N 28016 Pooelve CIV LC C m CIV ' me m-83
O J O Netch Nucteer Plant Unit 2 IST Proerse Pope No. IT of 60 vetve feet Teide 11 - Revielen 0 volve P&lD/ Emercise Leeksee ST Remarke ID CC Cat Description A/P Coord Feetten NP SP Frog Test Reqd RR/CSJ/ROJ 2E11 F003A 2 B 16" MD SV A N-26015 RM Rx SheLL 0 0 etr M Yes NA D-4 Side Outlet 2E11-F0035 2 3 16" MO GV A N-26014 Rtut Nx Shett 0 0 etr M Yes NA E-8 side Outlet 2E11-F004A 2 B 24" MD GW A N-26015 Reut Pg Suet 0 O/C i etr NA Yes Note 4 F-8 Torus Iso 4 M11-F004s 2 B M" No GV A N 26014 RNR Pump Suct 0 0/C Str NA Yes Note 4 F3 Torus too 2E11-F004C 2 B 24" M0 SV A M 26015 Reut Pwp Suct 0 0/C etr NA Yes Note 4 E9 forus Iso ! 2E11-F0040 2 5 M" MO GV A N 26014 Reut Pump Suct 0 0/C etr BA Yes Note 4 F-2 Torus Iso 2E11 F005A 3 C 14" CV A N-21039 RtutW Puup C O/C Str NA NA Notes 6,7 C-5 Disch CV 2E11-F005e 3 C 14" CV A M-21039 ReutW Pump C O/C etr M MA Notee 6,7 F-5 Dlech CV 2E11-F005C 3 C 14" CV A N-21039 ReutW Puup C O/C etr NA NA Notes 6,7 D-4 Disch CV 2E11-F0050 3 C 14" CV A N-21039 ReutW Puun C O/C etr M NA Notes 6,7 G-4 Oloch CV 2E11-F006A 2 B 20" MO SW A N-26015 Rtut SDC Suet C 0 etr NA Yes M F-8 2E11-F008e 2 3 20" MO GV A N-26014 Rtut SDC Suct 0 C etr M Yes NA F-3
_ . . . _ . . . . . .. . . _ . _ _ - .___ - - _ . _ _ . . . . . _ _ _ . . . . . . ~ _ . . _ . _ _ ~.. .. . _ . _ . .. . _ . . Netch Nucteer Plant Unit 2 IST Program Page No.18 of 60 Vetve Test folde 11 - Revisten 0 Vetwe P4ID/ Emerefse Leeksee ST Reenrks ID CC - Cet Description A/P Coord F metion MP SP Frog Test Reqd DR/CSJ/m0J 2E11-F006C 2 8 20" NO GV A N-26015 km SBC Suct C 0 etr NA Yes WA F-10 2E11-F0060 2 8 20" NO GV A N-26014 RNR MPC Suct C 0 etr NA ' Yes NA t F-2 2E11-F007A 2 3 4" MD GV A N-26015 km Pg Min 0 0/C etr mA Yes note 4 D-5 Flou Torus Iso i 2E11-F0073 2 3 4" no GV A N-26014 RNR P g Min 0 0/C etr mA Yes Note 4 D-6 Flou Torus Iso 2E11-F008 1 A 20" No GV A N-26015 R M 30C Outbrd C O/C CS PIV/CIV Yes CSJ-V-3 D-10 CIV 2E11-F009 1 A 20* M0 GV A N-26015 km 3DC Irdrd C O/C CS PlV Yes CSJ-V-3 D-10 PIV 2E11-F011A 2 s 4= no GV A N-26015 Run Cond Disch C C etr u Yes Note 4 D-3 to Torus 2E11 F011s 2 3 4" MO GV A M-26014 Reut Cond Diech C C Str NA Yes Note 4 D-8 to Torus 2E11 F015A 1 A 24" MO GV A N-26015 LPCI outbrd CIV C O/C etr PIV/CIV Yes NA D-T 2E11-F0158 1 A 24" MD GV A N-26014 LPCI outbrd CIV C 0/C Str PIV/CIV Yes WA ! D-4 l I 2E11 F016A 2 A 16" MD GLV A N-26015 Cent Sprey C O/C Str CIV Yes un , B-7 Outbrd CIV 2E11 F016e 2 A 16" MO GLV A M-26014 Cent Spray C O/C etr CIV Yes RA B-4 Outbrd CIV l l l
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Notch Nuclear Plant Unit 2 IST Program Pepe No. 19 of de
, Velve Test Tabte 11 - Revielen 0 ,
Vetve PS10/- It CC Cet Descriptlen Emercise L% ST Reserks A/P Coord Feetten MP SP Frog . Test Regd RE/CSJ/NOJ l M11-F01FA 1 3 24" No EV A 3-26015 LPCI O O etr M Tee M D-7 '.
- R11-F017B 1 5 24" MD E V A N-26014 LPCI O O etr M Yes M D-4 M11-F021A 2 B 14" MO SV A N-26015 Crust sprey C O/C etr M Yes M B-9 R11-FS218 2 3 14" MD GV A N-26014 Crust sprey C O/C etr M Yee m C2 2E11-F023 2 A 4" MD EV P N-26014 Pesolve CIV C C m CIV No m B-3 i
l M11-F024A 2 B 16" MD EV A N-26015 SPC C O/C etr m Tee Note 4 { C-6 l 2E11-F0248 2 8 14" MD EV A N-26014 SPC C O/C etr M Yes Note 4 0-6 2E11-F025A 2 C 1" RV A N-26015 LPCI RV C O/C Note 5 m m Note 4 C-7 2E11-F0258 2 C 1" RV A N-26014 LPCI RV C O/C Note 5 m m Note 4 C-4 M 11-F026A 2 3 4" MD GV A N-26015 Cand Disch to C C etr m Yes Note 4 D-2 RCIC 2E11-F0268 2 3 4" MD OV A N-26014 Cond Disch to C C Str M Yes Note & E-9 RCIC R 11-F027A 2 3 6" MD EV A N-26015 S w Poot sprey C O/C etr M 7ee m C-7 _ - _ - _ _ _ - _ - - - - - - - - - - - - - - - - - - - - - - ~ - - - ~
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Netch Nucteer Plant Unit 2 IST Program Page No. 20 of 60 Velve Test febte 11 - Revielen 0 volve P&tD/ Exercise teekage SF Remsete ID CC Cet Description A/P Coord Function MP SP Frog Test Regd NR/CSJ/n0J R11-F0273 2 3 6" MD eLV A N-26014 Sipp Poet sprey C (VC Str M Yee M D-5 R11-F0204 2 A 16" NO SW A N 26015 sw Poet sprey C 0/C etr CIV Tee m l C-6 Outbed Civ l 2E11-F02RB 2 A 16" MD GV A N-26014 Sigp Poet Sprey C O/C etr Civ Yee m C-7 Outbrd CIV 2E11 F029 2 C 1" W A N-26015 pm Pop Sue W C O/C mote 5 mA m note 4 E-9 I l 2E11 F0304 2 C 1" W A N-26015 RNR Pump suc W C O/C mote 5 m m note 4
- F-8
. 2E11-F0305 2 C 1" W A N-20014 RNR Pump Suc W C O/C Note 5 un m Note 4 ! F-4 l 2E11 F030C 2 C 1" W A N-26015 Rm Pup Sue W C O/C Note 5 NA m Note 4 F-10 2E11-F030D 2 C 1" W A N-26014 R m P g Sue W . 0/C C Note 5 m m Note 4 F-2 2E11-F051A 2 C 20" CV A N-26015 km Pop DIsch C O/C etr m m Notes 6,7 N-6 2E11 F031s 2 C 20" CV A N-26014 km Pop Diech C O/C Str NA NA Notes 4,7 N-6 2E11-F031C 2 C 20" CV A N-26015 RNR Pwp Diech C O/C Str m NA Notes 6,7 N-9 2E11 F0510 2 C 20" CV A N-26014 km Pop Disch C O/C etr -m m Notes 6,7 N-3
1 Netch Nutteer Plant tinit 2 IST Program Page No. 21 of M Velve Test Tebte 11 - Revision 0 Vetve P&lD/ Esercise Leekage ST Reserke O CC Cet Description A/P Coord Functlen NP SP Frog Test Rouyf RR/CSJ/ROJ 2E11-F040 2 3 4" NO SLV P N-26014 Rtut to RW Drain C C m m to Note 8 B-6 2E11-F061A 2 A 1" A0 Centrol A N-26015 Reut Inst Civ 0 0/C etr Civ Yee m A-4 2E11-F0618 2 A 1" A0 Centrol A N-26014 Reut Inst CIV O 0/C etr CIV Yes m A-6 2E11 F061C 2 A 1" A0 Centrol A W-26015 Rest inet CIV o 0/C etr CIV Yee m A-8 2E11 F0619 2 A 1" A0 Centrol A N-26014 Reut Inst CIV 0 0/C etr CIV Yes IIA A-3 2E11 F0644 2 C 3" CV A N-26015 RIut Min Floor C O/C DIIE NA NA ROJ-V-12 G-6 Line Note 9 2E11-F0664 2 C 3" CV A N-26014 RIut Nin Floor C O/C DifE IIA NA ROJ-V-12 N-5 Line Note 9 2E11-F046C 2 C 3" CV A N-26015 RINt Min Floor C O/C DifE NA NA ROJ-V-12 E-9 Line Note 9 2E11-F0660 2 C 3" CV A N-26014 RINt Nin Floor C O/C DINE IIA NA ROJ-V 12 G-2 Line Note 9 2E11-F067A 2 B 16" No GV A N-26015 Rent Na shell 0 0 etr NA Tee sen , E-5 side Intet ' 2E11 F0673 2 8 16" No GV A N-26014 Reut Na Shett 0 0 Str NA Yee len E-6 side Intet 2E11-F0484 2 B 24" NO GLV A N-26015 RIut Nx shett 0 0/C etr IIA Yee isA ' D-5 side typese
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- o Netch Nucteer Plant Unit 2 IST Progree Pope No. 22 of 60 O
Vetve Test Telde 11 - Revlelen 0 Volve PSIO/ Exerclee Leeltage ST Resorte 19 CC Cet Deectlption A/P Coord Ftmetton MP SP Frog Test Regd- RR/CSJ/ROJ M11-FM85 2 3 M" 40 SLV A N-26014 RNR Na Shett 0 0/C etr .M Yes NA E-6 Side typoos C11-FM9 2 3 4" NO SW P N-26014 RNR to RW Drain C C M M4 No Note 8 B-5 M 11-F0504 1 AC 18" CV A N-26015 LPCI PIV l C O/C RR-V-10 PIV m RR-V-10 D-9 2E11-F0505 1 AC 10" CV A N-26014 LPCI PtV I C O/C RR-V-10 PIV NA RR-V-10 i D-3 2E11-F055A 2 C 4" RY A N-26015 RNR Nx Shett RV C O/C Note 5 NA E Note & F-4 2E11-F0558 2 C 4" RV A N-26014 RNR Rx Shett RV C O/C Note 5 NA NA Note 4 F-7 2E11 F065A 2 B M" A0 SFV P N-26015 RNR Pw p suct 0 0 #4 m No Note 8 I F-8 Melnt i 2E11-F0658 2 B M" A0 SFV P N-26014 RNR P g suct 0 0 NA NA No Note 8 F-3 Melnt 2E11-F065C 2 5 M" A0 SFV P N-26015 RNR Pup Suct 0 0 NA NA No Note 8 F-9 Neint ' t 2E11-F0650 2 3 M" AO BFV P R-26014 RNR Puup suct 0 0 NA NA - No Note a F-2 Melnt , 2E11 F0604 3 8 10" MD Bell A N-21039 RNR Na Ser Utr C O/C 9tr NA Yes NA C-10 Disc L 2E11-F0605 3 5 10" MD sett A N-21039 RNR Na See Wtr C O/C etr NA Yes NA E-10 Oloc
__ _ _ . . . . _ _ .__m. .. ._ _ . . _ _ _ _ . _ _ _ _ _ m. O Netch Nucteer Plant thit 2 IST Program Pege me. 25 of 60 l Vetwo Test Tabte 11 - Revielen 6 i l Velve P&lD/ Exercise Leekese SY Reserke '. IS CC Cet Description A/P Coord Function WP SP Freq Test Rogd RR/CSJ/WOJ ! 2E11-F073A 2 3 10" MO SV A N-26015 RNRsW to RM C O/C etr M Yee m G-4 Creestle 2E11 FOT38 2 8 10" MO SV A N 26014 RNRev to R M C O/C etr M Yee m i G-T Crosette 2E11-F075A 2 3 10" MO SV A N-26015 RNRsu to RNR C O/C etr u Yee m , C-4 Crosette 2E11 F0758 2 8 10" MO SW A N-26014 RNR9W to RNR C O/C M etr Yee m 0-7 Croestle i
.2E11-F078A 2 C 10" Test CV A N-26015 i
RumsW to RNR C O/C DINE m m notee 9.10
- E-4 Crosette i
2E11-F07E5 2 C 10" feet CV A N-26014 RNR9W to RM C O/C DINE m m Notee 9.10 E-T Crosette 2E11-F091A 2 3 6" MO RV P N-26015 Steam Line to C C m M No Note 4 l l E-2 RM Na shutdown 2E11-F0918 2 5 6" MO RV P N-26014 Steen Line to C C m m no Note 8 E-9 RM Na Shutdoom i 2E11-F097 2 C 3" RV A N-26014 Steen Line RV C O/C mote 5 m m note 4 E-9 ' 2E11-F103A 2 3 1* MO RV A M-26015 RM Na Vent Iso C C etr M Yee note 4 E4 j 2E11-F1038 2 3 1" MO RV A N-26014 R M Na Vent too C C etr M Yes Note 4 - l E-T 2E11 F1224 1 A 1" A0 Plus P N-26015 Pesolve PIV C C m PIV no note 3 D-8 i
m Netch Nutteer Plant imit 2 IST Prograo . Pese no. M of 60 Velve Test Tetde 11 - nevielen 0 Vetve PSID/ Exercise Leekage ST Resorts ID CC Cet Description A/P Coord Functlen MP SP Frog Test . Req 6 RR/CSJ/40J 2E11-F122B A 1" A0 Plus N-26014 1 P Pesolve PIV C C m PIV se note 8 D-3 M11 F124A 2 C 2" Step CV A N-26019 Melnteln RM O/C C Str m m Note 11 D-4 Water Level 2E11-F1248 2 C 2" Stop CV A N-26019 Mainteln anR ' 0/C C Str M m . Wete 11 D-6 Water Levet
O O O. Match Nucteer Plant Unit 2 IST Program Page No. 25 cf 60 Velve Test Table 11 - Revision 0 Velve PSID/ Exercise Leekage ST Romerks ID ' CC Cat Description A/P Coord Function NP So Freq Test Reqd RR/CSJ/ROJ 2E21-F001A 2 5 20a MO GV A H-26018 CS Ptap Suct 0 0/C Otr NA . Yes . Note 4 G-7 Iso 2E21-F0010 2 a 20" MO GV A M-26018 CS Ptsp Suct 0 0/C Str NA Yes~ Note 4 H-7 Iso 2E21-F003A 2 C 12" CV A H-26018 CS Ptap Disch C O/C Otr. NA NA Notes 7,12 i F-7 2E21-F0035 2 C 12" CV A N-26018 CS Ptap Disch O/C C Qtr NA NA Notes 7,12 F-9 2E21-F004A 1. B 10" M0 GV A H-26018 CS Outbrd 0 0 Qtr - NA Yes NA E-6 Inject 2E21-F0048 1 8 10* MO GV A H-26018 CS Outbrd 0 0 Otr NA Yes MA i C-6 Inject 2E21-F005A 1 A 10" MO GV A H-26018 CS Inbrd Inject C O/C Qtr PIV/CIV Yes NA E-5 2E21-F0058 1 A 10" MO GV A H-26018 CS Inbrd Inject C O/C Qtr PIV/CIV Yes NA f C-5 2E21-F006A 1 AC 10" CV A H-26018 CS Inject O/C C RO PIV NA ROJ-V-13' D-4 2E21-F0065 1 AC 10" CV A H-26018 CS Inject C O/C RO PIV NA -20J-V-13 D-4 2E21-F012A 2 C 2" RV A H-26018 CS Puup Disch C O/C Note 5 NA NA NA E-7 RV 2E21-F0123 2 C 2" RV A H-26018 CS Ptap Disch C Note 5 O/C NA NA NA B-7 RV
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O O Netch Nucteer Plant tinit 2 IST Program Pese No. 26 of de Vetve Test Tatde 11 - Revisten 0 Vetwe PSID/ Emerefoe Leekage ST' Romerts O CC Cet Beecription A/P Coord Fwuction MP SP Frog Test Regd RR/CSJ/NOJ N21-F0154 2 3 10" NO SLV A N-26018 CS Test Bypees C C etr u Yes Wete 4 D-T leo 2E21-F015s 2 e 10" NO SLV A N-26018 CS Test Bypees C C etr M Tes Note & D-T leo 2E21-F0184 1 AC 1" EFCV A N-26018 Inst EFCV O- C RO LTV NA NOJ-V-3 B-3 2E21-F0185 1 AC 1" EFCV A N-26018 Inst EFCW 0 C NO LTV NA ROJ-V-3 5-3 2E21-F018C 1 AC 1" EFCV A N-26018 Inst EFCV O C RO LTV m NOJ-V-3 E-4 2E21-F019A 2 3 16" A0 SFV P N-26018 CS Suct 0 0 NA NA No Note 8 N-5 2E21-F0195 2 B 16" A0 SFV P N-26018 CS Suet 0 0 NA NA No Note 8 G-5 2E21-F031A 2 5 3" NO GV A N-26018 CS Pump Min 0 O/C Str NA Yes NA F-8 Flow 2E21-F0313 2 3 3" ND GV A N-26018 CSPopMin 0 0/C Str NA Yes NA F-9 Flow 2E21-F032A 2 C 1" RV A N-26018 CS Suct RV C ' O/C Note 5 NA NA NA G-8 2E21-F032s 2 C 1" RV A N-26019 CS Suet RV C O/C Note 5 NA NA NA G-9 2E21-F036A 2 C 3" CV A N-26018 Min Flow Line C ' O/C DINE NA NA Notes E-8 too 4,9,13 ROJ-V-28 I
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Netch Nucteer Plant Unit 2 IST Progres . Pese No. 2T of 60 Velve Test Telde 11 - Revielen 0 Velve PSIO/ Enercise Leekage ST Reencke B CC Cet - Dooeription A/P Coord Feetten MP SP Frog Test Reqd AR/CSJ/ROJ
~2E21-FS360 2 C 3* CV A N-26018 Min Flou Line C O/C DIIE IIA IIA Notes E-9 Iso 4,9,13 ROJ-V-28 2E21-F037A 1 A la A0 Plte Viv P N-26018 Pesolve Iso C C NA ' PIV ilo Note 8 D-4 2E21 F0373 1 A la A0 Plus vtv P N-26018 Pesolve too C IIA C PIV Ile ilote 8 C-4 2E21-F0404 '2 C 1-1/2" Step CV A N-26019 Italnteln CS 0/C C Str NA IIA Note 11 D-5 Water Level 2E21-F0405 2 C 1 1/2" Step CV A N-26019 Melnteln CS 0/C C Str IRA NA IIete 11 D-6 Water Level 2E21-F044A 2 C 1-1/2" Step CV A N-26019 Jockey Pump 0 C 30 NA - IIA 30J-V-14 E-1 Bypeos too Note 4 l 2E21-F0448 2 C 1-1/2" Stop CV A N-26019 Jockey Ptsp 0 C RO NA NA ROJ-V-14 E-9 Bypees Iso Note 4 I
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O O Netch Nucteer Plant Urtit 2 IST Program C Page No. Es of 60 Vetve Test Table 11 - Revision 0 Velve PRID/ Exerclee Leekene ST Reserks ID CC Cet Description A/P Coord Fmction WP SP Frog Test Reqd RR/CSJ/NOJ 2E41 9003 2 D 16" W A N-26021 Turbine Edoust C O/C Note 14 M M NA D-6 RO 2E41-9004 2 9 16" RD A N-26021 Turbine Enhoust Note 14 C O/C NA M M E-6 2 2E41 F001 2 5 10" MO GV A N-26020 Steen S w ty C 0 etr M Yes NA E-10 Shutoff 2E41 F002 1 A 10" MD GV A N-26020 Steen S w ty 0 0/C CS CIV Yes RR-V-1 C-3 Ir6rd CIV CSJ-V-6 , 2E41-F003 1 A 10" MO SV A N-26020 Steam S w ty 0 0/C Str Civ Yes NA C-4 Outbrd CIV 2E41 F004 2 3 16" MO GV A N-26020 Puup Suc from 0 0/C Str NA Yes NA D-7 Cond Stor 2E41 F005 2 AC 14" CV A N-26020 Pw p DIsch C O/C etr Ptv NA Note 15 E-3 2E41-F006 2 A 14" No sv A N-26020 Puup tr6rd C O/C Str etV Yes NA E-4 Disch Iso 2E41-F007 2 B 14" MO GV A N-26020 Pu p Outbrd 0 0 Str NA Yes NA E-5 DIsch 2E41 F008 2 5 10" MD SLV A N-26020 Pw p Test C C Str NA Yes NA D-6 Bypees 2E41 F011 2 3 10" MO GV A N-26020 Po p Test C C etr NA Yes Note 16 C-6 Bypese 2E41 F012 2- S 4" MO SLV A N-26020 Ptep Min Flow C O/C Str NA Yee pote 4 F-6 tr6rd too
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\j V Netch mucteer Plant tinit 2 IST Program Page No. 29 of 60 vetvs Test falde 11 - Revleton 0 volve PRIS/ Emercise Lookese ST Resorte 19 CC Cet Description A/P Coord Feetten NP SP Frog Test Rayf RR/csJ/ROJ M41 F019 2 C 16" CV A N-26020 Ptsy Sue Cond C 0 Otr m NA Note T D-T Stg 2E41-F020 2 C 1 1/2" RV A N-26021 Ptap Suctlen RV C O/C Note 5 m NA NA B-6 2E41-F021 2 C 12" Step CV A M-26020 Turb Enh tr6rd C O/C Note 15 NA NA ROJ-V 15 G-3 Iso Notes 4,17 .
