ML17276B690

to Pump & Valve Inservice Test Program Plan.

ML17276B690
Person / Time
Site:	Columbia
Issue date:	08/28/1982
From:	Hoyle T, Martin J, Renberger D WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17276B662	List: ML17276B661 ML17276B663 ML17276B664 ML17276B665 ML17276B666 ML17276B667 ML17276B668 ML17276B669 ML17276B670 ML17276B671 ML17276B672 ML17276B673 ML17276B674 ML17276B675 ML17276B676 ML17276B677 ML17276B678 ML17276B679 ML17276B680 ML17276B682 ML17276B683 ML17276B684 ML17276B690
References
NUDOCS 8210260113
Download: ML17276B690 (309)

Text

WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO.2 PUMP AND ALVE INSERVICE TEST PR RAM PLAN 8210260113 821007 PDR ADQCK,05000397 APDR

~'+)Q~f PUMP AND VALVE INSERVICE TEST PROGRAM PLAN-REV.1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO.2 Prepared by Operations Support Engineering

>l>mls~Date Approved by Lead Engineer, P ant En ineering 8 Survei ance Da e Approved by Manager, WNP-2 ngineering Date Approved by Assistant Director, Generation Engineering

~~/8>Date Reviewed by Technical Manager, WNP-2 Date Approved by Plan Manager, WNP-2 Reviewed by anager, Oper ational ua1 i y Ass anc 0 te Reviewed by Author ized Nuclear Inservice Inspector Date RECORO OF PROGRAM PLAN REVISIONS No.8/2S/82 4/23/Sl OATE ORIGINAL REVISIONS CrlK'0 APP'0 TITLE Title Sheet Sin Ori.Records of Revision 1.0 Intro..0 Table of Contents 3.0 Pump Test Pro ram SHEET 2-1 3-1 3-2 3-3 3-4 3-5 3-6 3-7 3-7A 3-8 3-9 3-10 3-11 3-lla DATE/REV.N/A Deleted TITLE 3.Pump Test Pro ram Contd 4.0 WNP-2 Valve Inservice Test Pro ram SHEET 3-12 3-12a 3-12b 3-13 3-14 3-15 3-16 3-17 3-18 3-19 3-20 3-21 3-22 3-23 3-24 3-25 3-26a 3-26b 4-1 4-2 4-3 4-4 4-5 DATE/REV.1 was 3-24 was 3-25 TITLE 4.0 MgP-2 SHEET 4-6 DATE/REV.TITLE SHEET 4.0 MNP-2 4-26 DATE/REV.Valve I ns er v l ce 4-7 Test Pro ram 4-8 Valve Inser vice 4-27 Test Pro ram 4-27a Contd 4-9 4-10 4-11 4-12 4-13 4]4 4-15 4-16 4-17 4-19 4-20 4-21 4-22 4-23 4-23a 4-24 4-25 Contd 4-28 4-29 4-30 4-31 4-32 4-33 4-34 3g 4-36 4 37 4-38 4 39 4-40 4 4]4 42 4-43 TITLE SHEET OATE/REV.TITLE SHEET OATE/REV.4.0 MNP-2 4-46 1 4.0 MgP-2 4-66 Valve Inservice 4-47 Test Pro ram 4-48 Contd 4-49 4-50 4-51 4-52 4-53 4-54 4-55 4-56 4-57 4-58 4-59 4-60 4-61 4-62 4-63 4-64 4-65 Valve Inservice 4-67 Test Pro ram 4-68 Contd 4-69 4-70 4-71 4-72 4-73 4-74 4-75 4-76 4-77 TITLE SHEET DATE/R EY.TITLE SHEET DATE/REY.5.0 ualit Floor Drain Radioactive M 539 37 Assurance Pro ram 5-1 Containment Coolin EPurae M 543 27 6.0 Flow Di a rams 6-1 Control Service Air M 510*Containment Atmos.Control M 554 21 Containment Instru.Air M 556 17 Main Steam Lea'(a e Cont.M 557.11 Diesel Oil 8 Misc.S stems M 512 Reactor Core Iso.Coolina M 519 Low Pressure Core S ra M 520 High Pressure Core Spra M 520 Residual Heat Removal M 521 Standby Liq.Control M 522 Reactor Water Cleanu M 523 Standby Service Water M 524 Reactor Closed Coolino M 525 Fuel Pool Coo lin M 526 Control Rod Drive M 528 Main Steam M 529 Reactor Feedwater M 529 Reactor Recirc.Coo lin M 530 Equip.Drain Radioactive M 537 20 27 25 25 12 39 30 26 34 25 29 29 27 33 Steam and Li ui d Sam.M 607 sh.2 7*Burns E Roe Flow Oia ram Number vii Page l-l R

1.0 INTRODUCTION

This Pump and Valve Inservice Test Program Plan is applicable to the WPPSS Nuclear Project No.2, hereinafter referred to as WNP-2.A single unit Boiling Water Reactor (BWR), the power plant is located 11 miles north of Richland, Washington, on the Hanford Reservation.

The plant employs a General Electric (GE)supplied nuclear steam supply system designated as BWR/5.The reactor is contained within an over-under drywell/wetwell con-tainment vessel designated Mark II.The plant rated electrical output is 1,094 MWe.This program plan has been prepared as the controlling document governing Pump and Valve Inservice Testing at WNP-2.The requirements for Pump and Valve Inservice Testing are outlined in the ASME Boiler and Pressure Ves-sel Code,Section XI, entitled"Rules for Inservice Inspection of Nuclear Power Plant Components." The scope of this plan encompasses the testing of ASME Section III Nuclear Class 1, 2 and 3 pumps and valves, as defined by Sub-sections IWP and IWV of ASME Section XI.The WNP-2 FSAR commits to testing Class 1, 2 and 3 pumps and valves ac-cording to.the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1977 Edition with Addenda through Summer 1978.However, Revision 1 is written to comply with the requirements of the 1980 Code Edition with addenda through Winter, 1980.This is consistent with-federal requirements for component testing as stated in Title 10, Code of Federal Regulations, part 50 (10CFR50.55a(g)).

This Program Plan is comprised of two independent subprograms

-the Pump Inservice Test Program and the Valve Inservice Test Program.The develop-ment, implementation and administration of these two programs is detailed in subsequent sections (3.0 and 4.0).

Page 2-1 R 2.0 TABLE OF CONTENTS Record of Revisions 1.0 Introducti on 2.0 Table of Contents 3.0 Pump Inservice Test Program Description 3.1 Program Development Philosophy 3.2 Program Implementation 3.3 Program Administration 3.4 Pump Reference List 3.5 Pump Inservice Test Tables 3.6 Requests for Relief from Certain IWP Requirements 3.7 Proposed Pump Test Flow Paths 3.8 Records of Inservice Tests 4.0 Valve Inservice Test Program Description 4.1 Program Development Philosophy 4.2 Program Implementation 4.3 Program Administration 4.4 Valve Test Tables 4.5 Request for Relief from Certain IWV Requirements 4.6 Listing of Category A Valves 4.7 Records of Valve Inservice Tests 5.0 guality Assurance Program 6.0 Piping and Instrument Diagrams Page 3-1 Revision I 3.0 WNP-2 Pump Inservice Test Program 3.1 Pro ram Develo ent Philoso h Highly reliable safety related equipment is a vital consideration in the operation of a nuclear gener ating station.To help assure operability, the WNP-2 Pump Inservice Test Program (Section 3.5)has been developed.

The Program is designed to detect and evaluate significant hydraulic or mech-anical change in the operating parameters of vital pumps and to initiate cor-rective action when necessary.

The Program is based on the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP.To the maximum extent practical, the Program complies with the specifications of the approved Codes,(>)regulations (2)and guidelines.(3)

Consistent with the intent of Subsection IWP, the Supply System has incorpor-ated into this program certain requirements which exceed the specifications of the Code.In particular, the Diesel Fuel Oil Transfer Pumps are included for testing due to their potentially significant impact on plant safety.The Supply System recognizes that design differences among plants may render impractical certain Code requirements.

For example, it is not practical to require suction pressure measurement on vertical turbine ("deep well")type pumps.Where such impracticalities exist, they have been substantiated as exceptions as allowed by the Code.Alternate testing requirements have been proposed when warranted.

The Relief Requests which document the exceptions comprise Section 3.6.The Supply System is confident that the WNP-2 Pump Inservice Test Program compli es with the intent of the approved Codes,(>)regulations(2) and guidelines(3) and contributes to ensuring the safety of the general public.l.ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP, (1980 Edition with Addenda through Winter, 1980).2.10CFR 50:55 a(g).3.NRC Staff Guidelines for complying with certain provisions of lOCFR 50:55 a(g)"Inservice Inspection Requirements".

3.2 Pro ram Im lementation Page 3-2 Revision 1 Surveillance testing is performed to detect equipment malfunction or de-gradation and to initiate corrective action.Since the safety related pumps are normally in a standby mode, periodic testing of this equipment is especially important.

The WNP-2 Pump Inservice Test Program provides a schedule for testing safety related pumps and will be implemented as part of the normal surveillance routine.It is anticipated that reference data will be gathered during initial surveillance tests.In most cases, test parameters will be measured with normal plant instrumentation.

This approach will simplify the test pro-gram and will promote timely completion of surveillance testing.When permanently installed instrumentation is not available, portable instru-mentation wi 11 be used to record the required parameters.

During subsequent surveillance tests, flow rate will normally be selected as the independent test parameter and will be set to match the reference flow rate.Then other hydraulic and mechanical performance parameters will be measured and evaluated against the appropriate reference values.The results of such evaluations will determine whether or not corrective action is warranted.

Each pump in the Pump'est Program will be tested according to a detailed test procedure.