2E41-F022 2 C 2" Stop CV A N-26020 Turb Enh Dm C O/C DIE NA NA Notes G3 Torus too 4,9,17 ROJ-V-16 2E41-F024A 1 AC 1" EFCV A M 26020 Inst EFCV 0 C RO LTV NA ROJ-V-3 C-4 2E41-F0245 ! 1 AC 1" EFCV A N 26020 Inst EFCV O C RO LTV NA ROJ-V-3 I D-4 5 2E41-F024C 1 AC 1" EFCV A N-26020 Inst EFCV O C RO LTV NA ROJ-V-3 C-4 2E41*F0240 1 AC 1" EFCV A M-26020 Instr EFCV O C R0 LTV NA ROJ-V-3 E4 t 2E41-F028 2 5 1" A0 GLV P N-26020 Drain Pot Drain 0 0 NA NA No Note 8 G-10 2E41-F029 2 8 1" A0 GLV P N-26020 F-10 Drein Pot Drain 0 0 NA NA h Note 8 i 2E41 F040 2 C 2" CV A M-26020 Turb Enh Drn C O/C DINE NA NA ROJ-V-17 G-4 Torus Iso f' Notes r 4,9,15 2E41 F041 2 0 16" NO EV A M-26020 Ptap suc Supply C 0 Otr NA Tee NA = D-T .
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- Notch Nucteer Plant Unit 2 IST Progren Pese No. 30 of 6e Velve Test Tebte 11 - Revielen 0 Vetve PSIO/ Emercise Leekese ST Reuerte 10 CC Cet Description A/P Coord Ftmetten MP SP Frog Test Rogd- int /CSJ/ROJ l
2E41 F062 2 3 16" NO SV A N-26020 Pisup Sue focus C O/C etr M Yes Note 4 N-4 Outbrd too , C41 F065 2 C 16" CV A N-26020 Pump Sue 0 C DIME M M M V-F N-5 Note 9 2E41 F066 2' C 4" CV A N-26020 Pisgn Min Fleu C O/C BIM M M ROJ-V 18 F-6 Outbrd Iso Notes 4,9 2E41-F068 2 C 2" CV A N-26021 Lidge Ott C 0 DINE M NA Note 9 I G-8 Cooting Utr Return CV l l 2E41 FM 9 2 C 20" CV A N-26020 Turb Enh Outbrd C. 0/C Note 15 m M ROJ-V-19 l G-4 Iso Note 4 i t 2E41 F050 2 C 2" RV A N-26021 Lidse Olt Cooler C O/C Note 5 M M NA G-8 RV i 2E41-F051 2 3 16" A0 BFV A N-26020 Piep Sue foruo 0 0/C Str NA Yes Wete 4 ; N-4 Irdprd leo i 2E41-F052 2 C 2" CV A N-26021 Beremetric Cond C C i Str NA NA Note 18 j G-9 Pisup Disch 2E41-F057 2 C 2" CV A N-26021 LtApe Oil i C 0 DIM NA NA Note 9 G-9 Cooling Utr . Return CV 2E41 F059 2 B 2" MD GLV A N-26021 Turb Ltime Olt C 0 etr N4 fee NA F-7 Cooling 2E41-F102 2 C 1" CV A N-26020 Vacuus RV C O/C RO NA NA ROJ-V-25 F-2 2E41-F105 2 C 1" CV A N-26020 Vacuus RV C O/C RO NA NA . ROJ-V-25 i F-2 '
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Netch Itucteer Pt- t Unit 2 IST Program Page No. 31 of 40 Vetve Test Table 11 - Revielen 8 . Volve PilD/ Emereise Leekage St Romerte O CC Cat Deecription A/P Coord Fametten IF SP Freq Test Regl N/CSJ/ROJ 341 F194 2 A 2* MD sv A N-26020 vec Retlef 0 C Str Civ Yes NA F-2 outbrd Torus CIV M41-F111 2 A 2* MO GV A N-26020 Vee Relief 0 C etr CIV Yes IIA G-1 Irded focus CIV M41-F121 2 A 3/8" 30t A N-26304 Psee Sagde C C etr CIV Yes NA N-9 Return M41-F122 2 A 3/8" SOW A N-26384 Paet Semple C C Str CIV Yes IIA N-9 Return i
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O-Netch Nucteer Plant imit 2 IST Program Pepe No. 32 of 60 velve Test Table 11 - Revielen 0 Velve P&lDI Emerefoe O Leekage ST Reserks CC Cet Description A/P Coord Fection WP SP Frog Test Reqd RE/CSJ/ROJ 2E51-F001 2 C 10" Step CV A N-26023. Turb Enh t erd C O/C Note 15 M M ROJ-V-20 G-5 Iso Notes 4,17 2E51 F002 2 C 2" Stop CV A N-26023 ! Turb Enh Drn C O/C R0 M M ROJ-V-21 F-5 Torve Iso i Notes 4,17 M51-F003 2 3 6" A0 BFV A M-26023 Ptop suct Terue 0 O/C etr M Yes Note 4 N-7 1 2rd Iso 2E51-F007 1 A 4" MO GV A N-26023 Steam SLgiply 0 C CS CIV Yes RR-V-1 C-5 lerd CIV CSJ-V-6 2E51 F008 1 A 4" MO GV A N-26023 Stees Supply 0 C etr CIV Yes M C-6 Outbrd CIV 2E11 F010 2 5 6" MD GV A N-26023 Pimp Sue from 0 0/C etr M Yes Note 16 C-8 Cond Stor M51 FC11 2 C 6" CV A N-26023 Puup Sue Cond C 0 Str M M Note 16 C-8 Stor M51 F012 2 B 4" MO GV A N-26023 Ptop outbrd 0 0 etr M Tee Note 16 D-6 Disch 2E51 F013 2 A 4" MD GV A N-26023 Ptsup Isrd C O/C etr PIV Yes M D-6 Disch PIV M51-F014 2 AC 4" CV A N-26023 Pimp Disch C O/C etr PIV M Note 15 0-6 M51-F017 2 C 1" RV A N-26024 Puup Suet RV C O/C Note 5 M M Note 16 E-6 M51-F019 2 3 2" MD ELV A N-26023 Puup Min Flou C O/C Str M Yes Note 4 ' E-7 Irdprd Iso
( ) b/ \.,/ s Netch Nucteer Ptervt Unit 2 IST Progree Pese No. 33 of es Velve Test Tehde 11 - Revlelon 0 Velve P61D/ Emercise Leekage ST 19 CC Cat Description A/P Coord Fleiction WP Remarks SP Frog Test Reqd RR/CSJ/90J 2E51 F021 2 C 2" CV A N-26023 Po p Min Flow C DIE M EVC
- M ROJ-V-22 E-7 Outbrd Iso
- Notes 4,9 2E51-F022 2 3 4* MD CLV A N-26023 Pump feet C C etr M Tee Note 16 C-6 Dypees 2E51-F928 2 C 2" CV A N-26023 Turb Enh Drn C C R0 M M 20J-V 23 F-7 Note 4 2E51-F029 2 8 6" MO GV A N-26023 Pop sue C O/C etr M Tee Note 16 C-8 shutoff 2E51 F030 2 C 6" CV A N-26023 Puup Suet C 0 DIME NA NA Notes 16, N-8 19 2E31-F031 2 5 6" MO SV A N-26023 Ptap Suet Torus C O/C Str NA Tee Note 4 N-7 Outbrd Iso 2E51 F040 2 C 10" CV A N-26023 Turb Enh Outbrd C O/C Note 15 NA NA ROJ-V-24 F-5 leo Note 4 2E51 F044A 1 AC 1" EFCV A N-26023 trist EFCV 0 C 20 LTV NA ROJ-V-3 A-5 2E51-F044s 1 AC la EFCV A N-26023 Inst EFCV O C RO LTV M ROJ V-3 5-5 2E51-F044C 1 AC l' EFCY A N-26023 Inst EFCV 0 C R0 LTV NA ROJ-V-3 t-5 2E51 F0440 1 AC 1* EFCV A N-26023 Inst EFCV O C RO LTV NA ROJ-V-3 3-5 2E51 F045 2 3 4' MD CLV A N-26024 Steen Sg pty C O/C Str NA Yes Note 16 C-10 shutoff
Netch Nucteer Plant tinit 2 IST Program Page me. 34 of de . Vetve Test Tabte 11 - Revielen 0 Velve PSID/ Exerclee Leekage ST Resorts O CC Cet Description A/P Coord Fwiction MP SP Freq Test Regd RR/CSJ/WOJ 2E51-F064 2 B 2* NO SLV A N-26024 Turts Lthe Oil C 0 Str M Tee Note 16 " D-6 Cooting 2E51-F067 2 C 2" CV A N-26024 Lthe of t C C DINE M M Wotes 16, G-7 Cooting Utr 19 Return CV 2E51 F102 2 C 1 1/2" CV A N-26023 voeten tellef C O/C R0 M M Wotes 16, F5 20 2E51-F103 2 'C 1 1/2* CV A N-26023 vectam Relief C O/C RO M M Notes 16, F-5 20 2E51-F104 2 A 1 1/2" No GV A N-26023 Vec Rollef 0 O/C Str CIV Yes M F-5 Outbrd focus CIV 2E51-F105 2 A 1 1/2" NO GV A M-26023 Vec Relief 0 O/C Str CIV Yes M
- F-4 Irtrd forus CIV
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Netch Nucteer Plant Unit 2 IST Progree Page so. 35 of 60 vetve Test Teide 11 - Revielen 0 ' Velve P8tD/ Emercise Leekage IT Resorte It CC Cet Deecription A/P Coord Fametion NP SP Frog Test Reqd M/CSJ/WOJ M11-F003 2 A 4" A0 SV A N-260M M Ftr Drne CIV O C Str CIV Yes M , B-3 2811 F004 2 A 4" A0 GV A N-26026 W Flr Drne CIV O C Str CIV Yes M 9-4 2011 F019 2 A 4" A0 CV A N-26026 W Egip Drne O C Str CIV Yes - M E-4 CIV 2811 F020 2 A 4" A0 SV A N-26026 W E p fp Drne O C Str CIV Yes M E-4 CIV 2811-F852 2 A 1-1/2" Men SV P N-26026 Poestve CIV LC C M CIV No M E-11 2811-F853 2 A 1-1/2" Hon SV P N-26026 Poestve CIV LC C M Civ se M D-11 l l
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i N , hetch Nucteer Plant Unit 2 IST Program Page me. 36 of 40' volve Test Tabte 11 - Revielen 0 volve . P6tD/ Emerefoe Leekage ST temorts it CC Cet Beecription A/P Coord Ftmetion WP SP Frog Test Regd- RR/CSJ/WOJ 2831-F001 1 A P No eV A N-26036 Rutu Po p suc e C CS Civ Yes CSJ-V-T C-2 Irtrd CIV 2E31-F904 1 A P M0 SW A N-26036 RutU Puup Sue O C CS CIV Yes CSJ V-7 C-3 Outbrd CIV i i s f i i i I i 6
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O. O O Netch Nucteer Plant imit 2 IST Program Page No. 3T of 60 Velve feet Totde 11 - Revielen 8 - volve PSIsf Emerclee Leekage ST Romerte O CC Cet Deserfption A/P Coord Feetten MP frog SP Test -Regg enjggafsos 2451-F011 2 3 3* Ao control P N-26062 Poselve Cent C C m m 'ee Notes 4,8 C-5 andr 2e51-F012 2 e 3" A0 Centrol P N-26062 Poselve Cent + C C m m Yes Notes 4.0 C-5 andy 2451 F013 2 3 3" A0 Centrol P N-26042 Paeolve Cent C C m M Yes Notes 4,8 C-2 andr 2851 F017 2 3 38 A0 Centrol P N-26042 Poselve Cent C C m M Yes Notes 4,8 C-2 andr
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(vT (~ O Netch Nucteer f tent imit 2 IST Program Pase.No. 39 of 6e vetve Test Tetde 11 - Revielen 0 Velve P&ID/ Exercise Leekage ST Reserks IS CC Cet. Description A/P Coord Functlen NP SP Frog Test Respi M/CSJ/M0J 2P33-F002 2 A 18 A0 RV A N-26068 N2 & O2 Anoty 0 O/C Str CIV Yes M S-4 CIV 2P33-F003 2 A 1* A0 RV A N-26068 N2 & O2 Anoty C - 0/C Str CIV Yes M C-4 CIV 2P33-F004 2 A 1" A0 RV A N-26048 N2 & O2 Analy - 0 0/C Str CIV Yes M D-4 CIV 2P33-F005 2 A la A0 RV A N-26068 N2 4 02 Analy 0 0/C Str CIV Yes M E-4 CIV 2P33-F006 2 A 18 A0 RV A N-26068 N2 & 02 Analy C O/C Str CIV Yes NA F-4 CIV 2P33-F007 2 A 18 A0 RV A N-26048 N2102 Anaty 0 0/C Str CIV Yes m N-4 CIV 2P33-F010 2 A 1" A0 RV A N-26068 N2 8 02 Analy 0 0/C Str CIV Yes m s-5 CIV 2P33-F011 2 A 18 A0 RV A N-26048 N2 & O2 Analy C O/C Str CIV Yes NA C-5 CIV 2P33-F012 2 A 1" A0 RV A N-26068 N2 & 02 Analy 0 0/C Str CIV Yes NA D-5 CIV 2P33-F013 2 A laA0RV A N-26048 N2 & 02 Analy 0 0/C Str CIV Yes NA E-5 CIV 2P33-F014 2 A 1* A0 RV A M-26048 N2 & 02 Analy C O/C Str CIV Yes NA F-5 CIV 2P33-F015 2 A 1" A0 RV A N-26068 N2 & O2 Analy 0 O/C Str CIV Yes NA N-5 CIV Fe I l . - - . -_ _ _ _ -.. .
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_ _ _ . . - . _ _ -~~ - - - - - - - - - - - -- - - ' ~~ ' ' Netch Nucleor Plant INilt 2 IST Program Page No. 41 of de Velve Test Table 11 - Revlelen 0 Vetve PS10/ toercise Leekage ST Remarke 19 CC Cet Description A/P Coord Feetten MP SP Frog Test Regi RR/CSJ/ROJ 2P41-F064 3 C 10" CV A N-26050 Divlelen 1 W - 0 0 DINE M M Wote 9 E-10 Sigpty 2P41-F065 3 C 10" CV A N-26051 DIvielen 2 W 0 0 DIM M M Note 9 B-10 sigpty I 2P41-F066 3 B 10" A0 SFV P N-26050 W to ESF 0 0 -M NA No Note S E-10 Cooters too 2P41-F067 3 3 10" A0 SFV P N-26051 W to ESF 0 0 m M No Note 8 B-10 Coolers Iso 2P41 F098 3 C 4" CV A N-26051 Centret am WAC 0 0/C DINE E M Note 9 i 33 -- 2P41 F105 3 C 3" CV A N 26050 Centrol Rm NVAC 0 0/C DIME M M Note 9 F-4 , 2P41-F115A 3 5 4" NO SV A N-26050 Ese LPCI Inv C O/C Str M Tee M F-6 Inlet Iso 2P41-F115e 3 e 4" NO sv A N-26051 Ese LPCI Inv C c/C etr M Tee M A-3 Inlet too 3 2P41-F306A 3 C 1-1/2" CV A N-21033 Service Wtr 0 0 etr M M Note 22 B-7 Noter Cooling 2P41-F306e 3 C 1-1/2" CV A N-21033 torvice Utr t 0 0 etr M M Note 22 8-7 Noter Cooling 2P41 F310 3 C 30" NO SFV I P N-21053 W Ditutlen C C M M No Note 8 F-8 Line leo 2P41-F311A 3 C 18" CV A N-21033 W Pup Disch O/C O/C Str M M Note 6 ' B-3 i u_________ ____ _ - . . , , - __. _ . _ _ _ _ _ _ _ _ _ _ __ _. . = . . . . - - - , . . . . . .._ - . - . . -
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Netch sucteer Plant Unit 2 Isf Progree -Page No. 42 of de vette Test Tetde 11 - Revielen 9 Volve PSIDI Emercise Leekage si Resorts-ID CC Cet Description A/P Coord Ftmetton MP SP Frog Test Reqd RR/csJ/90J 2P41-F3118 3 C 18" CV A N-21033 W P g elech 0/C O/C M M (tr Nete 4 E-3 2P41-F311C 3 C 18" CV A N-21033 W Po p Disch O/C O/C m etr mA note & I C-3 l l 2P41-F3110 3 C 18" CV A N-21033 W Pu p Diech O/C O/C etr M M mote 6 ( F-3 l 2P41-F312A 3 3 8" M0 BFV P N-21033 W to DG 24 0 0 m M We Note 8 E-9 l 2P41 F3125 3 A 8" MD SFV P N-21033 W to N 2C 0 0 m at to note 8 - i 8-8 2P41-F315A 3 5 10" No BFV P N-21033 m to Rx etds 0 0 m NA no note 8 A-9 Iso l 2P41-F313e 3 5 10" No BFV P N-21033 m to ax stds 0 o m m no note 8
- F-9 leo j 2P41-F316A 3 5 30" MD BFV A N-21033 W to Turbine O C CS m Tee CSJ-V-9 A-9 Stds Shuteff '
2P41-F3160 3 5 30" MO SFV A N-21033 W to Turbine O C Cs m Tee CsJ.V 9 i F-9 Bt4 Shutoff i 2P41-F316C 3 5 30" MD BFV A N-21033 W to Turbine O C Cs M ves tsJ-V-9 A-10 Btde shutoff 2P41 F3160 3 5 30" MD OFV A N-21033 W to Turbine O C Cs M Tee CsJ-V-9 F-10 side Shutoff 2P41-F321 3 C 6" CV A N-21033 StbF Dieset W C O/C etr m NA Notes T.35 J-2 Pu p Disch L
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O O Netch Nucteer Plant Iktit 2 IST Progree' Pese to. 43 of 40 i Velve Test Teide 11 - Revision 9 .
'Velve PSID/' Exerclee ST. Reserks Leekese 19 CC Cet Description A/P Coord Ftmetten NP SP Frog Test Reqd RR/CSJ/ROJ 2P41 F33M 3 8 P A0 BFV A W-21033 Dieset een C 0 etr a4 Yes mR-V-8 N-9 Cooling 2P41-F339e 3 3 6" A0 BFV A n-21033 Olesel een C 0 etr un Yee at-V-8 N-7 Cooling IP41-F340 3 3 6" A0 BfV A N-11400 Dieset een C 0 etr NA Yes at-V-8 s-5 Cooline I
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V l Netch nueteer Plant thlt 2 IST Program ! Page me. 44 of de Velve Test Telde 11 - Revision 0 Velve PS10/ Exercise Leekepe ST Reemrts
- 19 CC Cet Descriptlen A/P Coord Feetten WP ' SP Frog Test Reqd ARICSJ/a0J 2P42 F051 -2 A 6" MD GV A N-26055 metCW to Recir o C CS CIV Yes CsJ-V-10 35 CIV I
2P42-F052 2 A 6" MD GV A N 26055 settu to Recir o C Cs CIV Yes . CsJ-V-10 C5 Civ 2P42-F0E5 2 C 1 1/4" RV A N-26055 Thenuet RV C O/C mote 5 m m m C-4 I . 6 l i I
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N notch sucteer Plant thtt 2 IST Progree Page us. (5 of 60 vetve Test Tabte 11 - Revielen 0 ( l Vetve P&lB/ Emercise Leekage ST Reserks ID CC Cet Description A/P Coord Fametten WP SP Frog Test Respi RR/CSJ/WOJ 2P51 F513 2 A 2" Iten OLV P R-26058 Poselve CIV LC C M~ CIV no m ( F-3 2P51-F451 2 A 2* Igen SLV P g.26058 PoesIve CIV LC C m CIV no u l F-3 i i l i l l 4
Retch Nucteer Plant thIt.2 IST Program Page No. 46 of 60 Velve Test Tetdo 11 - Novielen 0 Velve PSID/ Eserclee Leekage ST Nemorts O CC Cet Description A/P Coord Ftmetlen MP SP Frog Test - Regd NN/CSJ/NOJ 2PS2-F346 - C 1* CV N-26064 A Accum A003 0/C C m Note 31 m Note 30 G-9 Intet CV 2P52-F349 - C 1" CV A N-26064 Accus A004 0/C C m Note 31 m Note 30 F-9 Intet CV
'2P52-F414 -
C la CV A N-26070 Accum A015 0/C C m Note 32 m Note 30 N-7 Intet CV 2P52 F419 - C 1" CV A N-26070 Aceta At?4 O/C C m Note 32 m Note 30 F-7 Intet CV 2P52-F450 - C 1" CV A N-26070 Ac w A013 O/C C m Note 32 m Note 30 N-5 tr.<et CV 2P52-F441 - C 1" CV A N-2607C Accus A014 O/C C E Note 32 m Note 30 N-5 Intet CV 2P52-7601 - C 1" CV A M-WA64 Accus A017 O/C C E Note 32 m Note 30 F-3 Intet CV 2PS2-F971 - C 1" CV A N-26070 Accus A018 0/C C m Note 32 m Note 30 1-7 Intet CV
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- O Notch Nucteer Plant Unit 2 IST Program Page No. 47.ef 60 Velve Test Tedde 11 - Revlelen 9 Velve PSID/ Emercise Leekage ST Reemrts 19 CC Cet Description A/P Coord Fametten WP SP Freq Test Regf RS/CSJ/WOJ 2PM-Ft45 2 A P MD SLV A N-26001 thitted Water 0 C CS CIV Yes CSJ-V-8 N-2 CIV '
2P64-FM7 2 A P MO SLV A N-26081 Chitted Water O C CS CIV Tes CSJ-V-8 G-11 Civ 4 t
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O O . O Netch Nucteer Plant linit 2 IST Program Page me. 44 of as . Velve Test TeMe 11 - Revielen 0 Velve P610/ Emercise Leekage. ST. Reemrts 10 'CC Cet Description A/P Coord Function NP SP Frog Yest Regf RR/CSJ/90J 2P N F982. 2 A 18 AS SLV P N-26066 W Pneametic C C M Civ -M Isote S F-8 CIV 2P70-F003 2 A 1" A0 SLV P N-26066 W Pnetantle C C HA CIV M Ilote B ' F-8 CIV 2P79-F004 2 A 2" SUV A N-26066 W Pnstmatic 0 C Str CIV Yes IRA 3-9 CIV ' 2P79-F005 2 A 2* SUV A N MMA W Pneuestic 0 C Str CIV Yes M B-9 CIV i 2P79-F066 2 A 2* SOV A N-26066 W Pneametic 0 C Str CIV Yes M D-9 Civ 2P79-F067 2 A 2" SOV A N-26066 W Pneumatic 0 C Str CIV Yes IIA D-9 CIV +
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patch Nutteer Plant Unit 2 IST Progree Pope No. 49 of 60 velve Test Table 11 - Revielen 0 Velve P4tD/ Exercise Leekage $7 Rennete ID ' CC Cet Description A/P Coord Fwictlen EP SP Freq Test Regl RR/CSJ/ROJ 2R43-F0124 - C 2" CW ' A M-21074 M Fuet oft C O/C Str M M4 Notes N-10 Pw p Bloch CV 16,23 2R43-F0128 - C 2" CV A M-21074 M Fuet Olt C O/C etr NA NA Notes M-9 Pw p Bloch CV 16,23 2R43-F012C - C 2= CV A M-21074 M Fuet 011 Day C O/C 9tr NA NA Notes N-8 Tank Intet CV 16,23 2R43-F012D - C 2* CV A N-21074 M Fuet Olt Dey C O/C Str NA NA Notes N-7 Tank Intet CV 16,23 2R43-F0134 - C 2" CV A N-21074 M Fuet 011 C O/C Str M NA Notes F-10 Pw p Disch CV 16,23 2R43 F0135 - C 2* CV A N-21074 M Fuet 011 C O/C Str NA NA Notes F-10 Pw p Disch CV 16,23 2R43 F013C - C 2" CV A M-21074 M Fuet 011 Dey C O/C Str NA NA Notes F-8 Tank Intet CV 16.23 2R43-F01D i C 2" CV A R-21074 M Fuel Olt Dey C O/C etr NA NA Notes F-8 Tank Intet CV 16.23 2R43-F029A - C 3/4" CV A M-21074 Air Receiver C C Note 25 NA NA Note 16 C-10 Intet CV 2R43-F029C - C 3/4" CV A M-21074 Air Receiver- C C Note 25 NA NA Note 16 C-10 Intet CV 2R43-F032A - C 1/2" RV A N-21074 Air Receiver RV C O/C Note 34 NA NA Note 16 3-9 i 2R43-7032C - C 1/2" RV A N-21074 Air Receiver RV C O/C Note 34 NA NA Note 16 3-9 _ . - _ _ _ _ _ _ _ -- , . , . . r ., , ., , , - . , ,
_ . ._ . . . . -. . . . . _ . . _ _ . . . - . . . . . _ . . _ . . . - . _ , _ _ _ _ . . _ _ . - . . _ . . _ . . .___1___m , m _. m O Q~% - Netch Nucteer Plant tinit 2 IST Program Page No. 50 of M Velve Test Telde 11 - Revielen 0
- Velve PGIDI Emerclee Leekege ST Resorts-O CC Cet Description A/P Caerd Functlen MP SP Freq Test Recyl RE/CSJ/WOJ 2R43-F8534 - C 1/2" W A N-210M Air Receiver W C O/C Note 34 m m Note 16 t 3-11 2R43-F853C -
C 1/2" RV A N-210M Alr Receiver W C O/C Note 34 m m Note 16 3-11 2R43-F0424 - 8 1 1/2" 30W A N-210M M Air Start C O/C Str M Yes Notes 5-7 Velve 16.24 2R43 F042C -- 8 1 1/2" S0W A N-210M M Air Stort C O/C etr M Yee ' Notes B-T Velve 16,M t 2R43 F0444 - 5 1 1/2" SOW A N-210M M Alr Start C O/C etr M Yes Notes A-7 vetve 16,M l 2R43 F044C - B 1 1/2" S0W A N-210M M Air Steet C O/C etr M Yes Wetes A-7 Velve 16,24 i 2R43 F0954 - C 3/4" CV A N-210M Air Reciever C C Note 25 m M Note 16 C-10 Intet CV 2R43 F095C -C 3/4" CV A N 21074 Air Reciever C C Note 25 M M Note 16 C-10 Intet CV l L l s l
O notch mueleer Plant thilt 2 157 Progree Pese No. 51 of at vetve Test TeMe 11 - twielen 0 Velve PSID/ Enercise Leakese ST Bemerke O CC Cet Deectlption A/P Coord Feetten p SP Freq Test Regd RR/CSJ/a0J -l 2T25 F906 2 A 1= Non EV P R-26057 Poselve Civ c C m Civ me M D-3 2T25-F995 2 A 1" Men EV P R-2605T Poselve CIV C C m Civ se m 0-3 i l l l i s N i. _..___z, _ . _ . , _ . . _m__.._-,,.. -, _ , , . , , , . _ . _ _ _ . - .. m .,, .,... , - , .
3 O Netch nueteer Plent tiritt 2 IST Progree Peso me. 52 of de Velve Test Tabte 11 - Revielen S Vetve P&lD/ Emerclee Leeksee ST Resorte i ! 19 CC Cet Deeeription A/P Coord Furetten WP SP Freq Test Reqd RR/CSJ/90J l 2T46-F001A 3 3 18" A0 SFV A N-26075 Filter Sed C 0 Str~ M Yes Note 16 j C-2 Intet frem Rm Sids ' t l 2146 F9018 3 3 18" A0 SFV A N-26078 Fitter Ded C 0 Str M Yes Note 16 s-2 Intet from Rx 1 l Bide 2746-F002A 3 3 18" A0 BFV A N-26078 3GTS Filter C 0 Otr M Yes Note 16 ; C-5 Outtet from as stds ( 2T46-F0025 3 8 18" A0 SFV A N-26078 SSTS Fitter C 0 Str NA Yes Note 16 s-5 Outlet from Rx stds 2746-F003A 3 -8 18" A0 SFV A N-26078 SGTS Ftte Bed C 0 Str NA Yes Note 16 C-2 Intet from RF 2T46 F0030 3 5 18" A0 SFV A N-26075 SETS Ftte Sed C 0 Str NA Yes Note 16 E-2 Intet from RF i b 1
t l o . o Netch Nueteer Plant Unit 2 Ist Program - Pese me. 53 of de' { Velve Test Table 11 - Revielen 0 l Volve P&lDI Esercise Leeksee - sf Resorts IS CC Cet Description A/P Coord Ftmetion WP SP Frog Test Regi M/CSJ/ROJ 2T48-F183 2 A 6" A0 BFV A N-26083 W & forue C C etr CIV Yes IIA D-10 Simply CIV 2744 F104 2 A 2* A0 RV A N-26083 W & Torue C C etr CIV Yes IIA t G-4 Outbrd CIV 2148-F113 2 A 2* A0 RV A N-26083 W Inerting C C etr CIV Yes HA G-9 Outbrd CIV 2748-F114 2 A 2* A0 RV A N-26083 W Inerting C C etr CIV Yes IIA N-9 Iribed CIV 2T48-F115 2 A 2* A0 RV A N-26083 m Inerting C C etr CIV Yes mA , G-10 Outbrd CIV 2T48-F116 2 A 2" A0 RV A N 26083 W Inertins C C etr CIV Yee mA N 10 Irdrd CIV 2744-F118A 2 A 1" A0 RV A N-26083 W Iteket, Irded C C etr CIV Yee un J-4 CIV 2T48-F1183 2 A la A0 RV A N-26083 Terue llakeip C C etr CIV Yes mA J-5 Ir6ed CIV s 2748-F209 2 A 4" A0 SV A N-26079 Irdioerd CIV C C etr CIV Yee un ; C-9 ! 2T48-F210 2 A 4" A0 GV A N-260F9 Outbeerd CIV C C etr CIV Yes NA C-9 2T48-F211 2 A 4" A0 GV A N-26079 Irdioerd CIV C C etr CIV Yes NA E-8 ' 2T48-F212 2 A 4" A0 GV A N-26079 Outboerd CIV -C C etr CIV Yee IIA G-8
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Ob . Estch Nucteer Plant Imit 2 IST Program Pese me. 54 of 60 Vetwe Test TsM e 11 - Newlefon 0 Velve P&ID/ Emercise Leekese ST Nemerke O CC Cet Description A/P Coord Function NP SP Freq Test Reqd- NN/CSJ/NOJ 2T48-F307 2 A 18" A0 SFV A N-26004 W Purge Intet C C Str CIV Yes ' R4 C-9 Ir6rd CIV - 2T48-F308 2 A 18" A0 SFV A N-26004 W Purge Intet C C etr CIV Yes NA C-10 Outbrd CIV 2T48-F309 2 A 18= A0 SFV A N-26004 Torus Purge C C etr CIV Yee NA ' E-10 Intet outbrd CIV 2T48-F310 2 A 20" A0 SFV A N-26004 Torus Purge voc C O/C etr CIV Yes NA F-10 trker CIV l 2T48-F311 2 A 20" A0 BFV A N-26004 Torus Purge Wee C O/C etr CIV Tee NA i F-9 Brker CIV 2T48-F318 2 A 18" A0 SFV A N-26084 Torus Purge C C etr CIV Yes NA G-4 Outlet Ir6rd CIV 2T48-F319 2 A 18" A0 SFV A N-26084 W Purge cuttet C C etr CIV Yes NA C-4 Iribrd CIV 2T48-F320 2 A 18* A0 BFV A M-26004 W Purge Outlet C C etr CIV Yes NA C-3 Outbrd CIV 2T48-F321 2 A 2* A0 GLV A N-26083 W Inertleis C C etr CIV Yes NA E-7 Outbrd CIV l 2T48-F322 2 A 28 A0 GLV A N-26083 W Inerting C C ' etr CIV Yes MA N-7 Ir6rd CIV 2748-F323A 2 C 18" A0 Test CV A N-26004 W to Torus Vs C O/C Str/NO NA NA Notes e-8 16,26,33 2T48-F3238 2 C 18" A0 Test CV A N-26004 W to Torus VB C O/C etr/NO NA NA Notes G-8 16,26,33
O
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Netch Nucteer Plant Unit 2 tsf Program Pese No. 55 of 60 Velve Test Tetde 11 - Revielen 8 Velve -_ PSID/ Enocclee Leekeen ST Resorte ID CC' Cet DeseriptIon A/P Coord Fametton MP $P Frog Test
. Req 6 RR/CSJ/30J 2148-F323C 2 C 10" A0 Test CV A N-26094 W to Torus vs C O/C Str/90 NA NA Notes -
C-8 16,26,33
'2T48-F323B 2 C. 18" A0 feet CV A N-26094 W to Torus VB C O/C etr/R0 NA NA Notes s-8 16,26,33 2T48-F323E 2 C 18" A0 Test CV A N-26004 W to Torus vt C O/C etr/R0 NA NA Notes E-8 16,26,33 2T48-F323F 2 C 18* A0 Test CV A N-26004 W to Torus VR C O/C etr/WO NA NA Notes e-8 16,26,33 2T48 F323e 2 C 18" A0 fat CV A N-26004 W to Torus VS C O/C etr/R0 NA NA Notes S-8 16,26,33 2T&O-F323N 2 C 18" A0 Test CV A N-26094 W to Torus VS C O/C Str/R0 NA NA Notes S-8 16,26,33 2T44-F323I 2 C 18" A0 Test CV A N-26004 W to Torus VB C O/C etr/R0 NA NA ~ Notes S-8 16,26,33 2T48-F323J 2 C 18" A0 Test CV A N-26094 W to Torus V5 C O/C etr/R0 NA NA Notes G-8 16,26,33 2148-F323K 2 C 18" A0 Test CV A N-26094 W to Torus VB C O/C Str/WO NA NA Notes -l, G-8 16,26,33 l
i l 2T48-F323L 2 C 18" A0 Test CV A N-26084 W to Torus VR C 1 O/C etr/R0 NA NA Notes 1 G8 16,26,33 i 2T48-F324 2 A 18" A0 BFV A N-26094 Torus Purge C C etr CIV Tee NA 0-10 Intet outbrd CIV 2T48-F325 2 A 2a A0 SLV A N-26083 Torus Inerting C C 1 etr CIV Tee NA S-8 Outbrd CIV I l
0 Retch Nucteer Plant Unit 2 IST Program 0
. Pepe me. 36 of de Vetve Test TsM e 11 - Revielen 0 votwe PRID/ Emercise- Leekage ST ~ Resorte D' CC Cet Description A/P Coord - Fisittlen NP SP Frog Test Reqd M/CSJ/NOJ 2T48 F3M 2 A 18" AS SFV A N-N004 Torus Purge C C etr CIV Yes M 8-3 Outtet Outtrd CIV 2T48-F32T 2 A 2* A0 KV A N-NOR3 Terus Inerting C C etr CIV - Yes M N-8 Irbrd CIV 2748 F3 NA 2 AC 20" A0 Test CV A N 26004 Rx Olds to S W C IVC Str/90 CIV M #etes 6-10 Chen Vs 26,33 IT48-F3205 2 AC 20" A0 feet CV A N-26004 Rx Btdp to S W C O/C Str/50 CIV E Wotes 8-10 theo VB 26,33 2T48 F332A 2 A to A0 RV A N-26004 Terus Purge C C Str CIV Yes M E-3 Outlet Outbrd CIV 2744-F332B 2 A 2* A0 RV A N-26094 Terus Purge C C Str CIV Yes M e-3 Outtet Outbrd CIV 2T44-F333A 2 A 2" AO KV A N-26094 Torus Purge C C Str CIV Yes M E-4 Outlet Irbrd CIV 2748-F333B 2 A 2" A0 RV A N-26094 Terus Purge C C etr CIV Yes M 8-4 Outlet Ir6td CIV 2140-F334A 2 A 2" A0 RV A N-26004 W Purge Outtet C C Str CIV Yes M s3 Outbrd CIV 2T44-F3348 2 A 2* A0 RV A N-26004 W Purge Outlet C C Str CIV Yes M C-3 Outbrd CIV 2748-F3354 2 A 2" A0 RV A N-26094 W Purge Outlet C C Str CIV- Yes 44 B-4 Ir6rd CIV
_. .. . . . - ._. . . . _ - . . ~ . - - - . . . . - . - . ._ . . . - . . . - . _ . _ . _ . . _ - . . , . . . . . - . . - . _ - - _ . Notch Nucteer Plant Urif t 2 IST Program Page No. 57 of 68 Velve Test Tetde 11 - Movielen 0 Velve P810/ Emercise Leeksee ST Nemorte O CC Cet Description A/P Coord Fametlen NP SP Freq Test Neqd NN/CSJ/M0J 2T48-F3358 2 A 2* A0 RV A M-26094 W Purge Outlet C C Otr CIV Yes NA ^ C-4 trdsrd CIV 6 2T48-F338 2 A 28 A0 RV A R-26004 Sypese-outbrd C C etr CIV Yee m N-2 CIV 2T48-F339 2 A 2* A0 RV A N-26094 Sypese-Irbrd C C Str Civ fee m N-3 CIV 2748-F340 2 A 2* A0 RV A N-26004 Sypees-cuttsr1f C C etr Civ Yee m D-2 CIV I 2748-F341 2 A 28 A0 RV A N-26004 Sypese-tr6rd C C Str C!V Yee m , E-4 CIV f' 2748-F342A 2 AP 1/2" SOV P N-26094 Terus to W W C C NA CIV No Note 27 N-8 Test CIV 2T48-F342B 2 AP 1/2" SOV P M-26084 Torus to W W C C NA CIV No Note 27 N-8 Test CIV 2T48-F342C 2 AP 1/2" SOV P M-26004 Torus to W W C C NA CIV Wo Note 27 M-8 Test CIV 2T48-F342D 2 AP 1/2" SOV P M-26084 Torus to W W C C m CIV to Note 27 N-8 Test CIV 2T48-F342E 2 AP 1/2" 30V P N-26004 Torus to W 48 C C M4 CIV Wo Note 27 R-8 Test CIV [ i. 2T48-F342F 2 AP 1/2" SOV P M-26084 Torus to W W C C NA "!/ No Note 27 N-8 Test CIV b 2748-F342G 2 AP 1/2" SUV P N-26004 Torus to N W C C MA CIV No Note 27 [ M-8 Test CIV i l
. . . . ~ . - .- - - - - - - - - - - - - - -
I Netch Nuclear Pteret Urtit 2 IST Progree 'Pese No. 58 of de - l
- Vetve Test Tatde 11 - Revielen 0
}
- Velve PSID/ Enercise La"h"9s ST Reenrks 19 CC Cet Description A/P 'toord Factlen WP SP Freq Test Reqd NN/CSJ/NOJ.
l '2T48-F342R 2 AP 1/2" Ser P N-26004 Torus to N VR C C M CIV No Note 27 N-8 Test CIV - 2T48-F342I 2 AP 1/2" ser P N-26004 Torus to W VS C C M CIV No Note 2T N-8 Test CIV 2T48-F342J 2 AP 1/2" SOV P N-26004 Torus to W VB C C NA 'CIV No Note 27 . N-8 feet CIV 2T48-F342K 2 AP 1/2" Set P N-26004 Terus to W VS C C M CIV No Note 27 N-8 Test CIV 2748-F342L 2 AP 1/2" SOF P N-26004 Torus to N V5 C C M CIV No Note 27 N-8 Test CIV 2748-F361A 2 A 1" A0 EV A N-26094 Torue unter 0 0/C Str CIV Yes NR G-9 Levet CIV 2T48-F3618 2 A 1" A0 KV A N-26004 Torus Unter 0 0/C Str CIV Tee M4 s-5 Levet CIV 2T48-F362A 2 3 1" A0 EV A N-26004 Terue Unter 0 0/C etr NA- Yes Note 4 N-9 Levet too
' 2T48-F3623 2 R 1" A0 RV A N-26004 forus Water 0 0/C etr NA Tee Note 4 N-5 Levet too 2748-F3634 2 A 1" A0 EV A N-26004 Prese 0 O/C etr CIV Tes NA l E-8 Transmitter CIV !