The procedure will include, as a minimum: a)Statement of Test Purpose.This section will identify test objec-tives, reference applicable Technical Specifications and note the operating modes for which the test is appropriate.

b)Prerequisites for Testing.System valve alignment, equipment for proper pump operation (cooling water, ventilation, etc.)and addi-tional instrumentation

('e.g., portable temperature or vibration monitors)will be noted.Identification numbers, range and cali-bration verification of additional instrumentation will be recorded.c)Test Instructions.

Directions will be sufficiently detailed to as-sure completeness and uniformity of testing.Instructions will include provisions for returning system to its normal standby con-figuration following testing.(For informational purposes, proposed flow paths are illustrated in Section 3.7.)d)Acceptance Criteria.The ranges within which test data will be con-sidered acceptable will be established by the Supply System and in-cluded in the test procedure.

In the event that the data fall outside the acceptable ranges, operator action will be governed by approved Administrative Procedures.

Finally it is recognized that the Pump Inservice Test Program sets forth minimum testing requirements.

Additional testing will be'erformed, as required, after pump maintenance or as determined necessary by the Plant Staff.

Page 3-3 Revision 1 3.3 Pro ram Administration The operations staff of WNP-2 is responsible for the administration and execution of the Pump Inservice Test Program.The Program will be offi-cially implemented upon the issuance of an Operating License and will govern pump testing for a 120 month period.Prior to that time, the Pro-gram will be reviewed and upgraded periodically to assure continued com-pliance with 10CFR 50:55a (g)(4).The Program may also be used as part of the pre-fuel loading surveillance testing program.Subsequent to Operating License, the program will be revised to reflect current ASME requirements consistent with lOCFR 50:55a (g)(4).

Page 3-4 Revision 1 3.4 Pum Reference List This list gives a brief description of each pump identified in the Pump Test Program.The pumps'SME Code Classifications are specified in the Program.HPCS-P-1 The High Pressure Core Spray pump provides emergency cooling spray to the reactor core.It is capable of injecting coolant at pressures equal to or above normal reactor operating pressures.

The pump can take suction from the Condensate Storage Tank or from the Suppression Pool.HPCS-P-2 This pump is dedicated to providing cooling water to the HPCS Emergency Diesel Generator, the standby power source for the High Pressure Core Spray System.HPCS-P-2 is located in the Pump House and takes suction from the spray pond.LPCS-P-I A high capacity, low head pump, the Low Pressure Core Spray pump provides cooling spray to the reactor core upon receipt of loss of coolant sig-nal.LPCS-P-1 takes suction from the suppression pool except when test-ing to the Reactor Pressure Vessel.RHR-P-2A, 2B, 2C The Residual Heat Removal pumps are high capacity, low head pumps which have multiple uses during normal and emergency plant conditions.

Briefly the system: a)In conjunction with other systems, restores and maintains reactor coolant inventory in the event of a LOCA b)Removes decay heat after shutdown c)Cools the suppression pool d)Condenses steam generated during Hot Standby e)Can provide cooling spray to upper and lower drywell and to the wetwell f)Can assist in fuel pool cooling g)Can provide a condensing spray to the reactor head h)P<<vides a flow path for Standby Service Mater in case containment flooding is required.Pumps take suction from the suppression pool in the standby operating mode.

Page 3-5 Revision 1 SLC-P-1A, 18 The Standby Liquid Control pumps are used to inject negative reactivity (sodium pentaborate) into the core independently of the control rod system.Suction is obtained from a storage tank containing the sodium pentaborate solution.SW-P-lA, 18 The Standby Service Water pumps supply cooling water to separate trains of safety related equipment.

The pumps take suction on their respective spray ponds but eventually discharge to the opposite pond.The two ponds are the ultimate heat sink during loss of offsite power conditions.

RCIC-P-1 The turbine driven Reactor Core Isolation Cooling pump supplies coolant to the core in the event of reactor vessel isolation.

It can take suc-tion from either the Condensate Storage Tank or from the suppression pool.DO-P-lA, 18, 2 These pumps transfer diesel generator fuel oil from the subterranean storage tanks to the diesel's Day Tanks.Pump 2 is dedicated to the HPCS Diesel.The discharge lines of Pump lA and 18 are cross tied, and each pump can supply fuel to either Diesel 1A or 18.FPC-P-lA, 18 The Fuel Pool Circulation (FPC)pumps take suction on the spent fuel pool and discharge through the FPC heat exchangers and, during normal opera-tion, through the Fuel Pool Filter/Demineralizers.

Page 3-6 R vision 0 3.5 Pum Inservice Test Tables The Test Table is the heart of the Pump-Test Proqram.It oresents a graphic display of the type and frequency of testing which the Supply System intends for its Class 1, 2 and 3 pumps.The Table incorporates the exceptions requested in Section 3.6{Relief Requests).

WNP-2 Pum Inservice Test Table IMP Parameter Pump Ident.ASNE Code Inlet Class Pressure, Pi Discharge Differential Pressure, Pressure, Po Fiowrate, Vibration, Q V Bearing Temperature Tb Pump Speed, R Lubrication Level/Relief Pressure Request(s)

HPCS-P-1 2 N/A NPCS-P-2 3 LPCS-P-1 2 H/A N/A N/A N/A NR NR 4,5 RHR-P-2A 2 H/A RHR-P-28 2 N/A RHR-P-2C 2 N/A NR SLC-P-lA 2 H/A N/A SLC-P-1B 2 N/A H/A N/A NR SW-P-lA 3 SM-P-16 3 N/A H/A N/A N/A N/A NR 4,5 RCI C-P-1 2 Q Q Q Q Q DO-P-lA 3 Q See Note A Q Q Q Q H/A DO-P-18 3 Q See Note A N/A NR DO-P-2 3 Q See Note A H/A NR FPC-P-IA 3 Q Q Q NR Q FPC-P-18 3 H/A NR Page-3-7A R~Le end A N/A=NR quarterly (92 day interval)test Annual test Not applicable.

See Relief Requests Not required IWP-4400 does not require pump speed measurement if pump's directly coupled to a constant speed motor driver.Note A: Storage Tank levels will be recorded and correlated to pressure in order to determine Pi and b,P.

Page 3-8 Revision 0 3.6 Pump Test Pro ram Relief Re uests Relief Requests identify Code requirements which are impractical for MNP-2 and provide technical justification for the requested exception.

Mhere appropriate, they also propose alternate testing to be performed in lieu of the Code requirements.

Page 3-9 Revision 1 RELIEF RE(UEST RP-1 (Deleted)

Page 3-10 R RELIEF RE(UEST RP-2~Pum (s)SLC-P-lA SLC-P-1B Section XI Code Requirement for which Relief is re uested Measure pump inlet pressure, Pi, and pump differential pressure,<P.(IMP-3100).Bases for Re uest 1.The SLC pumps are positive displacement pumps which, at a constant speed, deliver essentially the same capacity at any pressure within the capabil-ity of the driver and the strength of the pump.The SLC pumps are di-rectly coupled to constant speed drive motors.2.Surveillance requirements specify system alignments which assure adequate NPSH for the pumps.3.There is no provision for suction pressure instrumentation.

4.Acceptable discharge pressure and flowrate will suffice as proof of adequate suction pressure.Alternate Testin Proposed Pump dischar ge pressure and flowrate will be measured and recorded during testing.ualit/Safet Im act Measurement of these parameters assures acceptable level of quality and safety since inadequate suction pressure would be indicated by erratic discharge pressure indication, subnormal flow rates and increased pump vibration and noise.,These abnormal indications will be investigated and corrected as required by IWP-3200.

Page 3-11 Revision 1 RELIEF REQUEST RP-3 (Oeleted)

Page 3-12 R RELIEF RE(UEST RP-4~Pum (s)HPCS-P-l, HPCS-P-2, L PCS-P-1, RHR-P-2A, RHR-P-2B, RHR-P-2C, SW-P-1A, SW-P-IB, 00-P-1A 00-P-IB 00-P-2 FPC-P-1A FPC-P-1B Section XI Code Requirement for which Relief is Re uested Measure bearing temperature and vibration.(IWP-3100)

Bases for Re uest l.Except for FPC pumps, these pumps are vertical turbine (" deep well")type pumps and are immersed in the fluid being pumped.This precludes measur-ing pump bearing vibration except for inboard bearings.2.IWP-4300 only requires temperature measurement of"centrifugal pump bearings outside the main flow path".The outboard and intermediate bearings of all pumps are in the main flow path.Therefore, temper ature measurement of these bearings is not required.The inboard bearings of the RHR pumps, LPCS-P-I and HPCS-P-1, are cooled by the seal injection water which returns internally to the discharge flow.The inboard bearing on HPCS-P-2 (the head bearing), SW-P-lA and 1B, and 00-P-1 A, 1B, and 2 are cooled by the pumped fluid which returns to the discharge flow with no provision for temperature measurement.

3.Although the FPC bearings are accessible, bearing housing temperature is not necessarily an accurate predictor of bearing condition.

Hence, temperature measurement is an unnecessary requirement with unreliable results.Alternate Testin Pro osed l.Except for FPC pumps, axial and radial vibration velocity measurement will be taken at the outboard bearing of the pump's motor.Radial vibration velocity measurements will be taken as close as practical to the inboard pump bearing.2.Vibration velocity measurements will be taken on the inboard and outboard bearings of the FPC pumps.3 Alert level will be 0.157~Vb 4 0.314 in/sec.Required action level will be Vb~0.314 in/sec.The General Machinery Vibration Severity Chart is provided for information purposes.

Page 3-12A Revision 0 gualit/Safet Impact Measurement of vibration velocity provides more concise and consistent information with respect to pump and bearing condition.

The usage of vibration velocity measurements can provide information as to a change in the balance of rotating parts, misalignment of bearings, worn bearings, changes in internal hydraulic forces and general pump integrity prior to the condition degrading to the point where the component is jeopardized.