2748-F3635 2 A 1" A0 RV A N-26004 Prese 0 0/C etr CIV Yes NA D-6 Trenamitter CIV 2T48-F3644 2 A 1" A0 RV A N-26004 Prose i 0 0/C Str CIV Yes' NA i G-5 Transmitter Ctv 4
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.T Netch Nucteer Plant imit 2 IST Program Pese no. 59 of 40 Velve Test Telde 11 - Revielen 0 Vetwe PGID/ Esercise Leekage ST Romerke
.O CC Cet Deecription A/P Coord Feetten NP SP Frog Test Reqd ER/C5J/ROJ 2T48-F3648 2 A 1" A0 SLV A N-26086 Prese O O/C Str CIV Yes NA t-8 Tronomitter CIV A
4 h _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ --.4 _ _ _ -,-. _ _ . __e, . - -- , . . - -- . - - , - - - - -- - . _ . - _ m ,_ _ . - _ - -
_ _- _m m - .._.m _- . _ , . - -_ . _ ~ ~ - - . . . _ . - . - - . _ . . _ _ , . _ _ . . _ _ ..._ __ _. . _ . . _ . _ . n di Netch Nucteer Plant Ittit 2 IST Progree Page No.'68 of 68 Velve Test febte 11 - Revisten 0 I vetve PSID/ Emercise Leekage ST tesorte le CC Cet Description A/P- Coord Fametten MP SP Frog Test Rogd RR/tSJ/poJ. , 2749-F001A 2 3 4" NO SV A N-26d68 Nydrogen Reces C O/C etr M Yes Note 16 C-3 W shutoff 2749-F0015 2 3 4" ND SV A N-26068 Nydrogen Reces C O/C M ' Str Yes Note 16 C-3 W shutoff i i 2T49-F002A 2 A 4" NO SV A N-26068 Nydrepen Recom C O/C 9tr Civ Yes M. C-4 W CIV 2T49-F002B 2 A 4" NO SV A N-26068 Nydrogen Reces C O/C Str CIV Yes M C-4 W Civ
. 2749-F004A 2 A 4" NO SV A N-26068 Nydrogen Recom C l O/C etr - CIV Yes M ,
F-5 See & Water Civ 2749-F0048 2 A 4" ND SV A N-26068 Nydrogen Reces C O/C CIV Str Yes M 't F-5 Gee & Water Civ 2747-F005A 2 3 4" NO SW A N-26068 See & Water C O/C etr M Yes . Note 16 F4 Return i 2T49 F0058 2 3 4" NO SV A N-26068 See & Water C O/C Str NA fee Note 16 F-4 Return 2749-F006A 2 B 3/4" NO OLV , A N-26068 Water Feed from C O/C Str M Yes M i N-5 RNR 2749-F006s 2 e 3/4" ND GLV A N-26068 Water Feed from C O/C Str M Yes M N-5 RM 2T49-Fs09A 2 C 1" RV A N-26068 Relief / Cont C O/C Note 5 M M Note 4 F-4 Bndr Vetve 2749-F0093 2 C 1" RV A N-26068 Rollef/ Cont Note 5 M C O/C M Note 4' F-4 OndF Vetve i
12.0 VALVE RELIEF REQUEST LOG l Relief Reauest Status
- RR-V-1 Submitted for NRC approval
. RR-V-2 Submitted for NRC approval RR-V-3 Submitted for NRC approval
- RR-V-4 Submitted for NRC approval i RR-V-5 Submitted for NRC approval
- RR-V-6 Submitted for NRC approval RR-V-7 Submitted for NRC approval j RR-V-8 Submitted for NRC approval l
- RR-V-9 Submitted for NRC approval '
j RR-V-10 Submitted for NRC approval 1 l. j 4 i i i i'O j ; l i i i e i i I 12-1 Rev. O
RELIEF REQUEST -j
-RR-V-1 SYSTEM: NA
(} VALVE (S):~IB21-F016 IE41-F002 IE51-F007 , 2821-F016 2E41-F002 2E51-F007 CATEGORY: A CLASS: l and 2 FUNCTION: NA TEST REQUIREMENT: ISTC 4.3.2 requires that containment isolation valves be tested for leakage in accordance with 10 CFR 50, Appendix J. 10 CFR 50, Appendix J requires valves to be tested in the same direction as'when the valve is performing 'its safety- ; related containment isolation function. BASIS FOR RELIEF: The correct test direction is to pressurize from the inboard side of the valve; however, the piping on the inboard side ; connects directly to the reactor vessel and cannot be pressurized for testing. , ALTERNATE TESTING: These containment isolation valves will be leak rate tested l in the reverse direction as addressed in the Edwin I. Hatch, 10 CFR 50, Appendix J containment leak rate test program for Type C leakage tests. Additionally, these valves are tested O- in the correct direction during the performance of each 10 L CFR 50, Appendix J, Type A integrated leakrate test. L i i r 12-2' Rev. 0
t RELIEF REQUEST j RR-V-2 4 1 SYSTEM: Mainsteam 1821 and 2821 i
, VALVES: 1821-F022A,B,C,D and IB21-F028A,B,C.D ; 2B21-F022A,B,C,0 and 2B21-F028A,B,C,D i
CATEGORY: A CLASS: 1 i FUNCTION: Main Steam Isolation Valves (MSIVs) 4 ) TEST REQUIREMENT: Relief is requested from applying the requirements of ISTC 4.2.8(d) and ISTC 4.2.9(b) to the main steam isolation l valves. BASIS FOR RELIEF: ISTC 4.2.4(a) requires that the Owner specify the limiting i value of full-stroke time for each power operated valve. For
- all valves which require stroke timing, except the MSIVs, 1 this limiting value' is a maximum allowable stroke time.
However, the design basis for the MSIVs imposes a minimum and a maximum allowable stroke time of 3 to 5 seconds 3 respectively. Therefore the MSIVs have a 2 second window of l 1 acceptable operating time. Applying a 50% increase limit per . ITSC 4.2.8(d) from the reference value to a valve which must i ! stroke in a 2 second window is impractical. When the I iV f) criteria of ISTC 4.2.4(b) are also applied, the stroke time of all power operated valves shall be measured to the nearest second, then the requirements of ISTC 4.2.8(d) become even
- j more impractical. ,
ALTERNATE TESTING: The MSIVs will be stroke timed during cold shutdown per Cold ' Shutdown Justification CSJ-V-1 and their closing time will i be confirmed to be between 3 and 5 seconds. As soon as it , is recognized that an MSIV does not meet this criteria, it will be declared inoperable and the applicable Technical ] Specification Action Statement entered. 1 , i i i !O I l 12-3 Rev. O
RELIEF REQUEST : i RR-V-3 i
' SYSTEM: CRD VALVE (S): ICll-F010A&B, ICll-F0ll, IC11-F035A&B, ICll-F037 '
.2C11-F010A&B, 2Cll-F011, 2Cll-F035A&B, 2Cll-F037 CATEGORY: B \
CLASS: 2 FUNCTION: Scram discharge volume vent and drain valves ' TEST REQUIREMENT: Establish limiting values of valve stroke time and measure ' individual valve stroke time per ISTC 4.2.4(a). BASIS FOR RELIEF: A limiting value of stroke time cannot be specified for the scram discharge volume vent and drain valves and they cannot be individually stroked and timed. In order to prevent water hammer induced damage to the system during a full CRD scram, plant Technical Specifications require that system valve ! operation is adjusted so that the outboard vent and drain I valves (F035A&B, F037) fully close at least five seconds after each respective inboard vent and drain valve (F010A&B, F011). All valves must be fully closed in less than forty-five (45) seconds for Unit I and sixty (60) seconds for A Unit 2. Additionally, the system is adjusted so that the inboard vent and drain valves (F010A&B, F011) start to open ; at least five seconds after each respective outboard vent and ; drain valve (F035A&B, F037) upon reset of a full core scram. l The valves are not equipped with individual valve control l switches and cannot be individually stroke timed. Because of the adjustable nature of the valve control system, individual valve stroke timing would not provide any meaningful information for monitoring valve degradation. System design prevents stroke timing these valves during normal operation without disabling the Reactor Protection System Scram Signal to the valves. Disabling this signal requires the installation of electrical jumpers and the opening of links in energized control circuits which increase the potential for a Reactor Scram. ALTERNATE TESTING: The valves will be exercised quarterly but not timed. Additionally, the total valve sequence response time will be verified to be less than Technical Specifications requirements during each refueling outage when a complete stroke time test is performed. ~ l 0 v l 12-4 Rev. 0 l
_ . _ - _ _ _ . - _ . . . ___ . . _ . _ . _ _ _ . . ~ _ _ _ . __ __ L, -
?
p RELIEF REQUEST. ! [
, RR-V-4 !
4
' Traversing Incore Probe (TIP).
. SYSTEM:
L 'VALVEi IC51-F3012 f
-CATEGORY: A' ,
h l CLASS: 2 s FUNCTION: Containment Isolation
~
iTEST REQUIREMENT: ISTC 4.2.1 and ISTC 4.2.4(a) require-power operated valves [ g to be stroke timed. quarterly and ISTC 4.2.8; requires comparison: testing to the reference stroke time value. , l BASIS FOR RELIEF: The safety position of this valve is . CLOSED 'to provide ! ! containment isolation which is initiated by a LOCA signal and results in isolation -of TIP purge and the TIP probes.- The' ' Technical Specifications nor the FSAR have _ any specific . l requirements for isolation stroke time for this valve.. - 4
- - This is a normally open .normally energized solenoid operated valve which strokes in milliseconds. The valve was not L provided with remote indicating lights and its design does
!. not provide for observation of actual stem movement. $[ A simple check valve is located upstream of this solenoid valve which provides outboard containment isolation of the i n penetration. Nitrogen purge is at a steady flow and pressure l p which does not impose any harsh operating conditions on this j check valve. Therefore, additional assurance is provided for i p isolation of the associated penetration. 1 c The purge line is small (3/8") and the FSAR evaluation : 1 indicates that even in the event of a TIP dry tube failure
- l and non-isolation of the purge line, the radioactive release
- would remain within the allowable limits. '
- Since this valve strokes in milliseconds, it is classified {
j as a rapid acting valve per GL 89-04, Position 6. Therefore, l t if indicating lights or valve stem movement were observable,
- comparison time testing of valves with stroke times of less
- than or equal to 2 seconds is not required per ISTC 4.2.8(e). ;
Industry history indicates that solenoid valves either operate properly or not at all. It has not been established that stroke time testing of solenoid valves provides data applicable for evaluation of degradation. The application of some type of electronic monitoring would be on a trial and ' error basis' since no such equipment has been proven to l provide useful test data to date. Considering the safety 4- function of the valve (containment isolation) and the M- redundancy of this function provided by a simple check valve, stroke time testing to monitor degradation will not provide i i 12-5a Rev. 0 :
- . -- _ = . . . --
RR-V-4 (ctnt.) a significant increase in assurance that the valve is capable of performing its intended function. ALTERNATE TESTING: The valve will be exercised closed quarterly, and observation of a decrease in nitrogen pressure in the associated tubing will be utilized as confirmation that the valve is in the safety related closed position. This valve is exercised closed and local leak rate tested (LLRT) at each refueling outage in accordance with 10 CFR 50, Appendix J. LLRT provides assurance that the valve is in the closed position and thus is capable of providing its safety function of containment isolation. l O l i 4 4 d O , 12-5b Rev. 0 l l
RELIEF REQUEST i RR-V-5
-U(9 SYSTEM: IC51, 2C51-VALVES: -1C51-Shear.A,B,C,0
' 2C51-Shear A,B,C,D CATEGORY:.AD CLASS: . 2
-{
1 FUNCTION: TIP System Outboard CIV TEST REQUIREMENT: ISTC 4.3.2 requires Category A, which are containment l isolation valves, to be leak tested at a frequency of at ; least every 2 years. . 7 BASIS'FOR RELIEF: These valves are explosive actuated shear valves. The shear ; valve isolates the TIP tubing by shearing the tube and TIP l drive' cable, and by jamming the sheared ends of the tubing into a teflon coating on the shear valve disc.- Thus the shear valves cannot be local leak rate tested without destroying the drive. tube. ALTERNATE TESTING: Each lot of shear valves is sample leakage tested by the manufacturer prior to delivery. This sample leakrate testing satisfies the requirements of the Plant Hatch 10 CFR 50, O d Appendix J Leakrate Program. , 4 These valves are also tested in accordance with ISTC 4.6 as t . explosive actuated valves. i. 5
- A
- , 12-6L P.ev. 0 l
,e - < - , - - .
RELIEF REQUEST RR-V-6 SYSTEM: .RHR VALVE (S): IEll-F050A,B l
' CATEGORY: AC :
CLASS: 1 FUNCTION: LPCI and Pressure Isolation TEST REQUIREMENT: Verify forward flow operability quarterly or at cold shutdown-per ISTC 4.5.1 and 4.5.2. , BASIS FOR RELIEF: The plant and system configuration does not provide for full-or partial flow exercising during normal . operation. LPCI injection ' during normal operation is impossible because. ! reactor pressure is significantly greater than LPCI injection , pressure. Therefore full or partial exercising with flow is impossible quarterly. t During operation in the cold shutdown mode, it has been
. determined that the subject valve for the loop in operation 4.
is only partially stroked to the open position. To fully
- open the valve in this mode would require the use of two RHR !
pumps in combination; however, net positive suction head , j requirements would not be met in this alignment. , l The only way to full flow exercise.these valves would be to
- align the RHR pump suction to the suppression pool and inject ,
- . to the RPV at cold shutdown or refueling outage. This would '
L result in a significant degradation of reactor coolant quality which would require an extensive amount of time to , i restore the Technical Specification required coolant quality. Therefore full flow exercising at cold shutdown or refueling l 1s-impractical. It is normal plant practice to utilize only one loop of.RHR in shutdown cooling for any unscheduled shutdown due to the l efforts. involved in system alignment, flushing, pipe warm-up
- . and swapping of loops. Requiring both loops of RHR shutdown i
cooling to be placed in operation during an unplanned : !. shutdown for the sole purpose of exercising each check valve - places undue hardship on operation's personnel involved with ! other shutdown activities and could extend shutdown duration. j' Therefore partial exercising each valve with RHR shutdown cooling flow during each cold shutdown is impractical. - l These valves are located inside the primary containment and l are therefore inaccessible during normal operation or at cold i shutdown unless the containment is de-inerted. The L
) containment is never de-inerted during an unplanned shutdown l
- unless containment entry is absolutely necessary. Therefore mechanical exercising quarterly or at cold shutdown is impractical.
12-7a Rev. 0
. i
l RR-V-6 (cont.) ALTERNATE TESTING: The loop of RHR utilized for shutdown cooling will be O alternated each shutdown. Therefore one of these valves will be partial exercised each cold shutdown and valves will be O alternated for each shutdown. During each refueling outage, both loops of RHR shutdown cooling are utilized in support of nortaal shutdown and fuel handling activities. Therefore each check valve will be partially exercised at each refueling outage. Additionally, each valve will be mechanically exercised in accordance with ISTC 4.5.4(b) at each refueling outage. Partial exercising with flow at the described frequency along with mechanical exercising and leak rate testing during each refueling outage provides sufficient confirmation of valve operability. O o V 12-7b Rev. O
RELIEF REQUEST.- RR-V-7 *
' SYSTEM: HPCI. '
VALVE: 1E41-F045 ' 2E41-F045 - C'ATEGORY: 'C i CLASS: 2- ' FUNCTION: HPCI Pump Suction (Alternate source from suppression pool). ! TEST REQUIREMENT: Verify forward flow operability quarterly per ISTC 4.5.1 and ISTC 4.5.2.
' BASIS FOR RELIEF: This normally closed check valve is located on the HPCI pump.
suction.line from.the suppression pool. The valve does not - experience. flow during any normal mode of reactor operation :' or shutdown conditions or during . HPCI pump surveillance testing. The normal suction source for the HPCI pump is the condensate storage tank (CST) for periodic surveillance .
. testing and ECCS injection. The pump. suction transfers to the suppression pool upon indication of a low water level in the CST which would only occur during an extended HPCI injection because 100,000 gallons of water are always maintained in the CST for ECCS usage.
Forward flow exercising this valve would require aligning the . HPCI pump suction to the suppression pool and discharging to l the CST. This flow path would significantly degrade the j water quality in the CST. t L ALTERNATE TESTING: Every second refueling outage the valve will be disassembled, l manually exercised and visually inspected to confirm that the valve is capable of full stroking and that its internals are structurally sound (no loose or excessively corroded parts). 4 This frequency is considered adequate to detect degradation i which would prevent the valve from meeting its safety function. The valve remains in the closed position in a torus water environment and does not experience flow which L ' could cause wear. Additionally, past inspections have shown little, if any, degradation other than the expected minor corrosion. Generic Letter 89-04 requires that a partial- flow test be i .. performed on check valves that are disassembled prior to their return to service. There is no possible flow path l available for ' partial flow testing this check valve that L would not introduce suppression pool water into the HPCI L system piping or back to the CST. This is a simple swing s, check valve (Powell Fiq.1561-WE) which does not require removal of the valve internals to perform a manual stroke
\
test or visual inspection. Even if exercising / inspection ; resulted in valve repairs, the valve could still be manually ! stroked after.the internals were reinstalled'in the valve. 12-8a Rev. O i
i RR-V-7 (cont) Therefore, full stroke capability of the valve is ensured prior to installation of the bonnet cover. This relief request is required because all of the requirements (partial exercise after reassembly and frequency of disassembly) of GL 89-04, Position 2, are not practicable. O i ll l i i I l l I' 12-8b Rev 0 l_ - . _ _
i RELIEF REQUEST RR-V-8 , SYSTEM: Plant Service Water VALVE (S): IP41-F035A&B, IP41-F036A&B, IP41-F037A-D, IP41-F039A&B, 2P41-F035A&B 2P41-F036A&B, 2P41-F037A-D, 2P41-F039A&B, 2P41-F339A&B, 2P41-F340 CATEGORY: B CLASS: 3 FUNCTION: Equipment Cooling Water Supply Valves TEST REQUIREMENT: ISTC 4.2.3 requires verification of valve obturator movement by observing an appropriate indicator, such as indicator lights, or by observing other evidence, such as changes in system pressure, flow rate, level , or temperature, that reflects changes in obturator movement. BASIS FOR RELIEF: These valves are normally closed, fail open air operated valves which have a safety function to open and provide cooling water flow to the associated safety related equipment. System design did not provide indicating lights, instrumentation or direct valve control switches. The valves receive an open signal upon initiation of the associated equipment and a close signal upon termination of operation of. the associated equipment. Therefore, O- verification of obturator movement and measurement of valve stroke time and can only be performed by observation of the actual valve stem movement when the associated equipment is placed into service. 4 ALTERNATE TESTING: Verification of obturator movement and measurement of valve stroke time will be performed by observing actual valve stem movement. Stroke time will be considered to be the time from 4 i start to stop of valve stem movement. The requirements of i ISTC 4.2.8 will be applied to monitor valve degradation. j l
- O 4
Rev. 0
RELIEF. REQUEST [ RR-V-9 ,
- D( ) ' SYSTEM
- Traversing Incore Probe (TIP) i VALVE: 2C51-F3012 l
l CATEGORY: A 1 : J CLASS: 2 - ! i j FUNCTION: Containment Isolation *
- TEST REQUIREMENT
- ISTC 4.2.1 and ISTC 4.2.4(a) require power operated valves L to be stroke timed quarterly and ISTC 4.2.8 requires '
i comparison testing to the reference stroke time value. l' BASIS FOR RELIEF: The safety position of this valve is CLOSED to . provide containment isolation which is initiated by a LOCA signal and results in isolation . of TIP purge and the TIP probes. 4 Neither the Technical Specifications or the FSAR have any '
! specific requirements for isolation stroke time for this valve.
j t i This is a normally open, normally energized solenoid operated valve which - strokes in milliseconds. The valve was not i provided with remote indicating lights and its design does ! not provide for observation of actual stem movement (stem is fully enclosed).