Hearing temperature does not always predict such problems.An increase in bearing temperature may not occur until the bearing has deteriora ed to a point where additional pump damage may occur.Hearing temperatures are also affected by the temperatures of the medium being pumped, which could yield misleading results.Vibration readings are not affected by the temperature of the medium being pumped, thus the readings are more consistent.

The oroposed alternate testing riill result in the maximum meaningful data regarding pump bearing condition.

Since vibration velocity analysis is more predictive in nature than bearing temperature measurement,'he alternate testing serves to increase levels of safety and quality.

~~I 1~

Page 3-13 R RELIEF RE/VEST RP-5 Pump(s)HPCS-P-2 SW-P-1A SW-P-IB Section XI Code Requirement for which Relief is Re uested Measure pump inlet pressure, Pi, and differential pressure, b,P.(IWP-3100)Bases for Re uest (I)SW-P-lA, 18 and HPCS-P-2 are vertical turbine type pumps which are im-mersed in their water source.They have no suction line which can be instrumented.

(2)Technical Specifications will state minimum allowable spray pond level to assure adequate NPSH and cooling water supplies.(3)Difference between allowable maximum pond level and minimum level is only six (6)inches of water or 0.2 psi.This small difference will not be significant to the Test Program and suction pressure will be considered essentially constant.(4)Acceptable flowrate and discharge pressure will suffice as proof of adequate suction pressure.Alternate Testin Pro osed Spray pond level and pump discharge pressure will be recorded during the test-ing of these pumps.ualit/Safet Im act The effect of granting this request will be to introduce an error of 0.5 ft./500 ft.=0.1X at rated discharge flow for SW-P-1A and 1B and an error of 0.5 ft/135 ft.=0.37K for HPCS-P-2.These small errors will not signifi-cantly impact the quality of test results nor jeopardize the safety of the pub 1 i c.

Page 3-14 3.7 Pro osed Pum Test Flow Paths These flow paths are proposed for use during pump testing and may be used during the valve test program.The valve alignment shown on these draw-ings reflect valve position during testing.Valve position during opera-tions may be different.

Surveillance procedures will define actual flow paths.

V-1 I l I I J r 20 0 SuPPI;"-~.

<O~POOL I l I REA(:TOI'I VEz~SI.I l I l:l---I V-'I-~~C'..7)=10 V-2 FE-2 S'I'-1 LPCS l HPCS I S7'-1 FE-7 24 24 REFLHI iNC'l:5: B 8 R ORIG.LPCS-P-1 HPCS-P-1 HIGH PRESSURE CGfif!it'(iAY LOFTI PRESSURI=-

CO'0" HAPP'7 PRV A 18 V-47A I Fi"=-14A 18 I I I REACTOR I VES~"L I I RHR-HX-1A='.RO-3A i--tocl-------.V-2'IA~~V-172A 24 V-4A SUPPRESS10i"1 POO!18 V-6A REFFHCNCF~:

BRRD!G.H521 jj ST 2n-REMI OIMf HFA7 RFt",OVAL O V-110A V-31A liO-SA RHR-P-2A PRV B I I RELIC>OR I I I VESSI I I I I I I I sQ 78 V-3I3 Rl IR-I-lX-1 P>SUPPVif-.'SS i ON I'OOI V-48 24 REI ERFNCI.S: B It.'R DIIG.N527 18 V-68 RES ff1iltiI, IIF/;1 IKi~iOV'iL ST-2" g AO-SB V-3 I I3 V-I I Ou RHR-P-28 I REAC TOA I I YES SEI I I[>cl'RO-4C 7 V-21~j V-17'UPPAE

~57ON POOl REFERENT:ES B R A 01'fIO.N527 18 Sr-ZC AE."ill>)JA17 1%8 l f'i'-"(>Jgf i ,.-T f,.T..T, i11T, I V-110C V-31C AO-5C RHR-P-2C

REACr0R VeS.".l.:L

---0 1 V-17 V-16 1 1/2 1/2 V-3A V-33'LC-P-1 A 1 1/2 3" 4 V-2A 1/2 S V-3B V-33B~il C-P-18

REFERENCES:

BR ROMG.H522-4-M V-18 STANDBY L1AUl D CONTflOL

T T.V-28-L V-IU SM-P-1f3 RHk-V-6CG AHA-f f'h-10 k 18 AHR-=V-1~8 20-liOU5L L'PRAY f'Oii'D f(12 PUMI" HOV:i(INf L 1n" 18 20 FE-10 18:J p'-1GSB KA hh SPRAY PCND h SERV f Cf2 hfA TER

REFERENCES:

8 8 R E)tie.H524 a (D (((C EQ (D (I(O 4)PO (O PRVF

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=.l>J V-2A T V 1A 20 T I 16 RHR-V-6'1 18 RHR-I IX-1A flhi'=V-1~P.HPCS-V-N'1 JV>.,'.,.I,,'.'-, C f.!PC.'i-l1 cj'(P 1 A 5 18 20 8 DfESEI GF'6!EQUIP"-[i(-a-(8 PUYiP I!0US=li PUIIP IIOU&f Vk!.I)i)'XA'L IV I'V I~I ski I lI I I D--M Cl---'CY 36 A-'-I:-BA V-12k rV-170k PUl~iP IIOUSE E)~-~~~~~~.'iPBikY-PONl)Fl REFf Vl'H(I)~Bg RDl/8 N524 x INDIVIDUAL fcl.Oll IM)IACATORS SERVICF h'Alf'I's'G O GJ I M CST-----t><-==-W V-hO V-23 V-2Z l:0-b 6 6 REACTOR VESSf=L V-101 ST-1 RCJC-P-1 V-16 SUPPRESS10N POOL 8" CST Y-10 V-11 8 REF l=Rl NCfb: BRRDVG H519 REAC lOR Oft~:-1601 h1 lON COOLINf.'RVH e

V-43 V-12 1 1/2 Dw=I-1 V-11 V-10 00-P-2 DO-TK-0 II 00-'l l-2 V-7018 DO-TK-3O I/1/2 V-40S V-40 V-28 V-1O UO-P-11'/I/2 DO-TK-1B V-701k DO-TK-3A 1/1/2~--D&V-40k V-4A V-2fi V-1A 11'2 00-P-1k REFERCNCLS:

B 8 R De/G M512 D1ESEL FUCl OIL 00-TK-1A PRVJ Q lD (EO O I 8~8 V-144A V-146A V=*1"6A FPC-TI-1A FPC-IX-18 4 FE-16;=.I.V&(P I T 10 (10 V-130 4-i i-~-T>~-!~i-T-c-:->~" v->stw sr-i;, FPC-P-1A 6-i~-i i-j'~--i)a-!!-T.-I I I V-1 12A V-I 1 r'r'r'c FPC-HX--1 n V--142 V-1~F7 10 V-118A V-1118 Sf-18 V-1'l2s'r-11ss FPC-I~-1U EPC-HX-18 V-184 V-124 V-I 72 V-1188 V-173 o PRV I I 11 Page 3-25 Revision I 3.8 Records of Inservice Tests Records of Pump Inservice Test results will be maintained in accordance with Article I'I!P-6000-af the Code.A file will be established for each pump and wi,ll include: 1)Pump identification by eauipment piece number, manufacturer, and serial number.2)Inservice test plans.This may be by reference to the surveillance test procedure by which the pump is tested.3)Summaries of corrective action.The Pump Inservice Test Program, associated surveillance test procedures and results will be kept at the INP-2 plant site.For informational

'purposes, a sample pump test data sheet is provided.

,L II 0 Page 3-26a SAMPLE PUMP TEST DATA SHEET Pump IO Parameters Date Action~Alert*Ran e Ranqe Measured Init.Value Pump Suction Press (PI)Before Pum Start Calib.Due Date N/A N/A Pslg Pump Suction Press Durin Test (Pr.)Calib.Oue Date N/A N/A Pslg Pump Discharge Press (PI)Calib.Due Date Calculated Pump b.P line 3-line 4 N/A psiD N/A psiO Pslg pslo System Flow (FI)m Calib.Oue Date gpm gpm gpm Pump Bearing Vibration See Reverse Side Lubrication Level or Pressure Satisfactory Unsatisfactory COMMENTS: ,*If deviations fall within the ALERT RANGE, the test frequency is increased to once each 45 days.If deviations fall within the ACTION RANGE, the pump shall be declared inoperable and the deviation investigated and/or corrected.

Where flow is calculated rather than measured, record identification numbers and calibration due date of'nstruments used to collect data (e.g., level indicator, stopwatch).

PUMP VIBRATION DATA Page 3-266 Revision 0TEST E Ul Q PMENT USED Cal ibration Due Date OPERATING Volts Amps Rpm Temp;Outbd.Bear.o CONDITIONS Sys.Temp.Temp.Outbd.BBar.EQUIPMENT SKETCH~I~I I~I Ias~;II~'I I I~I I, Legend: Pickup Point~,~~!I I I~~'I I~'I'I's~e s s~~,,i~I I~~I 0 I,~s'-I'~s s~~I!!I!I I s~~~~!ei~'S s I~s'~~I'I I~s.s~'I I Ss I~~I I~Performed by Bearing Coupling Date I~I s~~~I'~I'Ims I I I m s~~~I~I s sss~~I I ai~I~~I s~I+I I I I s 1 I~s s'~~s I'..I I'I I'~~.I~I I~s<<I,"gi~I I I I~~I I I~i I I I~N I!!as~~.I'iai I~.~~I I I~I~~..'I~~>I su!I I s~I'I I\\~,~~'*I I~I I~~I Verified by Date!~I I e I'<<~!~I I~I I I S I I, I I~~I I, I SSS I I!.I',~I I~I~'m,~'s I I s I~I~I~s~~':~~S~I~<<Ss I SC,'I i S.'S I>>I I~~~I~, i~~Alert j ange: Vel.).157 in/sec Action Ran e: Vel.>.314 in/sec I'1,,1 si s~~I I~~~I*I I~I I~~!~'1.I'~~!,~~~I, I i I~s s~~I~~I~s~I'.I~I~.I s I.'s.s!-~I I~~!~~~s I.I I I!I I I~!~~I I I I I~I I I I~~I s!~.!I I~i~s~~~I I I I'I~I I I I I I!I I e-'la, I.'I'm mI II'I I~FILTER OUT II I~~s'~I I~i'~DISPL.I V EL ITY I'Olhm!PCIS H M.l LS: CFM>INDE C~+IA I I g I V I siss'e-A H I V j A~V V.A V

Paqe 4-1'WNP-2 Valve Inservice'est

'Prog.am Pro ram Devel o ment Phil osooh Washington Public Power Supply System Nuclear Project Unit 2 (WNP-2)is a Soiling Water Reactor being constructed in compliance with the ASME Boiler and Pressure Vessel Code.The Code r quires periodic testing of certain safety related valves in order to verify their operability and physical integrity.

The WNP-2 Valve Inservice Test Program satisfies these requirements and conforms to FSAR commitments

or valve testing.The Program will detect potentially adverse changes in the mechanical condition of valves within the scope of-Section XI, Subsection IWV of the Code.The scope includes all valves"which are required to perform a specific function in shutting down a reactor to the cold shutdown condi-tion or in mitigating, the consequences of an accident".

Mary valves users in normal shutdown operations are not necessarily"required" nor would they necessarily be available for that purpose.Hence, the scope of, IWV is restricted to valves required to shutdown the r ac.or in emergency situations and to mitigate accident consequences

.To generat the WNP-2 Program, all ASME Class 1, 2 and 3 valves were analyzed to determine the required+ype and frequency of t sting for each valve.The valves to be tested under Section XI, Subsection IllV commi+-ments are listed, by system, in the Valve Test Tables (Section 4.4).The Tables schedule only valve exercise tests.Leak rate testing mandated by Section XI will be incorporated into a WNP-2 unified lea!<rate testing program which.vi ll satisfy Section XI and other requirements.

The HNP-2 FSAR commits to meeting the.equi.ements of both 10 CFR 50, Appendix J(1), and of Section XI.Each of these documents addresses particular but slightly different concerns with respect to valve leak-age.Each contains guidance for valve leak rate testing.Appendix J is primarily concerned with lea<age out of containment subsequent to a Loss-of-Coolant Accident (LOCA).It requires leak rate testing of con-tainment isolation valves at the maximum differential pressure (dP)expected during an accident.Section XI requires leak r ate testing o: all valves for which seat leakage"is limited to a specific maximum amount" and that testing be performed at the valves'perating EP unless II Title 10, Code of Federal Regulations, Part 50, Appendix J."Primary Reac+or Containment Leakage Testing for!!ater-Cooled Power Reactors."

Page 4-2 a lowered.P can be shown to give conservative results.OperatingaP may be many times the maximum post-LOCA b.P.Finally, plant Technical Specifications also address leak'rate testing and impose specific testing requirements (e.g.excess flow check valve operability demonstration; testLP for drywell-wetwell downcomer vacuum breakers).

The testing requirements imposed by the various sources are not identical nor are they mutually exclusive.

It is anticipated that Appendix J test-ing may satisfy Section XI leak rate testing in some instances.

How-ever, some valves may require both Appendix J and Section XI testing.Section 4.6 identifies valves which, under the scope of Section XI, Sub-section IWV, are subject to leak rate testing beyond Appendix J require-ments.Relief valves are not required to be leak rate tested (IWV-3512) subsequent to bench testing and are not include'd in Section 4.6.Normally closed, manually operated containment isolation valves are excluded since these valves are subject only to Appendix J testing.For implementation purposes, the test frequencies mandated in Appendix J, S'ection XI and the Technical Specifications are the same.Leak rate testing will, in general, be performed during outages although some valves may be amenable to leak testing during power operations.

Similar testing frequencies and overlapping requirements necessitates a, unified leak rate testing program which will maximize compliance with the various commitments, provide consistancy in test methodology and reduce duplication of effort.The Supply System is actively developing a uni-fied program which will be submitted for review at a later date.Proce-dures to implement this program are being prepared.Verification that position indication agrees with actual valve position will be accomplished biannually as part of the valve exercise tests.Although the tables in Section 4.4 specifically designate position indi-cation verification only for certain manually operated valves and check valves, the position indication for power operated valves will be checked biannually during an exercise test.The Code recognized that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements.

The relief requests for the Valve Inservice Test Program (Section 4.5)identify testing impracticalities, provide technical basis for the request and propose alternate testing where warranted;-

Most of the requests ask only for the postponement of test-ing, not cancellation.

The Supply System is confident that the WNP-2 Valve Inservice Test Prp-gram complies qigh the intent of all applicable codes, regulations,(>>

and guidelines'l3) and that it will make a positive contribution to the safe operation of the plant.10CFR 50:55 a(g)(2)NRC Staff guidelines for excluding exercising (cycling)tests of certain valves during Plant operations.

Page 4-3 R 4.2 Pro ram Im lementation The Valve Test Program will be executed as part of the normal plant sur-veillance routine.Two types of tests will be conducted as part of the Valve Test Program: 1)Valve Operability Tests 2)Valve Leak Rate Tests The Operability Tests will verify 1)the valve responds to control commands, 2)the valve stroke time is within specific limits and, 3)remote position indication accurately reflects the observed valve position.Base line data for stroke times will be obtained from ini-tiall Valve Operability Tests.The initial Valve Operability Tests will meet the requirements for preservice testing (IWV-3100).

Where applicable, acceptance criteria for initial stroke times will be within the limits specified in Table 6.2-16 of the WNP-2 FSAR.Otherwise, the Supply System will specify acceptable times.When these times are established, they will be inserted in the Valve Test Tables under the Stroke Time column.Remote valve position indication will be verified ever y two years.Manually operated valves with remote position indication have been included in this program.Fail safe valves will be tested by observing the valve operation upon loss of electrical, pneumatic or hydraulic actuating power.In most cases, loss of electrical powe~causes loss of actuating fluid and can be accomplished using normal control circuits.Valve leak rate baseline data will be obtained in accordanc'e with IWV-3100 and accepted industry practice.Leak rate acceptance criteria will be specified by the Owner.4.3 Pro ram Administration The Valve Inservice Test Program will be administered in a manner analogous to the Pump Inservice Test Program.

Page 4-4 Revision 0 4.4 Valve Test Tables The Valve Test Tables are th essence of the Supply System's Program to meet ASt1E Section XI, Subsection IHV requirements.

The Tables reflect the positions taken in support of tie relief requests.To aid the reader in the interpretation of the Tables, brief explanations of the Table headings and abbreviations are provided.

I Cl Page 4-5 Revision 0 (1)Valve Number Each piece of equipment in tlie plant has a unique"tag" number which identifies the system to which the equipment belongs, the type of equipment (flow control valv FCV, relief valve=RV, rupture disc=RD, etc.), and a unique serial number.(2)Class ASME Code Class oer Section III of the ASME Boiler and Pressure Vessel Code.These are roughly equivalent to the safety classes defined in Chapter 3 of the FSAR.(3)Coordinates The specific coordinates of each valve are supplied to;acilitate location of'he valves on the flow diagram provided.(4)Valve Category Categories are defined by ASME Section XI, subsection INV.Each valve has specific testing requirements which are determined by the category to which i belongs.(5)Siz Nominal pipe diameter to which the valve connects is given in inches.(5)~Valve T e The following abbreviations are used to describe valve type: BF=Butterfly valve CK=Ch.ck valve DIA=Diaphragm valve GB=Globe valve GT=Gate Valve RD=Rupture disc.RV=Relief Valve S/R=Safety/Relief Valve SV=Solenoid Valve

Page'-6 Revision 0 The following abbreviations are used+o describe actuator types.Valves mav be actuated in more than one way.AO=Air ooerated HO=Hydraulic operated i~1AN=Manually operated MO=Motor operated SA=Self actuated (actuated by a change in system parameters such as flow or pressure, e.g., chec'<and relief valves).SOL=Solenoid operated-(8)Normal Position Valves may be either normally open (0)or normally closed (C).Throttle valves are not included in+he scooe of this program since they are either passive or regulating type valves.Both types of valves are exempt from INV testing (IIJV-2100).

19)This column defines the operatino modes as defined by the Technical Soecifications, during which, the valve may be safely tested.See below for the definition o,"all,""CSD" and"Refuel."~eceend t5eanine All Testing is approved during all operating modes and wi 11 be conducted on a quarterly basis, as permitted by olant status.

Page 4-7 Revision 0 CSD Cold shutdown.Guidance>or Inservice 1I valve testing at cold shutdown is: Valve testing should commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after cold shutdown is achieved and continue until complete or until plant is ready to return to power.Comp 1 et i on n.all valve testing is not a prerequisi.e to return to power.Any testing not completed at one cold shutdown should be performed durinq the subsequent cold shutdowns to meet the Code specified testing requency.Refuel Test will be conducted during refueling outages but at least every two years.Cer-tain work which is nominall.y scheduled for a refueling outage may be performed at other times when plant conditions permit.The two year minimum frequency will be maintained.

IMV-3620 Test frequency will be according to vendor specifications.

(10)Test Testing requirements identified for the valve are identified here.S/E Stroke exercise;valve timing not, relevant.

Page 4-8 R S/T Stroke time;valve must meet stroke timing requirements specified in the FSAR or else-where.Bench Test Relief valves will be tested in accordance with IWV-3500 requirements.