- A simple check valve is located upstream of this solenoid valve which provides outboard containment isolation of the penetration. Nitrogen pcrge is at a steady flow and pressure which does not impose any harsh operating conditions on this
'- check valve. Therefore, this upstream check valve provides additional assurance for isolation of the associated p penetration. i The purge line is small (3/8") and the FSAR evaluation '
- indicates that even in the event of a TIP dry tube failure and non-isolation of the purge line, the radioactive release
! would remain within the allowable limits. ' i i :, i Since this valve strokes in milliseconds, it is classified as a rapid acting valve per GL 89-04, Position 6. Therefore, t if indicating lights or valve stem movement were observable, !
, comparison time testing of valves with stroke times of less !
j than or equal to 2 seconds is not required. . 1- ] Industry history indicates that solenoid . valves either [ operate properly or not at all. It has not been established ; 4 that stroke time testing of solenoid valves provides data ; applicable for evaluation of degradation. The application of some type of electronic monitoring would be on a trial and 4 error basis since no such equipment has been proven to provide useful test data to date.- Considering the safety 12-10a .Rev. O ! 4
.1._____________n_______________________..__. ,-.m. -- --
RR-V-9 (cent.) function of. the valve (containment isolation only) and the redundancy of this function provided by a simple check valve, testing to monitor degradation will not provide a significant
\- increase in assurance that the valve is capable of performing its intended function.
ALTERNATE TESTING: This valve will be exercised closed quarterly, and observation that nitrogen flow in the asseciated tubing has stopped will be utilized as confirmation that the valve is in the safety related closed position. This valve is local leak rate tested (LLRT) at each refueling outage in accordance with 10 CFR 50, Appendix J. LLRT provides assurance that the valve is in the closed position and thus is capable of providing its safety function of containment isolation. i 1 f--]s
\~-
12-10b Rev. O
l RELIEF REQUEST RR-V-10 (l V SYSTEM: RHR ' VALVE (S): . 2E11-f050A,B
. CATEGORY: AC CLASS: 1
- FUNCTION: LPCI and Pressure Isolation i TEST REQUIREMENT: Verify forward flow operability quarterly or at cold shutdown
) per ISTC 4.5.1 and 4.5.2. '
BASIS FOR RELIEF: The plant and RHR system configuration does not provide for full or partial flow exercising during normal operation. LPCI injection during normal operation is impossible because reactor pressure is significantly greater than LPCI injection
- pressure. Therefore, full or partial exercising with flow j
quarterly is impossible. i During the shutdown cooling mode of RHR operation, the normal
- flow rate is between 7700 and 8200 gpm. At 7700 gpm the flow velocity is approximately 14 fps. Valve vendor information indicates that a flow velocity of a
- 10 fps is sufficient to fully open the valve disk if the valve is in good operating condition. Therefore, normal shutdown cooling flow rates are sufficient to fully open the disk of a valve in good operating condition.
Valve design incorporates a two piece (outside hollow 4
. cylinder and inside solid cylinder) hinge pin because the valve was initially provided with an operator which was used to minimally exercise the valve disk. The operator is no longer utilized for disk exercising, but the two piece hinge pin allows for external visual determination of the disk position by observing the inside hinge pin position.
It is normal plant practice to utilize only one loop of RHR
- in shutdown cooling for any unscheduled shutdown due to the extra efforts involved in system alignment, flushing, pipe warm-up and swapping of loops. To require both loops of RHR shutdown cooling to be placed in operation during an unplanned shutdown for the sole purpose of exercising each check valve seems unwarranted. Therefore, exercising both valves at each shutdown is impractical.
ALTERNATE TESTING: At least one of these check valves receives shutdown cooling flow (7700. - 8200 gpm), therefore is at least partially exercised, each cold shutdown. The loop of RHR shutdown
/'~ cooling placed into service will be alternated for each unplanned shutdown. Therefore, a different valve will be at L least partially exercised each time shutdown cooling is l
utilized. 12-Ila Rev. 0
.-_ _~ - . . . - . - - . - -._- . -. . . - _ - .
l RR-V-10 (cent.) l During each refueling outage, both loops of RHR shutdown
- cooling are utilized in support of normal shutdown and fuel l T handling activities. Therefore both valves are exercised j during each refueling outage.
i ) In conjunction with RHR -shutdown cooling operation each ! refueling outage, external visual observation of rotation of 7 the inside hinge pin will be utilized to confirm that the ' valve disk is fully open. Scribe marks, angular measurements ' or some other positive means will be used to ensure that the
- flow actually moves the valve disk to the full open position.
' If visual observation does not confirm that the flow has fully exercised the valve disk, then appropriate additional ; actions will be taken (e.g. mechanically exercising the valve i per ISTC-4.5.4(b), disassemble, exercise and visually f inspect,etc.). 1 , t i l i e i i 4 4
- O 1
1 4 12-Ilb Rev. O
13.0 COLD SHUTDOWN JUSTIFICATION (CSJ) LOG l ! .GLI Status CSJ-V-1 Submitted for NRC Concurrence CSJ-V 2 Submitted for NRC Concurrence CSJ-V-3 Submitted for NRC Concurrence r CSJ-V-4 . Submitted for NRC Concurrence CSJ-V-5 Submitted for NRC Concurrence CSJ-V-6 Submitted for NRC Concurrence CSJ-V-7 Submitted for NRC Concurrence CSJ-V-8 Submitted for NRC Concurrence i CSJ-V-9 Submitted for NRC Concurrence l CSJ-V-10 Submitted for NRC Concurrence l CSJ-V-Il Submitted for NRC Concurrence CSJ-V-12 Submitted for NRC Concurrence O O 13-1 Rev. O
COLD SHUTDOWN JUSTIFICATION , CSJ-V-1 O SYSTEN:^ Main Steam j VALVE (S): IB21-F022A-D,;IB21-F028A-D l 4 2B21-F022A-D, 2821-F028A-D CATEGORY:'A l' CLASS: 1-4 FUNCTION:. Main Steam Isolation Valves-QUARTERLY TEST REQUIREMENT: Exercise and Stroke Time per ISTC 4.2.1
- COLD SHUTDOWN . . .
l TEST JUSTIFICATION: Full stroke testing these valves during normal reactor
- operation requires isolating one of the four main steam
- lines. Isolation of these lines results. in primary system !
! pressure spikes, reactor power fluctuations, and increased
- flow in the unisolated steam lines. This unstable !
t
- operation can lead to a reactor scram, and as discussed in
- NUREG-0626. Pressure transients resulting from full stroke i l- testing NSIVs increase the chances of actuating primary .
. system safety / relief valves. Also, stroking these valves L
- during power operation requires decreasing the unit to 75%
power, therefore, resulting in a substantial capacity , factor loss prior to, during, and after the test. *
- j PARTIAL QUARTERLY r STROKE TESTING
- Yes
- l. 1
! COLD SHUTDOWN !. TESTING: Exercise and stroke time each cold shutdown, with the test ; i frequency not to exceed testing once every quarter. l ! l t !? ; i + f O ; 13-2 Rev. 0 1
- , _ ~ . -
_ .._ _ ._. . _ _ _ _ _ __ _ _ . _ . _ . . _ . _ . . _ . ~ . . . . . _ _ _ _ . _ - . .
-_ l
[ COLD SHUTDOWN JUSTIFICATION CSJ-V-2 SYSTEM:. . Reactor Recirculation System VALVE (S): IB31-F031A,B 2831-F031A,B l CATEGORY: B. ! i [ CLASS:- 1
- FUNCTION: . Valves close to provide loop isolation .
QUARTERLY TEST
- REQUIREMENT
- Exercise and Stroke Time )
l COLD SHUTDOWN TEST JUSTIFICATION: Closure during normal operation requires a reduction in power to trip.the associated recirculation pump. .If.the associated pump is tripped, it also creates a potential for j exceeding the permissible temperature differential between , j the recirculation loops for. pump re-start. In addition, i the valves are located inside the primary containment and
- are inaccessible during normal operation, which precludes an operator from. manually re-opening the valve.in case of
+
[ ' actuator failure. I ! r" ' QUARTERLY PARTIAL _ l 2 STROKE TESTING: None. The valve operating circuitry does not allow for l l~ partial closure of the valve. j
- COLD SHUTDOWN TESTING
- Exercise and stroke time each cold shutdown, with the test !
frequency not to exceed testing once every quarter. ' ! l I 4 4 1 i 1 4 4 4 4 13-3 Rev. O _ . . -, _ . _ - + . ,
COLD SHUTDOWN JUSTIFICATION CSJ-V-3 SYSTEM: ' Residual Heat Removal VALVE (S): IEll-F008,-lEll-F009 ' 2 Ell-F008, 2 Ell-F009 CATEGORY:' A i CLASS: 1 l FUNCTION: RHR Shutdown Cooling Pressure Isolation
-QUARTERLY TEST l REQUIREMENT: Exercise and Stroke Time .
COLD SHUTDOWN TEST JUSTIFICATION: These pressure isolation valves are interlocked to prevent , valve opening during power operation or when reactor t pressure is > 145 psig. Defeating the interlock and ' opening one of the in-line valves during normal operation could result in the over-pressurization of the low pressure : design RHR pump suction piping.. QUARTERLY PARTIAL ! STROKE TESTING: None COLD SHUTDOWN . Exercise and stroke time each cold shutdown, with the test O" TESTING: frequency not to exceed testing once every quarter. , i l ( O 7 13-4 Rev. 0 i
2 COLD' SHUTDOWN JUSTIFICATION.
- j. CSJ-V-4 j
0 svstca: aaa
-VALVE (S): . IE11-F015A & B CATEGORYi A r .
l l- CLASS:' 1- ;
- i FUNCTION: LPCI Outboard _CIV/PIV l
. QUARTERLY TEST. .. .
Exercise and stroke time per ISTC 4.2.1 REQUIRENENT:-- 4' COLD SHUTDOWN . cTEST-JUSTIFICATION: These are normally closed valves which must open to permit LPCI and must close to provide containment isolation and . pressure isolation. The valves are interlocked to prevent - opening unless the', corresponding' downstream 1E11-F017A(B) valve- is. closed or reactor. pressure is. below a predetermined design value. The' NRC GL 89-10 evaluation a for;these valves indicates that the valve motor operators l I were not required to be designed to. ensure valve opening against the.possible differential pressure that might be ! -encountered if exercising during normal operation. ; i . 5 e- QUARTERLY, PARTIAL STROKE TESTING: None l COLD SHUTDOWN .
- . TESTING
- These normally closed motor operated valves will be full i stroke exercised and stroke timed each cold shutdown, with
. the test frequency not to exceed testing once every , quarter. 1
- I
,L l L l i l l. 4 O ' 1 13-5 Rev. O I
4 COLD SHUTDOWN JUSTIFICATION CSJ-V ' SYSTEM:' Core Spray-
~
3 VALVE (S): .1E21-F005A E B CATEGORY: -A' 1 CLASS: 1 i FUNCTION: Core Spray Injection Outboard CIV/PIV l 1 -l i QUARTERLY TEST . . Exercise and stroke time per ISTC 4.2.1- [ REQUIRENENT:- COLD SHUTDOWN { TEST JUSTIFICATIONi These are normally closed valves which must open to permit i- core spray injection and must close.to provide containment - isolation and pressure. isolation. The valves are
- .
- interlocked to prevent opening unless the corresponding downstream 1E21-F004A(B) valve is closed or reactor i
pressure is below a predetermined design value. The NRC GL l- 89-10 evaluation for these valves indicates that the valve 1 l motor operators were not required to be designed to ensure valve opening against the possible differential pressure . that might be'. encountered -if - exercising . during normal
- operation. The GL 89-10 evaluation also. indicated that
!. Y leakage past the corresponding downstream lE21-F004A(B) E .. valve with the IE21-F005A(B) valve open could result in ! over-pressurization of the core spray pump discharge piping and a LOCA outside of containment. [ l- QUARTERLY PARTIAL STROKE TESTING: None COLD SHUTDOWN i- TESTING: These normally closed motor operated valves will be full l- stroke exercised and stroke timed each cold shutdown, with -
- the test frequency not to exceed testing once every quarter.
l t ? l .. p l i. l I 13-6 Rev. 0
>,~I- L-
COLD SHlHDOWN JUSTIFICATION'
'CSJ-V-6 SYSTEM: 'HPCI, RCIC-VALVE (S): 1E41-F002, 2E41-F002 1 1E51-F007, 2E51-F007 CATEGORY: A CLASS:- 1 FUNCTION: HPCI/RCIC Steam Supply _CIV QUARTERLY TEST _ _
REQUIREMENT: Exercise and Stroke Time per ISTC 4.2.1 COLD SHUTDOWN TEST JUSTIFICATION: These are normally open, motor. operated valves located inside the primary containment. If the valve is exercised closed during normal operation and fails to re-open, the entire system safety function would be rendered inoperable. The primary containment is inerted during normal operation and a plant shutdown would be required to repair the valve and restore the system safety function. QUARTERLY PARTIAL' STROKE TESTING: None LO l' COLO SNUTOOwN TESTING: Exercise and stroke time each cold shutdown, with the test l frequency not to exceed testing once per quarter. l a O 13-7 Rev. 0
--_-_1_-___
COLD SHUTDOWN JUSTIFICATION. CSJ-V-7 SYSTEM: Reactor Water Cleanup System (RWCU) VALVE (S): IG31-F001, IG31-F004-2G31-F001,'2G31-F004 CATEGORY: A CLASS: 1 FUNCTION: RWCU Pump Suction CIV QUARTERLY TEST
' REQUIREMENT: Exercise and stroke time per ISTC 4.2.1 COLD SHUTDOWN TEST JUSTIFICATION: The RUCU System is in operation during normal plant operation in order to maintain reactor coolant chemistry within Technical Specifications limits. _ The isolation valve:; are open teenever RWCU System is in operation supplying reactor coolant as pump suction source for processing and eventual return to the reactor coolant inventory. Exercising ~ and stroke timing these valves closed quarterly requires the entire RWCU System to be taken out of service which could result in the degraded chemical makeup of reactor coolant and subjects the entire O RWCU System to unnecessary transients.
transients could letd to degradation and failure of other related system components These unnecessary (e.g., pumps, valves, l_ domineralizers) and the potential loss of the system availability which could cause required shutdown. , Exercising and stroke timing these valves also results in undue hardships and exposure limits to personnel involved in the actual surveillance activity. The steps necessary to exercise and stroke time these valves are briefly l described below.
- 1. Take RWCU Domineralizers out of service.
- 2. Trip operating RWCU Pump.
- 3. Exercise and stroke time valves closed.
- 4. Align system valves to required position for system to be placed inservice with reactor at operating conditions.
- 5. Restart RWCU Fump. (Standard plant practice is to position operator in pump room to monitor start. l RWCU pumps are located in a High Radiation Area and Health Physics escort is required.)
- 6. After pump is restarted and system flow stabilizes, I the domineralizers are returned to service.
13-8a Rev. 0 l 1
CSJ-V-7 (cont)
; NOTE: RWCU System is normally put into service prior to reactor startup. Returning the system to service with reactor at O normal operating conditions poses the potential for a system auto isolation which results in additional work of having to backwash the domineralizers before returning them to service.
- QUARTERLY PARTIAL '
- STROKE TESTING
- None. The system logic does not allow partial closure of
! these valves.
2 COLD SHUTDOWN TESTING: Exercise and stroke time each cold shutdown, with the test 4 frequency not to exceed testing once each quarter. ) ) i !O t l i l i 13-8b Rev. 0 1
l COLD SHUTDOWN JUSTIFICATION I CSJ-V-8 SYSTEM: Plant Service Water (l(2)P41) and Chilled Water System (1(2)P64) ; VALVE (S): IP41-F049, IP41-F050 2P64-F045, 2P64-F047 CATEGORY: A e CLASS: 2 FUNCTION: Drywell Air Cooler CIV QUARTERLY TEST REQUIREMENT: Exercise and stroke time per ISTC 4.2.1 COLD SHUTDOWN . TEST JUSTIFICATION: Closure of this valve would totally interrupt flow to the drywell coolers (Unit 1) or the drywell cooler condensers (Unit 2). This interruption of cooling water flow could , result in an increase in the drywell temperatures which could require shutting the plant down because of Technical Specification requirements. 4 QUARTERLY PARTIAL STROKE TESTING: None. The valve circuitry does not allow partial closure of this valve. ! O COLD SHUTDOWN TESTING: Exercise and stroke time each cold shutdown, with the test frequency not to exceed testing once per quarter. l I N l l i 1 l I O 13-9 Rev. O
. -- . .. -- - - - . _ ~ . - . - . . _ - _ _ - - _ . . . - . -
' COLD SHUTDOWN JUSTIFICATION L CSJ-V-g >
i j SYSTEM: Plant Service Water [, VALVE (S): IP41-F310A-D 2P41-F316A-D l i
. CATEGORY: B ;
,( CLASS: 3 !
- 1. .
. FUNCTION: Turbine Building Supply Shutoff !
fj ~ QUARTERLY TEST
. Exercise and stroke time per ITSC 4.2.1 REQUIREMENT:
i } COLD SHUTDOWN
' TEST JUSTIFICATION: The individual service water supply trains combine into a !
common header prior to entry .into the turbine building. 1 During normal operation at.least three service water pumps .; ji are required to provide cooling water to the safety and ; 3 non-safety related loads. I i Closure of one of these normally open valves in any _. sequence during normal operation would decrease flow to the 5 3 turbine building equipment by a minimum factor of one-third i and a maximum factor of two-thirds. A decrease in cooling water flow of this magnitude could cause increased . temperatures for components necessary for power operation i and result in a required power reduction, . forced shutdown
- or plant trip. ,
[ If one of these valves was to fail in its safety related i
- position (Closed) during exercising, increased temperatures
- and a resultant plant shutdown would most certainly occur.
f -QUARTERLY PARTIAL ! i STROKE TESTING: None. The valve circuity does not allow partial closure of 4 this valve. COLD SHUTDOWN
- TESTING: Exercise and stroke time each cold shutdown, with the test I frequency not to exceed testing once each quarter.
i 7 L l i i , LO l 13-10 Rev. 0 l 4
COLD SHUTDOWN JUSTIFICATION i ' CSJ-V-10 j SYSTEN: Reactor Building Closed Cooling Water (RBCCW)
- VALVE (S): IP42-F051, IP42-F052 2P42-F051, 2P42-F052 CATEGORY:. A
, CLASS: 2 ; FUNCTION: RBCCW to Recirculation Pumps CIV ). i ' QUARTERLY TEST i ! REQUIRENENT: Exercise and stroke time per ISTC 4.2.1 . l COLD SHUTDOWN i i TEST JUSTIFICATION: Closure of these normally open valves would result in a - i loss of the cooling water flow to the reactor recirculation j pumps which could result in possible damage to the pumps. ; 4 !
- QUARTERLY PARTIAL
! STROKE TESTING: None, valve operating circuitry does not provide for ' partial exercising. , [ COLD SHUTDOWN Exercise and stroke time each cold shutdown, with the test
- TESTING
frequency not to exceed testing once each quarter. 8 i i i f i 1 3 i e [o - 13-11 Rev. 0
+ -
. . _. _ _ ~ _ _ .__ . .
y COLD SHUTDOWN JUSTIFICATION CSJ-V-11 SYSTEM: Nuclear Boiler (Feedwater) (} , VALVE (S):. 2B21-F076A&B { CATEGORY: C l CLASS: 2 ! 4 FUNCTION: Feedwater Isolation QUARTERLY TEST-REQUIREMENT: Exercise quarterly or at cold shutdown per ISTC 4.5.1 COLD SHUTDOWN TEST JUSTIFICATION: Feedwater injection is required during normal operation. Isolating one of the feedwater lines to perform a closure ' test would require reducing reactor power by 'approximately 50% and would introduce main feedwater flow transients into the reactor due to an unsymmetrical injection pattern. This could affect other safety systems and potentially trip d the reactor. Closure testing consists of a leakrate type test and entry into the required areas, drywell and i mainsteam chase, during power operation is not allowed due the drywell being inerted and to high radiation levels in both areas. Performing this leakrate type test requires a
/
'(Q m ,/ significant amount of time to setup, isolate portions of the system, and perform valve alignments. Attempting to perform such testing during a cold shutdown could delay the
- startup of the unit.