IWV-3620 Rupture disc will be tested in accordance with Section XI, Subsection IWV, paragraph 3620.Pos Ind (ll)Stroke Time Position Indication verification only.Used only for manual valves.Power oper-ated val ves'osi ti on indi cati on wi 1 1 be verified biannually during exercise test.4 r Reference stroke time will be listed where ()appears.Values wi 1 1 be determined during initial surveillance testing and will comply with limiting values of full stroke time specified in the FSAR, Techni-cal Specifications or other commitment documents (12)Notes Generally self explanatory, e.g., NO=Normally open FO=Fails open NC=Normally closed FC=.Fails closed (13)Re uests for Relief Cross references documentation which re-quests waiver of certain code require-ments.A valve may have more than one associated relief request.

Uil System Name CONTROL AND SERVICE AIR Dug.No.M510 Page 1 of 1 Valve fiumber a ve Category Size Class Coordinates

~~0 Inches Valve Actuator T e T e Normal Test Position Durin Stro1<e Test Time Notes equests For Relief CAS-V-453 2 KB X 1 SV SOL C ALL S/E N/A I CAS-CVX-82e 2 X X CK SA ALL, S/E N/A System ttame DIESEL OIL Nl0 HISC.DO Dwg.No.I4 512 Paqe 1 of 1 Valve ttumber a ve~Cate or Size Class Coordinates A 8 C 0 Inches Val ve Actuator ttorma1 Test Stroke T e T e Position Durin Test Time equests For Notes Relief 00-V-IA 3 03 X X 1 1/2 CK SA C ALL S/E tt/A 00-V-18 r DO-V>>IO 03 HS X X X X 1 1/2 1 I/2 CK CK ALL S/E N/A ALL S/E N/A DO-V-40A 3 I 1/2 SV SOL ALL S/E N/A DO-V-408 3 E3 1 1/2 SV SOL ALL S/E N/A DO-V-43 tl6 SV SOL ALL S/E N/A R7'CD CD Dr (ID~CD C CD

Page 1 of 2 System Name REACTOR CORE ISOLATION COOLING SYSTEM RCIC Dwg.No.M 519 eques s For Relief a ve Category Size Class Coordinates

~I C D Inches Valve Actuator T e T e Normal Test Position Burin Stroke Test Time Valve Number Notes ALL S/E N/A Rapid Acting RCIC-V-1 2 El 1 X 3 GT MO 0 ALL>>S/T ()ALL S/T (NA)F6 RCIC-V-8 GT MO GT RCI C-V-10 2 B14 HO RCIC-V-11 2 813 ALL S/E N/A X X CK SA RCIC-V-13 1 ALL S/T ()ALL S/T ()ALL S/T ()GT HO RCIC-V-19 2 E7 GB HO RCI C-V-198 2 J6 1/2 GT RC I C-V-21 2 EB ALL S/E N/A X X CK SA RCIC-V-22 2 JB ALL S/T ()ALL S/T N/A ALL S/E N/A HO RCIC-V-28 2 08 1 1/2 CK X X SA RCI C-V-30 2 C7 CK X X RCIC-V-31 2 ALL S/T ()C7 GT HO RCI C-V-40 2 08 10 X X CK SA ALL S/E N/A ALL*S/T ()ALL S/T ()RCI C-V-45 2 Fl1 HO GB RCI C-V-46 2 F1 1 GB MO C RCIC-V-59 2 J9 ALL S/T ()GT HO O*Valves marked with an ASTERISK (*)close automatically if Reactor Vessel Pressure is less than 47 psig.Therefore, if Cold Shutdown conditions extend beyond a 3 month period, IWV testing frequency may not be met.However, valves will be tested prior to resuming power operations (IWV-3416)

System Name REACTOR CORE ISOLATION COOLING RCIC Owg.No.M 519 Page 2 of 2-Valve Number alve Cat~ear Si ze Class Coordinates

~I~Inches Valve Actuator Normal Test T e T e Position Durin Stroke Test Time Requests For Notes Relief'CIC-V-63 1 N3 X 10 GT MO" 0 ALL*S/T ()RC I C-V-64 1 G6 10 HO ALL*S/T ()RCIC-V-65 1 H6 X X CK AO/SA C ALL S/E N/A RCIC-V-66 I RC I C-V-68 2 RCIC-V-69 2 J4 E7 07 X X 10 1-1/2 CK GT GT AO/SA HO MO CSD S/E N/A ALL S/T ()ALL S/T ()RCI C-V-76 I N3 GB HO ALL*S/T ()RCIC-V-086 2 A13 X X CK SA ALL S RCIC-V-110 2 RCIC-V-113 2 E7 E6 GT GT HO HO ALL*S/T ()ALL*S/T ()RCIC-RO-I 2 D11 10 RUPTURE SA OISC C I WV-3620 I WV-3620 N/A RCIC-RO-2 2 C12 X 10 RUPTURE SA OISC C IWV-3620 IWV-3620 N/A RCIC-RV-17 2 RCIC-RV-18 2 C13 09 1xl 3/4 x I RV RV SA C REFUEL BEN(N N/A TEST C REFUEL BENCII N/A TEST*See note on RCIC System page I of 2.

System Name LOW PRESSURE CORE SPRAY SYSTEH LPCS Dug.No.M520 Pally.1 of Va ve Valve Cat~eo~r Size Number Class Coordinates

)(IM: 0 Inches Valve Actuator T e T e Normal Test Position Durin Stroke Test Time Requests For Notes Relief LPCS-V-1 2 Dll X 24 GT HO 0 ALL S/T ()LPCS-V-3 2 B13 X X 16 CK SA ALL S/E N/A LPCS-V-5 1 G11 12 GT MO ALL 5/T ()LPCS-V-6 1 LPCS-'V-12 2 LPCS-V-33 2 ll9 F14 C12 X X X X 12 1 1/2 CK GB AO HO SA CSD S/E N/A ALL 5/T ()ALL S/E N/A LPCS-V-51 1 H9 12 GT 0 REFUEL POS IND N/A LPCS-FCV-11 2 B13 GB ALL S/T ()LPCS-RV-18 2 LPCS-RV-31 2 F12 C12 1 1/2 x 2 RV RV C REFUEL BENCH N/A TEST C REFUEL BENCH N/A TEST System Name HIGH PRESSURE CORE SPRAY SYSTEH HPCS Owg.No.H520 Paqe Valve Number a ve Cat~e~or Size Class Coor dinates)(8 0 0 Inches Valve Actuator Normal Test Stroke T e T e Position Burin Test Time Requests For Notes RelieF HPCS-V-1 2 C6 X 14 GT HO 0 ALL 5/T ()HPCS-V-2 2 HPCS-V-4 1 HPCS-V-5 1 C6 G7 X X X X 20 12 12 CK GT CK HO AO ALL S/E N/A ALL S/T ()CSO S/E N/A HPCS-V-7 2 CS X X 1 1/2 SA ALL 5/E N/A HPCS-V-10 2 HPCS-V-11 2 HPCS-V-12 2 E3 E3 85 10 10 GB GB GT ti0 ALL S/T ()ALL 5/T ()ALL 5/T ()HPCS-V-15 2 07 18 GT HO ALL S/T ()HPCS-V-16 2 HPCS-V-23 2 HPCS-V-24 2 E6 85 X X X X 24 12 16 CK GB CK ALL 5/F.H/A ALL S/T ()ALL 5/E N/A HPCS-V-28 3 H524 Rev.19 J5 SA ALL S/E N/A HPCS-V-51 1 HB 12 GT flan 0 REFUEL POS INN N/A HPCS-RV-14 2 HPCS-RV-35 2 C6 C4 1X1 1x2 RV RV SA C REFUEL BENCH N/A TEST C REFUEL BENCH N/A TEST System Name RESIDUAL IIEAT REHOVAL SYSTEH RHR Dwg.No.H521 Page f ef Valve Number a ve Cateqo~r Size Class Coordinates

~0 Inches Valve Actuator Normal Test Stroke T e T e Posi t ion Dur inn Test Time Notes Requests For RelieF RIII-V-3A 2 J13 X 18 GT HO 0 ALL S/T ()RIII-V-38 2 RNR-V-4A 2 RIIR-V-48 2 J4 E 11 06 18 24 24 GT GT GT HO HO HO ALL S/T ()ALL S/T ()ALL S/T ()RIIR-V-4C 2 011 24 GT HO ALL S/T ()RIIR-V-6A 2 RIII-V-68 2 RIB-V-8 C12 C6 F11 18 18 20 GT GT GT HO HO HO ALL S/T ()ALL S/T ()CSD S/T ()RIIR-V-9 F10 GT HO CSD S/T ()RIIR-V-11A 2 RIIR-V-118 2 RHR-V-16A 2 F12 E7 16 GT GT GT HO HO HO ALL S/T (ALL S/T ()ALL S/T ()RIS-V-168 2 F6 16 GT HO ALL S/T ()RNR-V-17A 2 RIIR-V-178 2 II10 F6 16 16 GT GT HO HO ALL S/T ()ALL S/T ()

System Name RESIDUAL IIEAT REMOVAL SYSTEM RIIR Ikvg.No.H521 Page 2 of 6 Valve Number a ve Cate or Size Class Coordinates A 8 D Inches Valve Actuator Normal Test Stroke T e T e Position Burin Test Time equests For Notes Relief RIIR-V-21 2 E11 X 18 GB MO C ALL S/T ()RIIR-V-23 1 H7 GB HO CSD S/T ()RIIR-V-24A 2 RHR-V-248 2 RIIR-V-27A 2 E12 E6 E11 18 18 GB GT HO MO HO ALL S/T ()ALL S/T ()ALL S/T ()RIIR-V-278 2 E7 GT HO ALL S/T ()RNR-V-31A 2 RIIR-V-318 2 RIIR-V-31C 2 813 X X X X X X 18 18 18 CK CK CK SA SA ALL S/E N/A ALL S/E N/A ALL S/E N/A RIIR-V-40 2 G4~4 GB MO ALL S/T.()RIIR-V-41A 1 RIB-V-418 1 RIIR-V-41C 1 G10 GB G10 X X X X X X 14 14 14 CK CK CK AO AO AO CSD S/E N/A CSD S/E N/A CSO S/E N/A RIIR-V-42A 1 G11 GT MO ALL S/T ()

System Name RESIDUAL MEAT REMOVAL SYSTEM RIIR Owg.No.M521 Page 3 of 6 Valve Number a ve Cat~ear Size Class Coordinates

~WC D Inches Valve Actuator Normal Test Stroke T e T e Position Burin Test Time Notes equests Fnr Rel lef RIIR-Y-428 1 G7 X 14 GT HO C ALL S/T ()RNR-V-42C 1 G11 14 GT HO ALL S/T ()RIIR-V-46A 2 012 X X CK ALL S/E N/A RNR-V-468 2 RIIR-Y-46C 2 RIIR-V-47A 2 E6 Dll J14 X X X X 18 CK GT SA HO ALL S/E N/A ALL S/E N/A ALL S/T ()RIIR-V-478 2 J3 18 GT HO ALL S/T ()RIIR-V-48A 2 RIIR-V-488 2 RIIR-V-49 2 J13 JS X, 18 18 GB GB GT MO MO ALL 5/T ()ALL S/T" ()S/T ()RIIR-Y-50A 1 G10 X X 12 CK AO CSO S/E N/A RIIR-V-508 1 RIIR-V-53A 1 RIIR-V-538 1 GB G11 G7 X X 12 12 12 CK GB AO MO HO CSO S/E N/A CSO S/T ()CSO S/T()

System Name RESIDUAL HEAT REMOVAL SYSTEM RHR Dwg.No.M521 Pa e 4 of 6 9-Valve Number a ve Cate<~or Size Class Coordinates

~~D Inches Valve Actuator Normal Test Stroke T e T e Position Durin Test Time Notes equests For Relief RHR-V-60A 2 H12 X 3/4 SV SOL C ALL S/E N/A RHR-V-608 2 JS 3/4 SV SOL ALL S/E N/A RHR-V-75A 2 H12 RHR-V-68A 3 M524 REV.19 H12 RHR-V-68B 3 M524 REV 19 Hll 16 16 3/4 GT GT SV MO MO SOL ALL S/T ()ALL S/T ()ALL S/E N/A RHR-V-75B 2 d5 3/4 SV SOL ALL 5/E N/A RHR-V-84A 2 RHR-V-84B 2 RHR-V-84C 2 RHR-V-89 2 RHR-V-101A 2 RHR-V-1018 2 813 B7 F14 F4 X X X X X X X X X X X X 1 1/2 1 1/2 1 1/2 14 CK CK CK CK CK CK AO SA SA ALL S/E N/A ALL S/E N/A ALL S/E N/A ALL S/E N/A ALL S/E N/A ALL S/E N/A RHR-V-103A 2 F14 X X CK ALL S/E N/A RHR-V-1038 2 F4 X X CK ALL S/E N/A System Name Rf 5 IOUAL IIEAT RDIOVAL SYSTEII RIIR Owq.tin.tl521 nf 6 Valve Hunker a vc Cate or Size Class Conrail inates A 8 0 Inches Valve Actnatnr T e Tvne ttnrmal Test Pnsition Onrln Strnke Test Time.eqni sts Fnr ttntns Rclln~RIIR-V-111A 1 09 X ln liT WN 0 REFUEL POS I'VO N/A Rt8-V-1118 1 ln GT 0 REFUEL PrIS INO N/A RI8-V-111C 1 ln GT 0 REFUFL POS I.'ID tl/A RI8-V-112A 1 G9 0 REFUEL POS INO N/A RI8-V-1128 1 GB 12 Gr NAN 0 RFFIIFL POS INO tl/A RI8-V-113 1 G9 20 GT IIAN 0 REFUE L POS Itin tl/A RI8-V-115 2 RIIR-V-116 2 J6 GT IIO ALL S/T ()ALL S/T ()RI8-V-124A 2 D14 1-1/2 GiB BIO ALL S/r ()RIIR-V-1248 2 Din 1-1/2 YO ALL 5/T ()RI8-Y-125A 2 RIL'l-V-1258 2 04 D4 l-l/2 l-l/2 IIO ALL S/T (I ALL S/T ()RIIR-V-134A 2 G15 GiB HO ALL S/T ()RIIR-V-1348 2 F2 GB I!0 AI.I S/T ()RtlR-V-182 2 3/1 SV SOL ALL S/E I/A RI8-V-jj09 I F IU X X rK PFFIIr/qx 1 6x8 3/4 x 1 3/4 x 1 3/4 x 1 GB RV RV RV RV RV RV RV RV RV RV NO SA SA ALL S/T ()REFUEL BENOI N/A TEST C REFUEL BENCH N/A TEST C REFUEL BENCII N/A TEST C REFUEL BEtICH N/A TEST C REFUEL BENCH N/A TEST C REFUEL BEfICH N/A TEST C REFUEL BENCH N/A TEST C REFUEL BEIICH tl/A TEST C REFUEL BENCH N/A TEST C REFUEL BENCH N/A TEST C REFUEL BENCH N/A TEST System Name STANDBY LI UID CONTROL SLC Awg.No.H522 Paqe I of I Valve Number a ve Cat~eor~Size Class Coordinates II IV C 0 Inches SLC-V-IA'E4 X 4 Valve Actuator Normal Test Stroke T e T e Position Durin Test Time Notes GB HO C ALL 5/T ()Requests For Relief 5LC-V-1B 2 D4 GB HO ALL 5/T ()SLC-V-4A 1 SLC-V-4B 1 FB DB 1-1/2 1-1/2 5HEAR 5QUI BB C REFUEL INV N/A PLUG 3610 SIIEAR SQUIBB C REFUEL INV N/A PLUG 3610 SLC-V-6 SLC-V-7 F11 F13 X X X X 1-1/2 1-1/2 CK CK SA C REFUEL 5/E N/A C REFUEL 5/E N/A SLC-V-8 F12 1-1/2 GT HAII 0 REFUEL POS IND N/A SLC-V-33A 2 SLC-V-33B 2 SLC-RV-29A 2 F7 07 E6 X X X X 1-1/2 1-1/2 1x2 CK CK RV SA SA ALL 5/E N/A ALL 5/E N/A C REFUEL BENCII N/A TEST SLC-RV-29B 2 De lx2 C REFUEL BENCH N/A TEST System Name REACTOR WATER CLEANUP RWCU Owg.No.H523 Paqe 1 of 1 Valve Number a ve Ca~te~or Size Class Coordinates

)(B C 0 Inches Valve Actuator Normal Test Stroke T e T e Position Ourin Test Time Notes eques s For Relief RWCU-V-1 1 F15 X 6 GT HO 0 ALL S/T ()RWCU-V-4 1 RWCU-V-40 1 E15 H11 GT GT HO HO ALL S/T ()ALL 5/T ()

System Name STANDBY SERVICE'WATER SW ling.No.H524 Page Valve Number a ve Category: Size Class Coordinates

~t C II Inches Valve Actuator Normal Test Stroke T e T e Position Durin Test Time Notes eques s For Relief SM-V-1A 3 N5 X X 20 CK SA C ALL S/E N/A SM-V-1B SW-V-2A SM-V-28 G5 N6 G6 X X 20 20 20 CK BF SA HO HO ALL S/E N/A ALL S/T ()ALL S/T (SW-V-4A E9 GT HO ALL S/T ()SW-V-4B SM-V-4C SW-V-12A G9 F7 G3 18 GT GT GT HO HO HO ALL S/T ()ALL S/T ()ALL S/T ()SW-V-12B G3 18 GT HO ALL S/T ()SM-V-24A SM-V-24B SM-V-24C G9 Flo Klo GT GT.GT HO HO HO'0 ALL S/T ()ALL 5/T ()ALL S/T ()SM-V-29 BF HO ALL S/T ()SM-V-34 SM-V-44 SW-V-54 Cl I E9 F7 I 1/2 GB GT SV HO HO ALL S/T ()ALL S/T ()ALL S/T ()

System Name STANOBY SERVICE WATER SW Owg.Ho.H524 H607 Page 2 of 3 Valve Number a ve Category Size Class Coordinates