QUARTERLY PARTIAL STROKE TESTING: None COLD SHUTDOWN TESTING: These normally-open feedwater check valves have an air assist operator to ensure tight closure and are provided with remote position indicating lights. Closure will be confirmed each cold shutdown, but not more frequently than - once per 3 months, by actuating the closure mechanism and observing the indicating lights. M (G 13-12 Rev. O
t .: ~ COLD SHUTDOWN JUSTIFICATION i i
, CSJ-V-12 SYSTEM: NuclearBoiler(Feedwater)
[N) i VALVE (S) .2B21-F077A&B j 7 i CATEGORYi AC' h CLASS:- I ; j FUNCTION: Feedwater Containment Isolation L QUARTERLY TEST [ d ' REQUIRENENT: Exercise quarterly or at cold shutdown per ISTC 4.5.1 f i COLD' SHUTDOWN - TEST ~ JUSTIFICATION: Feedwater injection is required during normal operation. ! (Close exercise) Isolatin!1 one of the feedwater lines to perform a closure i test wou'd require reducing reactor power by approximately ! 50% and would introduce main feedwater flow transients.into L the reactor due to .an- unsymmetrical injection pattern. i - This could affect other safety systems and potentially trip l j the reactor. Closure testing consists of a leakrate type I i j test and entry into the required areas, drywell and mainsteam chase, during power operation is not allowed due the drywell being inerted and to high radiation levels in !. both areas. Performing this leakrate type test requires a j.- significant amount of time to setup, isolate portions of the system, and perform valve alignments. Attempting to perform such testing during a cold shutdown could delay the startup of the unit. l (0 pen Exercise) Normal feedwater flow is significantly greater than the flowrate required for the open safety function (HPCI or RCIC injection). Therefore, the valve is proven capable of i opening to the required position with normal feedwater j injection during power operation. I l- QUARTERLY PARTIAL j STROKE TESTING: None o l COLD SHUTDOWN l' TESTING: These normally-open feedwater check valves have an air assist operator to ensure tight closure and are provided with remote position indicating lights. Closure will be j' confirmed each cold shutdown, but not more frequently than once per 3 months, by actuating the closure mechanism and 1 observing the indicating lights. The valves are maintained in the open position during normal operation by feedwater injection.
- , ADDITIONAL TESTING
- .LLRT in accordance with 10 CFR 50, Appendix J.
1 13-13 Rev. 0
I 14.0 VALVE REFUELING DUTAGE JUSTIFICATIDH LDG Justification Status R0J-V-1 s Submitted for NRC Review
- O'-- R0J-V-2 Submitted for NRC Review R0J-V-3 Submitted for NRC Review R0J-V-4 Submitted for NRC Review R0J-V-5 Submitted for NRC Review R0J-V-6 Submitted for NRC Review ROJ-V-7 Submitted for NRC Review R0J-V-8 Submitted for NRC Review R0J-V-9 Submitted for NRC Review R0J-V-10 Submitted for NRC Review 4
R0J-V-Il Submitted for NRC Review , R0J-V-12 Submitted for NRC Review R0J-V-13 Submitted for NRC Review R0J-V-14 Submitted for NRC Review R0J-V-15 Submitted for NRC Review R0J-V-16 Submitted for NRC Review R0J-V-17 Submitted for NRC Review _ R0J-V-18 Submitted for NRC Review R0J-V-19 Submitted for NRC Review R0J-V-20 Submitted for NRC Review ! ROJ-V-21 Submitted for NRC Review R0J-V-22 Submitted for NRC Review i R0J-V-23 Submitted for NRC Review R0J-V-24 Submitted for NRC Review i R0J-V-25 Submitted for NRC Review O ' \m> R0J-V-26 Submitted for NRC Review R0J-V-27 Submitted for NRC Review R0J-V-28 Submitted for NRC Review 1 i I i l l d O 14-1 Rev. 0
- 1 , v
.b REFUELING OUTAGE' JUSTIFICATION l ROJ-V-1 !
)
SYSTEM: Feedwater (1821 and 2B21) *
]
i' VALVE (S):.IB21-F010A&B. (
- 2B21-F010A&B ;
I
- CATEGORY:L AC
}
d CLASS:- 1 ! [ FUNCTION: Feedwater Line Injection.and CIV f i. TEST i- REQUIREMENT: Exercise quarterly or at cold shutdown per ISTC 4.5.1 l 4 BASIS FOR . i JUSTIFICATION:' Feedwater injection is required during normal operation. l (Close exercise) Isolating one of the feedwater lines to perform a closure ! i test would require reducing reactor power by approximately [ 50% and would introduce main.feedwater flow transients into r the reactor due to an unsymmetrical injection pattern. This j could affect other safety systems and potentially trip the i l reactor. Closure testing consists of a leakrate type test i and entry into the required areas, . drywell and. mainsteam :
- chase, during power operation is not allowed due the drywell l being inerted and to high radiation levels in both areas. ~
- / Performing this leakrate type test requires a significant
- amount of time to setup, isolate portions of the system, and
- perform valve alignments. Attempting to perform such testing i l during a cold shutdown could delay the startup of the unit. .!
~, . i (0 pen Exercise) Normal feedwater flow is significantly greater than the flowrate required for the open safety function (HPCI or RCIC ! injection). Therefore, the valve is proven capable of l opening to the required position with normal feedwater injection during power operation. ! p ALTERNATE TESTING: Open exercising is performed with normal feedwater injection ! to the reactor and closure exercising will be proven each 4 refueling outage during Appendix J, local leakrate testing. ! 4 i 4 ! 1 14-2 Rev. 0 l
- t. . - - . _. _
REFUELING OUTAGE JUSTIFICATION {p ROJ-V-2
, SYSTEM:- Nuclear toiler System (1821 and 2B21)-
I' VALVE (S): 1821-F013B, D, E, F, J, K,.L I 2821-F013A, C, E. H K, L, M
; CATEGORY: BC i 4- .
CLASS: I b FUNCTION: Nuclear Boiler System Over-Pressure Protection j (Automatic De-pressurization) l TEST REQUIREMENT: Exercise andjtroke time quarterly or at cold shutdown per i ISTC 4.2.4 7 j BASIS FOR 4
. JUSTIFICATION: Failure of these valves to close after exercising during :
- < power operation would result in a loss of reactor coolant. Additionally, these valves cannot be exercised at a pressure . below 100 psig and the position of the main stage of this 2 i j stage relief valve can only be determined by indirect means. l l ALTERNATE TESTING: Each pilot operating assembly is removed and sent 'to an ! ! independent testing laboratory each refueling outage. The l l pilot assemblies are inspected and set-point tested in ! i, accordance with ASME OMc Code,1994 Addenda, Appendix I to ; determine their operating condition. Each pilot assembly is t also stroke timed to monitor degradation and ensure that it actuates within an acceptable time range. Each pilot ; assembly is repaired and/or adjusted to ensure its !' operability prior to re-installation. ! Additionally, each valve is exercised using the manual ,
- control switch at least once every 18 months. ;
r ! This bench testing, pilot stroke timing, maintenance / , l adjustments, and inspection performed each refueling outage ! i should ensure that the valves are maintained in a state of
- operational readiness. ,
4 4: ; O ! i i 14-3 Rev. O ___.____ ________ ____ _ _ __ _ - - -- --m.
l l , REFUELING OUTAGE JUSTIFICATION l ROJ-V-3 SYSTEM: Nuclear Boiler, Reactor Recirculation, CS, HPCI, and RCIC VALVE (S): IB21-F015A-H, IB21-F015J-N, IB21-F015P, IB21-F015R&S, 1821-F041, IB21-F043A&B, IB21-F045A&B, 1B21-F047A&B, 1B21-F049A&B, 1821-F051A-D, 1B21-F053A-D, IB21-F055, IB21-F057, IB21-F059A-H, IB21-F059L-N, ! IB21-F059P, IB21-F059R-U, IB21-F061, IB31-F003A&B, IB31-F004A&B, ! 1831-F009A-D, IB31-F010A-D, IB31-F0llA-D, IB31-F012A-D, IB31-F040A-D, j IE21-F018A-C, IE41-F024A-D, IE51-F044A-D, i i 2B21-F041, 2821-F043A&B, 2821-F045A&B, 2B21-F047A&B, 2821-F049A&B, 2B21-F051A-D, 2B21-F053A-D, 2B21-F055, 2B21-F057, 2821-F059A-H, ! 2B21-F059L-N, 2B21-F059P, 2B21-F059R-U, 2B21-F061, 2B21-F070A-D, 2B21-F071A-D, 2821-F072A-D, 2B21-F073A-D, 2831-F003A&B, 2831-F004A&B, 2B31-F009A-D, 2831-F010A-D, 2B31-F011A-D, 2B31-F012A-D, 2B31-F040A-0, 2E21-F018A-C, 2E41-F024A-D, 2E51-F044A-D 1 l CATEGORY: AC l l CLASS: 1 FUNCTION: Active CIV l l TEST REQUIREMENT: ISTC 4.5.1 recuires quarterly or cold shutdown exercise i j testing of chec( valves and ISTC 4.5.2 describes the required !
- testing.
j O BASIS r0R JUSTIFICATION: The test requirements for check valves in the ASME OM Code i are intended for testing simple check valves. The excess flow check valves are designed to actuate and limit flow in j the case of an instrument line break downstream of the valve
- and installation of these valves meets the provisions of NRC Safety Guide 11 (Unit 1) or Reg. Guide 1.11 (Unit 2). The
! valves limit the leakage in the event of an instrument line j break to within the capacity of the reactor coolant makeup ! system. The more critical requirement for the valves is to } remain open when a fault does not exist to guarantee the d reactor protection function of the instruments. The { instruments served by these valves are critical during both ] plant operation and cold shutdown. Testing of these valves j requires the removal from service of portions of the reactor protection instrumentation for an extensive period of time. ALTERNATE TESTING: Section 3.6.1.3.8 (Unit I and Unit 2) of the Plant Technical Specifications specifies the frequency (at least once per 18 months) of testing to verify operability and flow limiting i' capability of all excess flow check valves. Testing will be performed in accordance with the Technical Specification requirements. i
;O j
l 14-4 Rev. 0 , I a
ll REFUELING OUTAGE JUSTIFICATION R0J-V-4 SYSTEM: -Main Feedwater (1821) >
- VALVE (S): .1821-F032A and B' CATEGORY: AC j- CLASS: l' l e
e FUNCTION: Feedwater Outboard CIV i TEST. REQUIREMENT: Exercise quarterly or at cold. shutdown per ISTC 4.5.1 ? 1 BASIS FOR , JUSTIFICATION: Feedwater. ' injection is requirrjd 'during normal operation. l Isolating one of the' feedwater lines- to perform a closure test would require reducing reactor power by approximately
- 50% and would introduce mair, feedwater flow transients into '
i the reactor due to an unsynetrical injection pattern. This
- could affect other safety systems and potentially trip the
4
. reactor. Closure testing consists-of a leakrate type-test l -and entry into the rer,uired areas, drywell and mainsteam
- chase, during power operation is not allowed due the drywell 4
being inerted and to high radiation levels in both areas. l Performing this leakrate type test requires a significant i amount of time to satup, isolate portions of the system, and , perform valve aligaments. Attempting to perform such testing during a cold shutdown could delay the startup of the unit. . ALTERNATE TESTING: The valves wi1* be confirmed to be exercised to the closed position each refueling outage by performing an Appendix J, l- type C local leakrate or similar type test. The acceptance . criteria of such testing should ensure that even slight valve l~ degradation will be detected and corrected each refueling outage. ; ! i i: { I 1 1 i
- t
.L 3 E i s ? 14-5 Rev. 0 l
l l-REFUELING OUTAGE JUSTIFICATION l R0J-V-5 '/ SYSTEM:' Mainstean (1821 and 2821)
- VALVE (S): IB21-F036A, B, C, D, E, F, G, H J, K, L >
2B21-F036A, B, C, D, E, F, G, H, K,.L. M
- CATEGORY
- C .-
I' CLASS:' 2' FUtTTION: MSRV Accumulator Check valves TEST REQUIREMENT: Verify reverse flow closure quarterly or at cold shutdown per ISTC 4.5.1 BASIS FOR , JUSTIFICATION: These valves cannot be tested during power operation because entry into the drywell is required. The drywell in inerted during normal operation. Because of the setup time, valve alignments and complexity of the test, attempting to perform these tests during cold shutdowns would potentially delay the startup of the unit. ALTERNATE TESTING: Reverse flow closure of these valves is verified each
, refueling outage by a leak test procedure similar to Appendix !
J, Type C, leakrate testing. l
- O i
l l t h 5 4-i i
' ,O V !
. 1 i l 14-6 Rev. 0 ,
REFUELING OUTAGE JUSTIFICATION ROJ-V-6 SYSTEM: Reactor Recirculation (1831 AND 2B31) VALVE (S): IB31-F013A&B, IB31-F017A&B 2831-F013A&B, 2831-F017A&B CATEGORY: AC CLASS: 1 FUNCTION: Recirculation Pump Seal Water 4 TEST REQUIREMENT: Verify reverse flow closure quarterly or at cold shutdown per , ISTC 4.5.1 BASIS FOR
- JUSTIFICATION: These valves are located in the Recirculation Pump Seal Water 1
injection lines which require continuous flow during power operation in accordance with the pump manufacturer's recommendations. Quarterly testing could damage the seals. Also, to attempt to perform this test during a cold shutdown i could delay the startup of the unit.
- ALTERNATE TESTING: Closure of these valves will be proven each refueling outage 4
by performing an Appendix J, type C local leakrate or similar 4 type test. 3 O l 1 4 i ) 4 i 14-7 Rev. O
. REFUELING OUTAGE' JUSTIFICATION ~
ROJ-V-7 l [ SYSTEM: 'CRD(101IIand2Cll)- *
' VALVE (S): IC11-HCU-ll4 [
'2C11-HCU-Il4 i
- CATEGORY: C CLASS: 2 1
FUNCTION: Scram Discharge . Volume'HCU Check Valve 7
- TEST REQUIREMENT:- Verify forward flow operability quarterly or at cold shutdown i per-ISTC 4.5.1 ,
} BASIS FOR
- l JUSTIFICATION: These ' valves are located on the scram discharge line of each ;
t CRD. Flow through each check valve is experienced only [ during the scram of the associated CRD unit. , 3 i ALTERNATE TESTING: The required flow is achieved through the valves during the j Technical Specification Control Rod Scram Insertion tests. i (1) As a minimum, 107, of the CRDs are scram timed on a j rotating basis every 120 days. 1 L'- (2) After each refueling outage or reactor shutdown it: 120 days, all control rods are scram tested from the fully I withdrawn position. i i r i i i i b 1 THE ALTERNATE TESTING DESCRIBED IN THIS REFUELING OUTAGE JUSTIFICATION , AGREES WITH THAT DESCRIBED IN NRC GENERIC LETTER 89-04, POSITION 7. i . O l i 14-8 Rev. O t
REFUELING. OUTAGE JUSTIFICATION' l . R0J-V-8 1
- 6
. SYSTEM: CRD (ICM and 2011) -
j I VALVE'(S):~IC11-HCU-115 !
.2C11-HCU-115 ;
CATEGORY: C ! CLASS: -2
-FUNCTION: Charging Water Header Check Valves TEST. REQUIREMENT: Verify reverse flow closure quarterly or at cold shutdown per ;
ISTC 4.5.1 + BASIS'FOR i TJUSTIFICATION: Reverse flow closure . verification of the charging water i header check valves requires that the CRD pumps be stopped
. in order to depressurize the charging water header. This -
test cannot be performed during normal operation because ; stopping the pumps resultr, in-loss of cooling water to all : CRD mechanisms and seal damage could result. Additionally, ! it -is impractical- to perform this testing during cold shutdown because the CRD pumps supply seal and motor purge ' water to the RWCU system pumps. RWCU is normally maintained in operation during shutdowns to maintain reactor coolant , chemistry in accordance with Technical Specification ; requirements. l ALTERNATE TESTING: Reverse flow closure will be confirmed at each refueling outage by performance of a HCU accumulator pressure decay : test. THE ALTERNATE TESTING DESCRIBED IN THIS REFUELING OUTAGE JUSTIFICATION AGREES WITH THAT DESCRIBED IN NRC GENERIC LETTER 89-04, POSITION 7. , i 1 f i l I
.14-9 Rev. O 4
i
-REFUELING OUTAGE JUSTIFICATION c
j R0J-V-9 SYSTEM: CRD (ICfl'AND 2C11) i VALVE (S): ICll-HCU-126, ICll-HCU-127
) 2Cll-HCU-126, 2011-HCU-127 r CATEGORY: B.
CLASS: 2 l FUNCTION: Scram Inlet and Outlet. Valves - 1 j- TEST REQUIREMENT: Exercise quarterly or at cold shutdown per ITSC 4.5.1 ! BASIS FOR
. JUSTIFICATION: The Hydraulic Control Units (HCU) are integrally designed ,
systems for controlling rod drive movements. Individual valve testing is not possible without causing a control rod ! scram with a resulting change in core reactivity. Quarterly i testing of these valves increases the potential to violate i plant Technical Specifications which govern the methods and i frequency of reactivity changes. In addition, these are
- power operated valves that full-stroke in milliseconds and
- are not equipped with remote position indicators. Therefore, measuring their full-stroke time is impractical. Verifying that the associated control rod meets the scram insertion
. time limits defined in the Technical Specifications provides
- an alternate method of detecting valve degradation. Trending the stroke times of these valves is impractical and unnecessary since they are indirectly stroke timed and no i meaningful correlation between the scram time and valve j stroke time can be obtained.
! ALTERNATE TESTING: Technical Specification Control Rod Scram Insertion Time , testing serves to verify proper operation of each of these ! valves. I- (1) As a minimum, 10% of the CRDs are scram timed on a j rotating basis every 120 days. f (2) After each refueling outage or reactor shutdown a 120
- ' days all control rods are scram tested from the fully withdrawn position.
THE ALTERNATE TESTING DESCRIBED IN THIS REFUELING OUTAGE JUSTIFICATION AGREES WITH THAT DESCRIBED IN NRC GENERIC LETTER 89-04, POSITION 7. t L O L 14-10 Rev. O' ;
REFUELING OUTAGE JUSTIFICATION R0J-V SYSTEM: Standby L'iquid Control (IC41 and 2C41) ' VALVE (S): IC41-F006, IC41-F007 2C41-F006, 2C41-F007 CATEGORY: AC CLASS: 1 FUNCTION: SBLC Injection Line Isolation TEST REQUIREMENT: Verify forward flow operability and closure quarterly or at cold shutdown per ISTC 4.5.1 SASIS FOR JUSTIFICATION: Forward flow exercising can only be performed by injecting into the reactor vessel using the SBLC pumps. The pumps are normally aligned to a sodium pentaborate storage tank and they would have to be aligned to demineralized water for exercise testing of the check valves. The associated piping would have to be flushed prior to the test and refilled with sodium pentaborate after the open exercise test. Closure testing can only be performed by a leakrate type test. Testing of these normally closed valves quarterly or during cold shutdown would require: (1) actuation and restoration of the explosive squib valves, 1(2)C41-F004A(B), to allow injection into the RPV (open exercise) (2) personnel entry into the primary containment to operate , the manual test boundary valve 1(2)C41-F008 (close exercise) j and, i (3) disablement of the entire SBLC system (close exercise). Due to the time required to setup the testing, the complexity of the test, and the time required for associated valve alignments, attempting to perform this testing at cold shutdown could potentially delay startup of the unit. l ' l ALTERNATE TESTING: These valves are full flow exercised once each refueling outage during Technical Specifications surveillance testing. Closure is verified each refueling outage by performing an Appendix J, type C local leakrate or similar type test. G .V l 14-11 Rev. 0
REFUELING OUTAGE JUSTIFICATION ROJ-V-Il 1 i SYSTEM: TIP Syst8m (ICSI and'2C51) *
' VALVE (S): IC51-F3017 2C51-F3017 CATEGORY: 'AC CLASS:' 2-FUNCTION: CIV TEST REQUIREMENT: Verify reverse closure quarterly or at cold shutdown per.ISTC 4.5.1 ,
l BASIS FOR , JUSTIFICATION: The only way to verify reverse closure is by performing a l
'leakrate type test. These normally open check valves are ;
. located inside the primary containment and therefore are '
inaccessible during power operation. The primary containment is inerted during normal operation and personnel entry is - prohibited. Therefore,' testing during normal operation is impracticable.- Performing a leakrate type test requires a significant amount - of _ time to setup the test and align the associated valves. To attempt to perform these tests during an unscheduled cold-O shutdown could delay the startup of the unit. ALTERNATE TESTING: Reverse flow closure of these valves will be proven each , refueling outage by performing an Appendix J, type C local leakrate or similar type test. i-l i O t I , 14-12 Rev. O f
. a. -.
t REFUELING OUTAGE JUSTIFICATION ROJ-V-12' 4 ^
~ SYSTEM: ;RHR-(IEll and 2E11)
- f l
VALVE (S):-IE11-F046A-D
-2E11-F046A-D-
' CATEGORY: C CLASS: '2-
- i j
. FUNCTION: RHR pump minimum' flow line check valve TEST REQUIRENENT: . ' Verify forward flow operability quarterly or at cold shutdown per_ISTC 4.5.1 BASIS FOR- -
, JUSTIFICATION: These valves are located in the RHR pump minimum flow line. l The minimum flow line was not' provided with . installed instrumentation to allow confirmation of full flow exercising l of the check valves in conjunction with RHR pump surveillance i testing. !- ALTERNATE TESTING: Partial flow is achieved through the check valves during
- j. quarterly RHR pump surveillance testing. Additionally, one ;
o valve from each unit will be disassembled,-visually inspected ' and manually full stroke exercised each refueling outage. , + Disassembly of the valves. requires that the associated loop of RHR be declared inoperable, therefore performing this valve disassembly during an unplanned cold shutdown could potentially delay startup of the unit. i . 1 . l . i i r l i 1 THE ALTERNATE TESTING DESCRIBED IN THIS REFUELING OUTAGE JUSTIFICATION 1 ' AGREES WITH THAT DESCRIBED IN NRC GENERIC LETTER 89-04, POSITION 2. , l i ; j i
- ,n '
iQ. i i 14-13 Rev. O ;
REFUELING OUTAGE JUSTIFICATION
- < ROJ-V-13 r SYSTEM
- Core Sprity (IE21 and 2E21) e VALVE (S): IE21-F006A,B 1
. 2E21-F006A,B CATEGORY: .AC CLASS: 1 l
- . FUNCTION
- Core Spray Injection and PIV l
TEST REQUIREMENT: Verify forward flow operability quarterly or at cold shutdown per ISTC 4.5.1 l BASIS FOR RELIEF: System configuration does not provide for full or partial , i flow exercise testing during normal operation. Core spray l i injection during normal operation is impossible because reactor pressure is significantly greater than core spray injection pressure. i 1 Power is removed from the equalization valve (1(2)E21- 2 4 F037A(B)) during normal operation making partial exercising impractical because these valves function as simple check 1- valves. These valves are inaccessible, located inside the l primary containment, PIVs and erroneous signal indications A caused by exercising could not be readily distinguished from V actual valve problems without shutting down the plant, de-inerting the containment, and performing a containment entry. The only possible way to flow test these valves is by injecting suppression pool water or condensate storage tank . (CST) water into the RPV. Utilizing either suction source results in a significant degradation of the reactor coolant quality due to the relatively poor quality of the suppression pool water or the relatively poor quality of stagnant water in the core spray piping. A significant amount of time would be required to restore reactor coolant to the Technical Specification required quality. Therefore exercising with flow-at cold shutdown or refueling is impractical. i These valves are located inside the primary containment and are therefore inaccessible during normal operation or at cold , shutdown unless the containment is de-inerted. The
)
i containment is not de-inerted during an unplanned shutdown - unless containment entry is necessary. Therefore mechanical exercising quarterly or at cold shutdown is impractical. ALTERNATE TESTING: Each check valve will be mechanically exercised per ISTC 4 4.5.4(b) during each ' refueling outage. This mechanical l exercising, in conjunction with OM Code local leakrate ! ,q ' testing each . refueling outage should provide sufficient tg confirmation of valve operability. j 14-14 Rev. O l
. . - . - . . - - . ~ - . - - - .- - - - . - . - - -.- ..-
t
-REFUELING OUTAGE JUSTIFICATION 1
{ 'ROJ-V-14 l
-SYSTEM:' Core Sptay (1E21'and 2E21) e i' VALVE (5):'_IE21-F044A,B- .
2E21~-F044A,B
~
CATEGORY:' C-3 j
- CLASS:. 2 i
, : FUNCTION: Containment Isolation Ba'rrier . . ~ .
. 3
- . TEST REQUIREMENT
- Reverse flow closure quarterly or at cold shutdown per ISTC i 4.5.1 B' ASIS FOR :
JUSTIFICATION:__ These valves function as containment isolation barriers. The only viable means of proving closure is by performing a leak rate or pressure test. To perform this test quarterly would ' require removing the associated systems from operation. - This ; type testing requires a significant amount of time setup, ' l
- align valves and perform the test and testing at cold <
shutdown could potentially delay startup of the unit.
- Since these valves only provide a containment barrier function and allowable leakage limits are significantly
[O
- V greater than allowed for. containment isolation valves, and the fact that these valves are not exposed to severe i operating conditions which would promote rapid degradation; leak rate or pressure testing at a refueling outage frequency will provide sufficient test results to ensure a margin of safe component operability.
E l Appendix J local leakrate testing requirements are not ! applicable to these valves. Review of previous testing and L maintenance history does not indicate any abnormal failure
- rate or maintenance requirements for these valves.
i l- These valves are located in the jockey pump recirculation l line back to the suppression pool. Performing the pressure
- test quarterly would require removing the associated jockey pump (s) from service and would likely result in not maintaining the associated train of RHR and Core Spray piping
. full of water as required by Technical Specifications. This would result in unnecessary ECCS unavailability and potential entries into Technical Specification 3.0.3. Per Technical {
Specifications the RHR and Core Spray Systems are normally i l required to be operable during brief periods of cold I shutdown. This testing can be more safely and efficiently L performed during refueling outages.
' ALTERNATE TESTING:' LValves will be reverse flow closure tested each refueling
' outage by performance of' a leakrate test similar to an
- Appendix J, type C test. . The equipment utilized for this testing allows measurement of the leakage rate from the test
(. 14-15a Rev. O ! L i l .. .-
__ ._ .._ .. . . _ . . . _ . . . _ . . - . . _ _ _ . . ~ . . . . . _ _ _ _ . . . . _ . _ . _ = _ . . _ . . _ . . . _ ,
- i. ROJ-V-14 (cont) -
boundary and trending of any significant changes in leakage l l characteristics. !
- s ,
i i i i t l t 1 i i 1 i l i . i l 4 l l i 14-15b Rev. 0
(. , - iij . REFUELING OUTAGE JUSTIFICATION [ , R0J-V-15
' SYSTEM:L LHPCI(IE41and'2E41)L +
VALVE (S)::IE41-F021 j -2E41-F021
- 1. j
[ CATEGORY: C l 1 CLASS:: 2 4
- FUNCTION: . Containment ' Isolation Barrier 1, -
Reverse flow closure quarterly or at cold shutdown per ISTC TEST REQUIREMENT: 4.5.1 b BASIS FOR - i ' JUSTIFICATION: These valves function as containment isolation barriers. The: i only viable means of prov',ng closure is by performing a leak i rate or pressure test. To perform this test quarterly would l
- -require removing the associated systems from operation. 1 t
i Since these valves only provide a containment barrier function and allowable leakage limits are significantly
- greater than allowed for containment isolation valves, and -
the fact that these -valves are not exposed to severe : i operating conditions which would promote rapid degradation; ' r leak rate or pressure testing at a refueling outage frequency : L- will provide sufficient test results to ensure a margin of
- safe component operability.
! The valves are located in the HPCI turbine exhaust to suppression pool line. Testing these valves quarterly during ! i power operation results in removing the HPCI system from the i operable condition and causes unnecessary safety system : I unavailability. To perform the required valve' line ups, i equipment setup and perform the test takes a significant ! i. amount of time for each test. Therefore, performing the ; l- tests at cold shutdown could delay the startup of the unit. l ! Because HPCI is a standby system which is normally only i , operated during surveillance testing, these valves do not ' experience service conditions which would promote rapid ; j degradation. ! i , ALTERNATE TESTING: Valves will be reverse flow closure tested each refueling : O outage by performance of'a local leakrate test similar to an ! Appendix J, type C test. The equipment utilized for this ; testing allows measurement of the leakage rate from the test t boundary and trending of any significant changes in leakage ' i characteristics. L l r ;
- 14-16 Rev. O !
l - . - .. . .-.
\
,- ~ - ...- -.~ - - - -.- -. - ,..-.-.
i r REFUELING.0UTAGE JUSTIFICATION l
'ROJ-V-16 I ; ' SYSTEM- ;HPCI (IE41'an'd-2E41) -
- j. , VALVE (S): ..lE41-F022
- . 2E41- F022~ l s i i
L ' CATEGORY: 'Cl 1 4 > -j' CLASS:- 2- }
; FUNCTION:; Containment Isolation Barrier '
l {7 TEST REQUIREMENT: .. Reverse flow closure quarterly or at' cold shutdown per ISTC I 4.5.1 l BASIS FOR 0 JUSTIFICATION: I These valves function as containment isolation barriers. The
- only viable means of proving closure is by performing a leak i rate or pressure test. To perform this test quarterly would i
[: require removing the associated systems from operation. ! , i
- Since these valves only provide a containment barrier !
function and allowable leakage limits are . significantly l l greater than allowed for containment isolation valves, and j i b .the . fact that these valves are not exposed to severe ' operating conditions which would promote rapid degradation; leak rate or pressure testing at a refueling outage frequency ,\ will provide sufficient test results to ensure a margin of safe component operability. o F These valves are located in the HPCI turbine exhaust drain
- to suppression pool line. Testing these valves quarterly during power operation will result in removing the HPCI L system from the- operable condition ~ and would cause
- unnecessary safety system unavailability. To perform the
! required valve line ups, equipment setup and perform the test
- takes a significant amount of time for each test. Therefore,
- performing the tests at cold shutdown could delay the startup of the unit. Because HPCI is a standby system which is normally only operated during surveillance testing these
- valves do not experience service conditions whic.h would
[ promote rapid degradation. ALTERNATE. TESTING: Valves will be reverse flow closure tested each refueling , outage by performance of a local leakrate test similar to an , Appendix J, type ~C test. Additionally, these valves are i ! disassembled, visually inspected, and full stroke exercised l l '- in accordance with NRC GL 89-04, Position 2. The inspection- '
- during disassembly should adequately detect any degradation in sufficient time to take corrective actions prior to the valve becoming inoperable.
O t iIt L 14-17 Rev. O I 1
REFUELING OUTAGE JUSTIFICATION.
-R0J-V-17 SYSTEM:- . HPCI (IMI and 2E41) *
- ' VALVE (S): IE41-F040-2E41-F040 F
1 CATEGORYi~C: [ ' CLASS: 2 FUNCTION: Containment Isolation Barrier 4: sTEST REQUIREMENT: Reverse flow closure quarterly or at cold shutdown per ISTC i 4.5.1.
^
BASIS FOR g : JUSTIFICATION: These valves function as containment isolation barriers. The t only viable means of proving closure is by performing a leak rate or pressure test. To perform this test quarterly would require removing the associated systems from operation. i 1 Since these valves only provide a containment barrier ,
- function and allowable leakage limits are significantly ;
F greater than allowed for containment isolation valves, and 1
- the fact that these valves are not exposed to severe '
operating conditions which would promote rapid degradation; O leak rate or pressure testing at a refueling outage frequency will provide sufficient test results to ensure a margin of safe component operability.
- 4 L
These valves are located in the HPCI turbine exhaust to suppression pool line. Tes' ting these valves quarterly during > power operation will result in removing the HPCI system from
- the operable condition and would cause unnecessary system i unavailability. To perform the required valve line ups, equipment setup and perform the test takes a significant amount of time for each test. Therefore, performing the '
tests at cold shutdown could delay the startup of the unit. L ' Because HPCI is a standby system which is normally only operated during surveillance testing, these valves do not experience service conditions which would promote rapid degradation. ' ALTERNATE TESTING: Valves will be reverse flow closure tested each refueling ! outage by performance of a local leakrate test similar to an : Appendix J, ' type C test. Additionally, these valves are > disassembled, visually inspected, and full stroke exercised ' in accordance with NRC GL 89-04, Position 2. The inspection E sduring disassembly should adequately detect any degradation in sufficient time to take corrective actions prior to the valve becoming inoperable. ;
- , 14-18 Rev. 0
^
REFUELING 0UTAGEJUNTIFICATION R0J-V-18 SYSTEM:' .HPCI (IM1 and 2E41) -
. VALVE _(S) :~ IE41-F046 !
2E41-F046 p CATEGORY: C i , i CLASS: 2
- FUNCTION: Containment Isolation Barrier L
L TEST REQUIREMENT: Reverse flow closure quarterly or at cold shutdown per.ISTC
- 4.5.1 1
- BASIS FOR JUSTIFICATION: These valves function as containment isolation barriers. The
'only viable means of proving closure is by performing a leak rate or- pressure test. To perform this test quarterly would
- require removing the associated systems from operation.
Since' these valves only provide a containment barrier function and allowable leakage limits are significantly ! greater than allowed for containment isolation valves, and i the fact 'that these valves are not exposed to severe , operating conditions which would promote rapid degradation; l L/T V leak rate or pressure testing at a refueling outage frequency : will provide sufficient test results to ensure a margin of i
- . safe component operability. l These valves are located in the HPCI minimum flow line to i
suppression pool. Testing any of these valves quarterly during power operation will result in removing the HPCI 1 l system from ti e operable condition and would cause
- unnecessary safety system unavailability. Testing these I
- valves quarterly during power operation will result in !
- removing the HPCI system frem the operable condition and ,
would cause unnecessary system unavailability. To perform i the required valve line ups, equipment setup and perform the i- test takes a significant amount of time for each test. [ Therefore, performing the tests at cold shutdown could delay l the startup of the unit. Because HPCI is a standby system which is normally only operated during surveillance testing, ' these valves do not experience service conditions which would promote rapid degradation. i. I ALTERNATE TESTING: Valves will' be reverse flow closure tested each refueling ! outage. by performance of a 'leakrate test similar to an i ' Appendix J, type C test. Additionally, these valves are disassembled, visually inspected, and full stroke exercised i in accordance with NRC GL 89-04, Position 2. The inspection during disassembly should adequately detect any degradation in sufficient time to take corrective actions prior to the , ivalve becoming inoperable. l l 14-19 Rev. 0 1 l
REFUELING OUTAGE JUSTIFICATION R0J-V-19. SYS TEM: -* HPCI (IEM 'and 2E41) VALVE (S): IE41-F049 2E41-F049 CATEGORY: C CLASS: 2 FUNCTION:' Containment Isolation Barrier TEST. REQUIREMENT: Reverse flow closure quarterly or at cold ~ shutdown per ISTC 4.5.1 BASIS FOR
. JUSTIFICATION:' These valves function as containment isolation barriers. The only viable means of proving closure is by performing a. leak -
i rate or pressure test. To perform this test quarterly would require removing the associated systems from operation. Since these valves only provide a containment barrier i function and allowable leakage limits are significantly greater than allowed for containment isolation valves, and the fact that these valves are not exposed to severe operating conditions .which would promote rapid degradation; leak rate or pressure testing at a refueling outage frequency O will provide sufficient test results to ensure a margin of safe component operability. The valves are located in the HPCI turbine exhaust to suppression pool line. Testing these valves quarterly during power operation results in removing the HPCI system from the , operable condition and causes unnecessary safety system unavailability. To perform the required valve line ups,
- equipment setup and perform the test takes a significant L
amount of time for each test. Therefore, performing the tests at cold shutdown could delay the startup of the unit. l Because HPCI is a standby system which is normally only operated during surveillance testing, these valves do not experience service conditions which would promote rapid degradation. ALTERNATE TESTING: Valves will be reverse flow closure tested each refueling outage by performance of a local leakrate test similar to an Appendix J, type C test. The equipment utilized for. this
. testing allows measurement of the leakage rate from the test boundary and trending of any significant changes in leakage
- i. characteristics.
O 14-20. Rev. 0
REFUELING OUTAGE JUSTIFICATION R0J-V-20
. SYSTEM: RCIC (1951 and 2E51)
VALVE (S): IE51-F001 2E51-F001 CATEGORY: C CLASS: 2 l- FUNCTION: Containment Isolation Barrier TEST REQUIREMENT: Reverse flow closure quarterly or at cold shutdown per ISTC 4.5.1 i BASIS FOR JUSTIFICATION: These valves function as containment isolation barriers. The only viable means of proving closure is by performing a leak L rate or pressure test. To perform this test quarterly would require removing the associated systems from operation. l Since these valves only provide a containment barrier function and allowable leakage limits are significantly greater than allowed for containment isolation valves, and the fact that these valves are not exposed to severe operating conditions which would promote rapid degradation; L leak rate or pressure testing at a refueling outage frequency l will provide sufficient test results to ensure a margin of safe component operability. These valves are located in the RCIC turbine exhaust drain
- line to suppression pool. Testing these valves quarterly during power operation will result in removing the RCIC system from the operable condition and would cause unnecesscry system unavailability. To perform the required l
valve line ups, equipment setup and perform the test takes a significant amount of time for each test. Therefore, performing the tests at cold shutdown could delay the startup of the unit. Because RCIC is a standby system which is normally only operated during surveillance testing, these valves do not experience service conditions which would promote rapid degradation. ALTERNATE TESTING: Valves will be reverse flow closure at each refueling outage by performance of a local leakrate test similar to an Appendix J type C test. The equipment utilized for this testing allows measurement of the leakage rate from the test boundary and trending of any significant changes in leakage characteristics.
.U 14-21 Rev. 0
F 1
)
REFUELING OUTAGE JUSTIFICATION R0J-V-21 SYSTEM:
- RCIC (IE51 and 2E51)
VALVE (S): IE51-F002 2E51-F002 i CATEGORY: C , i CLASS: 2 FUNCTION: Containment Isolation Barrier TEST REQUIREMENT: Reverse flow closure quarter 1'y or at cold shutdown per ISTC 4.5.1 BASIS FOR JUSTIFICATION: These valves function as containment isolation barriers. The only viable means of proving closure is by performing a leak rate or pressure test. To perform this test quarterly would require removing the associated systems from operation. Since these valves only provide a containment barrier function and allowable leakage limits are significantly greater than allowed for containment isolation valves, and the fact that these valves are not exposed to severe operating conditions which would promote rapid degradation; i leak rate or pressure testing at a refueling outage frequency ( will provide sufficient test results to ensure a margin of safe component operability. These valves are located in the RCIC barometric condenser , vacuum pump discharge line to the suppression pool. Testing : these valves quarterly during power operation will result in removing the RCIC system from the operable condition and : would cause unnecessary system unavailability. To perform t the required valve line ups, equipment setup and perform the test takes a significant amount of time for each test. Therefore, performing the tests at cold shutdown could delay the startup of the unit. Because RCIC is a standby system which is normally only operated during surveillance testing, these valves do not experience service conditions which would promote rapid degradation. - ALTERNATE TESTING: Valves will be reverse flow closure at each refueling outage ! by performance of a local leakrate test similar to an Appendix J type C test. The equipment utilized for this testing allows measurement of the leakage rate from the test boundary and trending of any significant changes in leakage characteristics. m i 14-22 Rev. 0
L
'REFUELINGLOUTAGE JUSTIFICATION p ROJ-V-22 LSYSTEM: .RCIC (1561'and 2E51)
- VALVE (S): IE51-F021 .
- 2E51-F021: ,
J
. CATEGORY:- C.
j CLASS:' 2-FUNCTION: Containment Isolation Barrier [ TEST REQUIREMENT: Reverse flow closure quarterly or at cold shutdown per ISTC *
; 4.5.1 BASIS FOR ;
' JUSTIFICATION: These valves function as containment isolation barriers. The only viable means of proving closure is by performing a leak io -
rate or pressure test. To perform this test quarterly would i
- require removing the associated systems from operation.
Since these valves only provide a containment barrier i , function and allowable leakage limits are significantly
- greater than allowed for containment isolation valves, and ,
the fact that these valves are not exposed to severe i operating conditions which would promote rapid degradation; : i leak rate or pressure testing at a refueling outage frequency t j will provide sufficient test results to ensure a margin of ! l safe component operability. i These valves are located in the RCIC minimum flow line to i suppression pool. Testing these valves quarterly during i , power operation will result in removing the RCIC system from the operable condition and would cause unnecessary system , unavailability. To perform the required valve line ups,
- equipment setup and perform the test takes a significant ;
amount of time for each test. Therefore, performing the F tests at cold shutdown could delay the startup of the unit. . , Because RCIC is a standby system which is normally only l 1 operated during surveillance testing, these valves do not ! experience service conditions which would promote rapid i l degradation. ALTERNATE TESTING: Valves will be reverse flow closure at each refueling outage ! by performance of a leak rate test similar to an Appendix J ;
- type C test. Additionally, these valves are disassembled, -
visually inspected, and full stroke exercised in accordance ! l with- NRC GL 89-04, Position 2. The inspection ~ during i ' disassembly should adequately detect any degradation in ; sufficient time to take corrective actions prior to the valve ' becoming inoperable. : I O .i 14-23 Rev. O ! r :
! ' REFUELING OUTAGE JUSTIFICATION l ROJ-V-23 . SYSTEMi RCIC (IE!PI and 2E51) - VALVE (S):-IE51-F028 2E51-F028 CATEGORY: C i CLASS: 2 l FUNCTION: Containment Isolation Barrier ) TEST' REQUIREMENT: Reverse flow closure quarterly or at cold shutdown per ISTC , 4.5.1 BASIS FOR
- JUSTIFICATION
- -. These valves function as containment isolation barriers. The
.. only viable means' of proving closure is by performing a leak i_ rate or pressure test. To perform this test quarterly would' ! , require removing the associated systems from operation. I [ Since these valves only provide a containment barrier
- t. function and allowable leakage limits are significantly
- greater than allowed for containment isolation valves, and i the fact that these valves are not exposed to severe i
- i. operating conditions which would promote rapid degradation; i leak rate or pressure testing at a refueling outage frequency L U(^\ will provide sufficient test results to ensure a margin of
! safe component operability, i i These valves are located in the RCIC turbine exhaust drain line to the suppression pool. Testing these valves quarterly 0 during power operation will result in removing the RCIC system from the operable condition and would cause
- unnecessary system unavailability. To perform the required l
! valve line ups, equipment setup and perform the test takes , i a significant amount of time for each test. Therefore, i
- - performing the tests at cold shutdown could delay the startup of the unit.