~1 Hl Inches Valve Actuator Normal Test T e T e Position Ourin Stroke Test Time Notes eques s For Relief SM-V-69A 3 G3 X 1&GT HO 0 ALi.S/T ()SM-V-698 F3 18 GT HO ALL S/T ()SM-V-70A G2 18 GT HO ALL S/T ()SW-V-708 SM-V-90 SM-V-92 9 SM-V-20'I 3 9 SM-V-202 3 9 SW-V-203 3 9)SM-V-204 3 9)SW-V-206 3 9 SW-V-207 3 9)SW-V-208 3 9 SM-V-209 3 9)SM-V-210 3 9)SW-V-211 3 F3 HB H9 C14 C14 C14 C14 815 815 815 815 Al 1 Bll X X 18 1/2 1/2 1/2 1/2 1/2 1/2 1/2 1/2 1/2 GT GT CK CK CK SV SV CK CK SV SV SV HO HO SA SOL SA SA SOL SA SA SOL SOL SOL ALL S/T ()ALL S/T ()ALL S/E N/A ALL S/E H/A ALL S/E H/A ALL S/E N/A ALL S/E H/A ALL S/E N/A Al.L S/E H/A ALL S/E N/A ALL S/E N/A ALL S/E N/A ALL S/E N/A System Name STANDBY SERVICE MATER SM Owg.No.H524 H607 Page 3 of 3 Valve Number a ve Category Size Class Coordinates 3M/C 0 Inches Valve T e.Actuator Normal Test T e Pos I t ion Our in Stroke Test Time Notes eques s For Relief g SW-V-212 3 A14 X 1/2 SV SOL 0 ALL S/E N/A SW-V-213 9.o 3 813 1/2 SV SOL ALL S/E NIA 9 SW-V-214 3 SM-V-215 SM-V-216 G8 GB BF BF BF AO ALL S/T ()ALL SIT ()ALL S/T ()SW-V-217 BF ALL S/T ()SM-V-75A 3 SW-V-758 3 SW-V-187A 3 A13 814 G14 GB GB ALL S/T ()ALL S/T ()ALL S/T ()SM-V-1878 3 C13 ALL S/T ()SM-V-188A 3 SM-V-1888 3'l13 012 GT GT ALL S/T ()ALL S/T ()(1)These valves are not yet installed and may not be installed until the first fuel outage.Above test program will be implemented after valves are installed and operable.KI a n3 C EQ~o n3 0 System Name REACTOR CLOSED COOLING RCC lbg.No.MS25 Paqe 1 of I Valve Number a ve Cat~e or>>Size Class Coordinates

~8 C D Inches equests Valve Actuator Normal Test Stroke For T e T e Position Durin Test Time Notes Relief RCC-V-5 2 D10 X 10 GT HO 0 CSD S/T ()RCC-V-21 2 D10 10 GT MO CSO S/T ()RCC-V-26 2 RCC-V-40 2 RCC-V-104 2 D11 D10 E10 X X 10 10 10 CK GT GT MO MO CSD S/E N/A CSO S/T ()CSD S/T ()RCC-V-129 3 E5 GT HO ALL S/T ()RCC-V-130 3 RCC-V-131 3 E6 E6 GT GT HO HO ALL S/T ()ALL S/T ()

System I!arne FUEL POOL CODLIIIG SYSTEN FPC 0 t9.Uo.I4528 Pano 1 n~1 a ve Valve~Cate eo Size IIunher Class Coordinates A 8 C 0 Inches Valve Actuator I!nrmal T e T e Position Teast Our Inn Strn'ke Test T{mn Romaunt;t s Fnc>Intns Rel ier FPC-V-112A 3 D12 X 6 CK SA 0 AI L 5/F.8/A FPC-V-1128 3 D12 ALL 5/F.II!A FPC-V-153 2 811 GT ALL S/T ()FPC-V-154 2 811 GiT>ID ALI.S/T ()FPC-V-158 2 Cll GT ALL 5/T ()FPC-V-172 3 C9 GT 90 ALL S/T ()FPC-V-173 3 C8 GT!t!0 ALL 5/T ()FPC-V-175 3 C9 GT ALL S/T ()F PC-V-181A 3 F PC-V-1818 3 014 D14 GT GT'IO ALL S/T ()ALL S/T ()FPC-V-184 3 C9 1!0 ALI 5/T FPC-RV-117A 3 FPC-RV-1178 3 Dll Cll 3/4 x 1 3/4 x 1 RV SA SA C PEFUFL DEN"II 8/A TEST REFUEL 8ENrH II/O TEST System Name CONTROL ROO DRIVE CRO HCU[kg.No.M528 Page I of g Valve Number a ve Catego~r Si ze Valve Ac tuator Normal Test Stroke Class Coordinates JM~.0 Inches T e T e Position Durin Test Time eques s For Notes Relief CRD-V-10 2 K6 X 1 GB AO 0 ALL S/T ()CRD-V-11 CRO-V-llOA 2 CRD-V-1108 2 F6 013 013 1-'1/2 1-1/2 GB SV SV SOL SOL N/A N/A ALL S/T ()CSO S/E N/A Normally energized 9 to ressurize cram a ve CSO 5/E II/A diaphragms CR0-V-111 2 OI3 1-1/2 CK SA CSO S/E N/A CRD-RV-12 2 H6 3/4 x 1 SA C REFUEL BENCH N/A HCU-V-114 2 HCU-V-115 2 C2 C5 X X X X CK SA SA ALL S/E N/A ALL S/E N/A HCU-V-117 2 03 SV ALL S/E N/A HCU-V-118 2 HCU-V-120 2 HCU-V-121 2 HCU-V-122 2 D3 C4 C4 C4 SV SV SV SV ALL S/E N/A ALL 5/E N/A TYPICAL OF 185 CONTROL ALL S/E N/A ROD DRIVE UNl TS ALL S/E N/A HCU-V-l23 2 HCU-V-126 2 C4 C4 SV GT AO ALL S/E N/A ALL S/E N/A System Name CONTROL ROD DRI VE CRD HCU Ihvg.No.H528 Page 2 of 2 Valve Number Valve Categorry Size Class Coordinates

~~5 Inches Valve Actuator Normal Test Stroke T e T e Position Durin Test Time Notes Requests For Relief HCU-V-127 2 C3 GT AO ALLS/E H/A HCU-V-137 2 C4 X X CK ALL S/E H/A HCU-V-138 2 C4 X X CK SA ALL S/E N/A System Name MAIN STEAM SYSTEM HS Dwg.tto.H529 page I of Valve ttumber a ve Catego~r Size Class Coordinates lM~.II Inches Valve Actuator Normal Test T e T e Position Durin Stroke Test Time Notes eques s For Relief HS-V-16 1 813 X 3 GT HO C ALL S/T ()HS-V-19 HS-V-22A I 814 F12 26 GT HO ALL S/T ()ALL S/T ()HS-V-228 I E12 26 GB ALL 5/T ()HS-V-22C 1 HS-V-22D 1 MS-V-28A F5 E5 F13 26 26 26 GB GB GB AO ALL S/T ()ALL 5/T ()ALL 5/T ()HS-V-288 1 E13 26 GB ALL 5/T ()HS-V-28C 1 MS-V-280 1 HS-V-37 SERIES HS-V-38 SERIES HS-V-67A HS-V-678 HS-V-67C E4 C6-Cl 1 X X C6-Cl 1 X X F13 F13 F4 26 , 26 10 10 1-1/2 1-1/2 1-1/2.GB CK CK GT GT GT SA HO HO HO ALL 5/T ()ALL 5/T ()CSD S/E N/A TYPICAL OF 18 5 CSD S/E N/A TYPICAL OF 18 5 ALL S/T ()ALL S/T ()ALL 5/T ()

System Name HAIN STEAN SYSTEH HS Dwg.No.H529 Page 7 of 3 Valve Number a ve Category Size Class Coordinates

~f Hi Inches Valve Actuator T e T e Normal Test Position Burin Test Stroke Time Notes eques s For Rel ief HS-V-67D 1 D4 X I-I/2 GT HO C ALL S/T HS-RV-IA HS-RV-18 HS-RV-1C HS-RV-1D HS-RV-2A HS-RV-28 F10 Ell F6 E7 F10 E10 6 x 10 6 x 10 6 x 10 6 x 10 6 x 10 6 x 10 S/R AO/SA C S/R AO/SA C S/R AO/SA C 5/R AO/SA C S/R AO/SA C S/R AO/SA C REFUEL REFUEL REFUEL REFUEL REFUEL REFUEL BENOI TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST N/A N/A N/A N/A N/A N/A HS-RV-2C HS-RV-2D HS-RV-3A HS-RV-3B F7 E7 F9 E9 6 x 10 6 x 10 6 x 10 6 x 10 S/R AO/SA C REFUEL S/R AO/SA C REFUEL S/R AO/SA C REFUEL S/R AO/SA C REFUEL BENCH TEST BENCH TEST BENCH TEST BENCH TEST N/A N/A N/A N/A HS-RV-3C HS-RV-30 HS-RV-4A HS-RV-4B HS-RV-4C F7 EB F9 E9 FB 6 x 10 6 x 10 6 x 10 6 x 10 6 x 10 S/R AO/SA S/R AO/SA S/R AO/SA 5/R AO/SA S/R AO/SA C REFUEL C REFUEL C REFUEL C REFUEL C REFUEL BENOI TEST BENCH.TEST BENCH TEST BENCH TEST BENCH TEST N/A N/A N/A ADS VALVE N/A ADS VALVE N/A ADS VALVE*Tech Specs require stroking ADS Valves at least every 18 months with Reactor steam dome pressure greater'than or equal to 100 psig.

0 System Name HAIN STEAH SYSTEH HS Dag.No.H529 Page 3 of 3 Valve Number a ve Category Size Class Coordinates

~l~J Inches Valve Actuator Normal Test T e T e Pos i t ion Burin Stroke Test Time Notes eques s For Relief HS-RV-SB Eg 6 x 10 HS-RV-40 1 EB X 6 x 10 S/R AO/SA C REFUEL BENCH N/A ADS VALVE TEST S/R AO/SA C REFUEL BENCH N/A ADS VALVE TEST HS-RV-5C FB 6 x 10 S/R AO/SA C REFUEL BENCH N/A ADS VALVE TEST*See note on previous page.