3 Because RCIC is a standby system which is ; normally only operated during surveillance testing, these e valves do not experience service conditions which would j promote rapid degradation. ALTERNATE TESTING: Valves will be reverse flow closure at each refueling outage
, .. by performance of a local leakrate test similar to an l Appendix J type C test. The equipment utilized for this i
testing allows measurement of the leakage rate from the test ! boundary and trending of any significant changes in leakage
;L t
characteristics. 4 . O c i 14 Rev. 0 p e -y.- .- . .i%- - . . - - - , _ y , - - - - * '
4 REFUELING OUTAGE JUSTIFICATION ROJ-V-24 SYSTEM: RCIC (IEll and 2E51) - VALVE (S): 1E51-F040 l ! 2E51-F040 1 CATEGORY: C CLASS: 2 L FUNCTION: Containment Isolation Barrier
- TEST REQUIREMENT
- Reverse flow closure quarterly or at cold shutdown per ISTC 1 4.5.1 BASIS FOR i
- JUSTIFICATION: These valves function as containment isolation barriers. The ,
1 only viable means of proving closure is by performing a leak t rate or pressure test. To perform this test quarterly would , require removing the associated systems from operation.
- Since these valves only provide a containment barrier t l function and allowable leakage limits are significantly greater than allowed for containment isolation valves, and :
. the fact that these valves are not exposed to severe
- operating conditions which would promote rapid degradation; j i^ leak rate or pressure testing at a refueling outage frequency i
C will provide sufficient test results to ensure a margin of safe component operability.
- i These valves are located in the RCIC turbine exhaust line to F
the suppression pool. Testing these valves quarterly during power operation will result in removing the RCIC system from the operable condition and would cause unnecessary system
- unavailability. To perform the required valve line ups, equipment setup and perform the test takes a significant !
amount of time for each test. Therefore, performing the 4-tests at cold shutdown could delay the startup of the unit. Because RCIC is a standby system which is normally only
- operated during surveillance testing, these valves do not experience service conditions which would promote rapid
. degradation. l ALTERNATE TESTINC: Valves will be reverse flow closure at each refueling outage by performance of a local leakrate test similar to an Appendix J type C test. The equipment utilized for this testing allows measurement of the leakage rate from the test boundary and trending of any significant changes in leakage i characteristics. i 1 O ; 14-25 Rev. 0 l
REFUELING OUTAGE JUSTIFICATION i
- l. ROJ-V-25 SYSTEM:. .HPCI (IEM and-2E41) --
, VALVE (S): IE41-F102, 1E41-F103 L 2E41 F102,-2E41-F103 i ! . CATEGORY: C
- CLASS: 12.
! FUNCTION:- Steam Exhaust Line Vacuum Breakers ! TEST REQUIREMENT: Verify forward flow exercise and reverse flow . closure
- . quarterly or at cold shutdown per ISTC 4.5.1 j
}
-BASIS FOR .. . . !
. JUSTIFICATION: Operability of these simple check valves cannot be proven by - ,
[ normal process flow since they. are acting as vacuum relief ; 4 valves. If a vacuum forms in the turbine exhaust line due ' r to steam condensation, the disc will' lift from the seat-i
- sufficiently to allow air into the line.- Otherwise, there !
L is no movement of the disc.. . l
- ALTERNATE TESTING: During the local leakrate test for valves 1(2)E41-F104 and !
! 1(2)E41-Fill the piping is pressurized between' valves i 1(2)E41-F111and1(2)E41-F104. Valve 1(2)E41-F103 will then , be vented as part of the test to ensure that flow passes i
- through the check valves thus ensuring their vacuum breaker
- function since this flow rate will be greater than that e
required for vacuum relief. 1 Closure of the valves is proven during quarterly HPCI pump . ; surveillance testing. If the valve did not close, steam ! j' would bypass the suppression pool into the torus bay air l . space and cause a resultant temperature increase. ) o { Reverse flow closure is also proven in conjunction with LLRT [ of valves 1(2)E41-F104 and 1(2)E41-F111. With the boundary ? between valves 1(2)E41-F104 and 1(2)E41-F111 pressurized, the
- 1 E41-F111 valve is opened and each valve,1(2)E41-F102 and
j 1 E41-F103, is confirmed to be closed. ! c . L 1 The Appendix J, type C LLRT or a similar type test for valves .! 1(2)E41-F104 and 1(2) E41-F111 will be performed each j refueling outage to confirm open and close exercisng of. valves 1(2)E41-F102 and 1(2)E41-F103. ; i i
+
- i
- 14-26 Rev. O !
i
l REFUELING OUTAGE JUSTIFICATION' ROJ-V-26 ) 4 SYSTEM:. Reactor elater Cleanup (IG31) , ! , VALVE (S): . IG31-F039 and IG31-F203 i CATEGORY: . AC . 'i J l CLASS: 1 ^ FUNCTION: RWCU Return Line CIV I ! TEST REQUIREMENT: Verify reverse flow closure quarterly or at cold shutdown per j ISTC 4.5.1 a i BAS'IS FOR' ' JUSTIFICATION: These normally open check valves are located in the RWCU ' : i-return line to the reactor vessel' thru each feedwater line. To establish the necessary test boundary for each of:these valves will require closure of the manual feedwater valve, , IB21-F0llA(B), which is located inside primary containment. Entry into primary containment is not possible during normal ' j- operation due to the nitrogen inerted atmosphere; To perform the test during cold shutdown would require the I [ same test boundary as above. Therefore, performing the test i would require; de-inertion of the primary containment, j multiple personnel entries into a potential high radiation exposure area, valve manipulations, setup of test equipment, i actual test performance, evaluation of test results, re-E establishment of normal system alignments and Technical 3 Specification required nitrogen inertion of the containment upon startup. Performing these activities would require a significant amount of time and could delay the startup of the
- - unit from an unplanned cold shutdown. Therefore, due to the i problems associated with an inerted containment, multiple l personnel containment entries to support the tests, ALARA
' concerns and the actual test duration, performance during cold shutdown seems unwarranted. i ! ALTERNATE TESTING: These check valves will be confirmed to close each refueling
- - outage during an Appendix J, type C local leak rate test.
1 i i ,q
;y 1 ' 14-27 Rev. O I l
REFUELING OUTAGE JUSTIFICATION
- R0J-V-27 SYSTEM
- P1 ant'Strvice Water (IP41)
- VALVE (S): IP41-F552A & C :
I CATEGORY: C ! j' -CLASS: 3 l 1 l . FUNCTION: Diesel Generator Cooling Water Discharge Line Check Valve s i TEST REQUIREMENT: Verify forward flow exercise quarterly or at cold shutdown i i per ISTC 4.5.1 i i '
' BASIS'FOR !
j JUSTIFICATION: These normally open check valves are located in the cooling water discharge lines from diesel generators IA and IC.
- - There are no system design provisions to measure cooling
- j water flow and thus verify forward flow operability. :
- 5 l-.
Each diesel generator is operated for a minimum of one hour ! at 1710 - 2000 kW (approx. 60 percent of continuous rated ;
- _ . load) during testing once each month. Partial forward flow j i operability is verified during this test by monitoring diesel
{ generator oil and Jacket cooling water temperatures. If !
- . sufficient cooling water flow was not provided to the diesel i i generator, elevated oil and jacket cooling water temperatures !
j would be evident. !
- Each diesel generator is also operated for a minimum of one '
! hour at 2250 - 2400 kW (approx. 80 percent of continuous : rated load) semi-annually. Partial flow operability is again l verified during this test by monitoring diesel generator oil ! and jacket cooling water temperatures. !
- . t l During each refueling outage (at least once per 18 months) t
- each diesel generator is operated for a minimum of 24 hours. '
- During the first two' hours of this test, the diesel is loaded l to 2
- 3000 kW (approx. 105 percent of continuous rated load) ,
- and during the remaining 22 hours of this test, the diesel ;
- -is loaded to 2775 - 2825 kW (approx. 90 percent of continuous '
- j. ratedload). Diesel generator oil and jacket cooling water .
temperatures are monitored during this test to ensure that sufficient cooling water is provided. i
^
Acceptable operation of the diesel generators during the
- monthly and-semi-annual tests verifies that the valves are ,
not stuck in the closed position. Acceptable operation of ! the diesel generators during each refueling outage test i
} verifies that the check valves have opened sufficiently to- :
perform their design function. The diesel generator oil and j O Jacket. cooling water temperatures for_each test are trended to ensure no significant changes occur from test to test. i
-i
. r 14-28a Rev. O i .
i ! ROJ-V-27 (cont.) The Architect Engineer (AE) performed an evaluation of these valves associated with INPO SOER 86-03 in 1987. This '
- evaluation considered valve type, operating conditions. and i environment, and past valve maintenance history. The AE
{ recommended periodic disassembly and inspection of the valve internals with at least one of the two valves being inspected
- every third refueling outage. The AE also recommended that
- the frequency of inspection be adjusted depending on inspection results.
l' ALTERNATE TESTING: Existing monthly and semi-annual diesel surveillance testing will be utilized to prove at. least partial check valve
- exercising. The existing refueling outage frequency diesel testing will be utilized to confirm that the valves will open r
- sufficiently to perform their design safety function. ;
1 1- Additionally, at least one of the two valves will be disassembled, manually exercised and visually inspected each ; 4 refueling outage on a rotating frequency in accordance with ; NRC GL 89-04, Position 2. This disassembly frequency should ; be adequate to detect any valve degradation in sufficient ' time to take corrective action and prevent the valve from 4 being unable to performing its safety function. Inspection results will be reviewed, and the disassembly frequency will be adjusted if warranted. . The valves are flanged into the system piping and are i l completely removed when inspected. The valve is visually ! inspected and manually full stroke exercised prior to being i reinstalled in the pipe line. The valve disassembly is i performed prior to the 24 hour diesel surveillance test, thus ' 1 the safety function of the valve is confirmed after l reassembly by monitoring diesel generator cooling during testing. This diesel testing confirms at least partial valve exercising after reinstallation in the system,
- t i
, Existing diesel generator surveillance testing in conjunction
- with the periodic disassembly and inspection should confirm the capability of the valves to perform their intended safety i function and should identify any degradation concerns prior
- to the valves becoming inoperable. i I
1 [o 14-28b Rev. O
. ~ . - - - . - .- . . . - - . _ - - . . - - - -.
l l REFUELING OUTAGE JUSTIFICATION g j ROJ-V-28 SYSTEM: Core Sppay < VALVE (S): IE21-F036A,B l 2E21-F036A,B,- CATEGORY: C CLASS: 2
- FUNCTION
- Core Spray Pump Minimum Flow Line containment Bound'ary l i.
1 TEST REQUIREMENT: Forward flow operability and reverse flow closure quarterly l per ISTC 4.5.1 1
- BASIS FOR JUSTIFICATION
- These valves are located in the core spray pump minimum flow i lines discharging to the suppression pool. Valves must open t to provide minimum flow protection for the core spray pumps j and close to provide containment boundary. Since there is no valve between the check valve and the suppression pool the line cannot be pressurized to ensure closure of the valve.
i This valve is sealed from the primary containment atmosphere $~ because the test line terminates below the water level of the torus and the leakage is not included in the Type C local leak rate testing. PARTIAL EXERCISING: Each valve is partial _ exercised open quarterly during core ! spray pump surveillance testing. T ,
- ALTERNATE TESTING: One valve for each unit will be disassembled, manually
- exercised and visually inspected each refueling outage per i
the guidance of GL 89-04. 'The valve internals will be " confirmed as structurally sound (no loose or corroded parts) ' i and the disk manually exercised to confirm ' full stroke , capability. ( L If the disassembled valve is not capable of being manually t full stroke exercised or there is binding or failure of valve j internals, the remaining valve will also be disassembled,
- inspected and manually full stroke exercised during the same 3 outage.
There are no test connections provided to facilitate atiy 4 measurements during pump testing. Therefore, partial flow t exercising after re-assembly will be confirmed by indirect means such as monitoring pipe wall temperature changes, using : acoustic monitoring equipment or observing flow induced ; vibration and noise. t i i' 14-29 Rev. O ; L -
f i j 4.0 GENERAL RELIEF REQUEST LOG i Relief Reauest Status
- 4 , .
RR-G-1 Submitted for NRC approval RR-G-2 Submitted for NRC approval RR-G-3 Submitted for NRC approval 4 i
?
4 i 1 1 4 f i, 1 i iO i l I l 1 l 1 i j 4 i i j
!O 1
15-1 Rev. 0
GENERAL RELIEF REQUEST RR-G-1 O SYSTEMS: s All in Scope of IST Program , VALVES: All in Scope of IST Program i l PUMPS: All in Scope of IST Program CLASS: 1, 2 and 3 j TEST REQUIREMENT: The version of .10 CFR 50. in effect on January 1, 1995, I paragraph 50.55a(b)(2) specifies the applicable Code to be ! the ASME XI, 1988 Addenda through 1989 Edition. The 1989 ! Edition of ASME XI references OM part 6 and 10 for inservice pump and valve testing respectfully. Paragraph 50.55a(b)(2) (viii) specifies the Code applicable inservice pump and valve testing to be the ASME/ ANSI part 6 and ASME/ ANSI part 10 of the OMa-1988 Addenda to the OM-1987 Edition BASIS FOR RELIEF: The ASME/ ANSI OM document was issued as a Code with the ASME OM Code 1990 Edition. This edition was amended with the OMa Code 1991 Addenda, the OMb Code 1992 Addenda, and the OMc Code 1994 Addenda. The ASME OM Code 1995 Edition was issued in early 1995. With each addenda and edition of the ASME OM Code, the ASME OM Code Committee has included updated ! inservice testing requirements based on improved knowledge, operating history and experience and changes in testing O. technology. Beginning with the ASME OM Code 1990 Edition, the format of the document was also changed to read like a Code instead of a standard as it was initially drafted. Therefore, application of later versions of the ASME OM Code, than specified in 10 CFR 50, should enhance the quality of the IST Program. ALTERNATE TESTING: The versions of the ASME OM Code utilized for the updated E.
- l. Hatch, Unit I and 2, Inservice Testing Program shall be as specified below.
Inservice Testing of Valves (all except safety / relief valves)
- ASME OM Code 1990 Edition l Inservice Testing of Pumps - ASME OM Code 1990 Edition i
Inservice Testing of Safety / Relief Valves - ASME OM Code 1995 Edition l j D 15-2 Rev. O
GENERAL RELIEF REQUEST I RR-G-2
- 5 -
[ SYSTEMS:' All in Scope of Unit 2 IST Program E VALVES: All in Scope of Unit 2 IST Program PUMPS: All in Scope of Unit 2 IST Peogram CLASS: 1, 2 and 3 l TEST REQUIREMENT: The version of 10 CFR 50 in effect on. January 1, 1995, i paragraph 50.55a(f)(4)(11), specifies that inservice testing , to verify operational readiness of pumps and valves required for safety, conducted during successive 120-month intervals l must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval. BASIS FOR RELIEF: The ISI Program submittal for the second 10-year interval for
- E. I. Hatch Unit 2 included Relief Request 6.1.2 which requested approval to allow start of the second 10-year i
interval on January 1,1986. This relief request was granted and subsequently both Hatch Units ISI and IST Programs were i updated to the same edition of the ASME XI Code applicable i at that time. The ISI and IST Program intervals for both units have been implemented concurrently since that date. i The commercial operation date for Hatch Unit I was December , 31, 1976. The commercial operation date for Hatch Unit 2 was September 5,1979. Therefore, the Hatch Unit 2 ISI/IST l Programs for the second 10-year interval were updated appreximately forty months early. Maintaining both units on the same interval schedule allows both IST programs to be developed utilizing the same edition of the Code, will make it easier for involved personnel to
- become familiar with the Code requirements, will ensure a greater degree of consistency for IST between the units, and
, will reduce the cost associated with surveillance procedure
- revisions for the program update and for maintenance of the
! program documents. ,' ALTERNATE TESTING: Update the E. I. Hatch Nuclear Plant Unit 2 IST Program concurrent with the Unit I third 10-year interval IST Program update due on December 31, 1995. The Unit 2 IST Program will
- be updated concurrent with the Unit 1 IST Program in
, accordance with the applicable regulations for the remainder
] of the plant life.
- O 15-3 Rev. O r
GENERAL RELIEF REQUEST l RR-G-3 ! SYSTEMS: All in S' cope of IST Program l VALVES: All in Scope of IST Program l PUMPS: All in Scope of IST Program
- CLASS
- 1, 2 and 3 i
TEST REQUIREMENT: The OM Code 1990 and 1995 Editions, paragraph ISTA 2.2.3(c), e require that the initial inservice test interval be 10 years i following commercial operation and each successive interval
- be 10 years following the previous interval.
! ISTA 2.2.3(c), as applied to Plant Hatch, would require the 3rd 10-year IST interval to start on January 1, 1996. Therefore, GPC assumes that this would mean compliance with i the 3rd 10-year IST Program testing requirements on January
- 1,1996, which would mean that all surveillance procedures must be in place to implement the surveillance testing requirements included in the IST Program update.
i BASIS FOR RELIEF: The surveillance testing requirements of the 3rd interval IST Program are not significantly different from those included
- in the existing 2nd interval IST Program. The ASME Section
! XI Code, 1980 Edition with the Winter 1981 Addenda was . utilized for the 2nd interval program, whereas the OM Code . 1990 and 1995 Editions have been utilized for development of the 3rd interval program (See RR-G-1).
- The 2nd interval program was revised in 1990 to address NRC
. GL 89-04 at which time the testing requirements of the OM Code were applied for pumps. Pump testing at Hatch presently utilizes the OM Code 1990 Edition. ,
- Power operated valve exercising and stroke timing j requirements of the 1990 OM Code require the use .of a reference stroke time as opposed to comparison to the previous stroke time required by the ASME XI Code. The actual testing is the same, acceptance limits and evaluation requirements are different between ASME XI and the OM Code.
,t i Safety and relief valve testing is more clearly defined in OM Code Appendix I, and is defined for each type and class of valve, but the required testing is not significantly different from that of the ASME XI Code which references ANSI /ASME PTC 25.3-1976.
- NRC NUREG-1482, paragraph 3.3.3, recommends that if a timely implementation of the updated IST Program requirements is not possible, that the licensee submit a schedule which O identifies the proposed schedule for implementation. This schedule should be submitted prior to the beginning of the new interval.
4 15-4 Rev. 0
s ] i RR-G-3 (cont.)'
! Revision of approximately one-hundred IST surveillance
]
- procedures within a short (3 month) time period would place i undue hardship on plant personnel who are also responsible
- for plant operation and support of a fall 1995 Unit 2 outage, and a spring Unit 1 1996 outage.
, NRC review and approval of IST Program updates has j historically required a significant amount of time. The J licensee is at the mercy of the regulators when coordinating
; and scheduling surveillance procedure revisions to implement
- an IST Program update while still maintaining and existing program's testing requirements.
1
! ALTERNATE TESTING: GPC will implement a transition from the existing IST Program l' to the 3rd Interval IST Program in accordance with the below described schedule.
! e 3rd Interval IST Program effective on January 1,1996. i Any program revisions required as a result of NRC review 4 and issue of SER will occur in accordance with schedule
- included in SER. Existing IST Program will also remain
- in effect until October 1, 1996.
- GPC administrative control procedures applicable to the ,
l 3rd Interval IST Program update to be revised and
- effective on January 1, 1996. ;
e GPC to begin revision of IST surveillance procedures on a system by system basis in January,1996. System by ! system surveillance procedure revisions to continue until ' September 30, 1996. ! l j e All surveillance procedures to be revised and effective j l and IST implementation to be in covpliance with 3rd Interval IST Program by September 30, 1996. Any j procedure revisions required as a result of NRC review I and issue of SER will occur in accordance with schedule ! included in SER. o 2nd Interval IST Program to be voided effective October g 1, 1996. i i O 15-5 Rev. O}}