System Name REACTOR FEEDMATER SYSTEH RFM Dug.No.H529 Page I of I Valve Number a ve Cat~ear S I ze Class Coordinates

~I C D Inches Valve Actuator Normal Test Stroke T e T e Position Our in Test Time equests For Notes Relief RFM-V-10A 1 G12 X X 24 CK SA 0 CSO S/E N/A RFM-V-108 1 G5 X X 24 CK CSO 5/E N/A RFM-V-32A 1 RFM-V-328 1 RFM-V-65A 1 G13 G5 G13 X X X X 24 24 24 CK CK GT AO AO HO CSO S/E N/A CSO S/E N/A CSO S/T ()RFM-V-658 1 G4 24 GT HO CSD S/T ()

System Name REACTOR REC IRCULAT ION COOLING RRC HY Owg.No.N530 Paqe 1 of 2 Valve Number a ve Cateqory Size Class Coordinates

~I P6 Inches Val ve Actuator Normal Test Stroke T e T e Position Durin Test Time enuests For Notes Relief RRC-V-13A 2 C12 X X 3/4 CK SA 0 REFUEL S/E N/A RRC-V-138 2 RRC-V-16A 2 RRC-V-16B 2 B12 C14 X X 3/4 3/4 3/4 CK GT GT HO 0 REFUEL S/E N/A 0 REFUEL S/T ()0 REFUEL S/T ()RRC-V-19 1 F ll 3/4 ALL S/E N/A RRC-V-20 1 F12 3/4 SV SOL ALL S/E u/A

System Name REACTOR REC IRCULAT ION COOLING RRC HY Owfl.No.II 530 Page 2 of 2 Valve Number a ve Cat~e~or Size Class Coordinates 3~K 0 Inches Valve T e Actuator Normal T e Pos I t 1 on Test Burin Stroke Test Time Notes Renuests For Relief IIY-V-17A, 8 2 E4 X 3/4 5V SOL 0 CSO S/E N/A I, 10 HY-V-18A, 8 2 E4 3/4 SV SOL CSO 5/E N/A 1, 10 HY-V-19A, 8 2 E4 3/4 SV SOL CSO S/E N/A HY-V-20A, 8 2 HY-V-33A, 8 2 E4 E13 3/4 3/4 SV 5V SOL SOL CSD S/E N/A CSO 5/E N/A 1, 10 1, 10 HY-V-34A, 8 2 E13 3/4 SV SOL CSO S/E N/A 1, 10 HY-V-35A, 8 2 E13 3/4 SV SOL CSO 5/E N/A 1, 10 HY-V-36A, 8 2 E13 3/4 SV SOL CSO 5/E N/A 1, 10 R'22 fgg gaa (agg~Iga gea gaa System Name FLOOR DRAIN RADIOACTIVE FDR Owg.No.H539 Page f of f Valve Number a ve Cate or SIze Class Coordinates C 0 Inches Valve T e Actuator Normal Test T e Position Ourin Stroke Test Time Reouests For Notes RelleF FDR-V-3 2 D6 X 3 GT AO 0 ALL S/T ()FOR-V-4 06 GT AD S/T ()

System Name E UIPHENT DRAIN RADIOACTIVE EDR Dwg.No.M537 Paqe I of Valve Number a ve Ca thor~Size Class Coordinates

~I~D Inches Valve Actuator Normal Test Stroke T e T e PositIon Durln Test TIme Notes equests For Relief EDR-V-19 2 09 X 3 GT AO 0 ALL S/T ()EDR-V-20 2 GT AO 0 ALL S/T ()

System tlame PRIttARY COttTAIHNENT COOLItlG I'URGE CSP CEP Dug.No.N543 Pate 1 nf L Valve ttumber a ve Ca~te o~r Size Class Coordinates

~8 l.0 Inches Valve Actuator tlormal Test Stroke T e T e Position Burin Test Time Notes Renuests For Relief CSP-V-5 2 C5 X 24 BF AO C ALL S/T ()tlC/FO CSP-V-6 814 BF AO C ALL S/T ()NC/FO CSP-V-7 X X CK AO/SA C ALL S/E N/A CSP-V-8 CSP-V-9 CSP-V-10 2 815 86 X X X X 24 24 24 CK BF CK AO/SA C AO AO/SA C ALL S/E tl/A ALL S/T ()ALL S/E N/A NC/FO CEP-V-18 2 J13 GT AO ALL S/T{)tl0/FC CEP-V-28 2 CEP-V-38 2 CEP-V-48 2 J13 C14 C14 GT GT GT AO AO ALL S/T ()ALL S/T ()ALL S/T ()HO/Fl'.NO/FC NO/FC CVB-V-1A 2 812 X X 24 CK AO/SA ALL S/E N/A CVB-V-18 2 CVB-V-IC 2 CVB-V-1D 2 812 812 812 X X X X X X 24 24 24 CK CK CK AO/SA C AO/SA C AO/SA ALL S/E N/A ALL S/E N/A ALL S/E H/A CVB-V-IE 2 811 X X 24 CK AO/SA ALL S/E N/A CVB-V-1F 2 811 74 AO/SA C ALL S/F.N/A

System ttame PRIMARY COIITAINIIEttT COOLlttG&PIIRGE CVB Ihcg.No.H543 Paqe Valve ttumber a ve Cat~ear Size Class Coordinates

~~C 6 Inches equests Valve Actuator ttormal Test Stroke For T e T e Position Ourinn Test Time Notes Relief CVB-V-IG 2 811 X X 24 CK AO/SA C ALL S/E N/A CVB-V>>IH 2 811 CVB-V-I J 2 89 CVB-V-IK 2 89 X X X X X X 24 24 24 CK CK CK AO/SA C AO/SA-C AO/SA ALL S/E N/A ALL S/E N/A ALL 5/E N/A CVB-V-1L 2 88 X X 24 AO/SA C ALI.S/E N/A CVB-V-IM 2 BB CVB-V-1N 2 88 X X X X 24 24 CK AO/SA C AO/SA ALL S/E N/A ALL S/E N/A CVB-V-IP 2 88 X X 24 CK AO/SA C ALL 5/E N/A CVB<<V-III 2 87 X X 24 AO/SA C ALL S/E N/A CVB-V-IR 2 87 CVB-V-IS 2 87 CV8-V-1T 2 87 X X X X X X 24 24 24 CK CK CK AO/SA AO/SA C AO ALL S/E N/A ALL S/E N/A ALL 5/E N/A PI-VX-250 2 F13 SV SOL ALL S/E N/A PI-VX-251 2 F13 PI-VX-253 2 F13 SV SV SOL SOL ALL S/E N/A ALL S/E N/A System tlame PRIHARY CONTAIHIIENT COOLItlG B PURGE CVB PI Dug.tlo.H543 Paqe 3 oF 3 a ve Valve Cat~e~orSize Number Class Coordinates

~h~Inches PI-VX-256 2 F7 X 1 Valve Actuator Normal Test Stroke T e T e Position Durin Test Time SV SOL 0 ALL S/E N/A Notes eques s For Relief PI-VX-257 2 F7 SV SaL ALL S/E N/A P I-VX-259 2 SV ALL S/E N/A UM-NUHBERED 2 F12 X X CK ALL S/E N/A HAVE POSITIOII Utt-IINIBERED 2 PI-VX-262 2 F7 E13 X X CK SV saL ALL S/E H/A ALL 5/E N/A PI-VX-263 2 E13 SV SOL ALL S/E N/A PI-VX-264 2 PI-VX-265 2 P I-VX-266 2 E13 E14 E7 SV SV SOL SOL ALL S/E N/A ALL S/E H/A ALL S/E tl/A PI-VX-267 2 E7 SV SOL ALL S/E N/A PI-VX-268 2 PI-YX-269 2 E7 E6 SY SV SOL SOL ALL S/E N/A ALL S/E N/A

Sys tern Name CONTAINMENT ATHOSPNERE CONTROL (CAC Dog.No.H554 Page ACC IDENT HI TIGAT ION Valve Number a ve Category Size Class Coordinates 7~~Inches CAC-V-IA 2 F15 X 2 Valve Actuator Normal Test Stroke T e T e Position Ourin Test Time OIA NO C ALL S/T ()Notes eques s For Relief CAC-V-18 2 Fl DIA IIO ALL S/T ()CAC-V-2 G10 GT HO ALL S/T ()CAC-V-2A 2 CAC-V-28 2 CAC-V-4 F12 F5 EIO GT HO OIA UO OIA IIO ALL S/T ()ALL S/T ()ALL S/T ()CAC-V-6 HIO GT HO ALL S/T ()CAC-V-8 CAC-V-11 2 CAC-Y-13 2 D10 G6 E6 GT GT GT HO HO ALL S/T ()ALL S/T ()ALL S/T ()CAC-V-15 ll6 GT MO ALL S/T ()CAC-V-17 2 GT MO ALL S/T ()CAC-V-318A 2 CAC-V-3188 2 012 D12 GT GT MAN C REFUEL IND N/A C REFUEL IND N/A CAC-FCV-1A 2 Hlo 2-1/2 ALL S/T ()

System Name CONTAINNENT ATHOSPHERE CONTROL CAC Dwg.No.N554 Page a ve Valve Category Size Number Class Coordinates 1nches Valve Actuator Normal Test T e T e Position Dur in Stroke Test Time Notes eques s For Relief CAC-FCV-18 2 H6 2-1/2 GB HO C ALL S/T ()CAC-FCV-2A 2 CAC-FCV-28 2 CAC-FCV-3A 2 CAC-FCV-38 2 Glo G6 010 06 2-1/2 2-1/2 2-1/2 2-1/2 GB GB GB HO HO ALL S/T ()ALL S/T ()ALL S/.T ()ALL S/T ()CAC-FCV-4A 2 CAC-FCV-48 2 CAC-FCV-5A 3 CAC-FCV-58 3 F10 F14 F2 2-1/2 2-1/2 GB GB HO ALL S/T ()ALL S/T ()ALL S/T ()ALL S/T ()CAC-FCV-6A 2 CAC-FCV-68 2 CAC-RV-63A 3 G12 G4 E12X 1 x2 RV SA ALL S/T ()ALL S/T ()REFUEL BENCH N/A TEST CAC-RV-638 3 E4 lx2 RV SA C REFUEL BENCH N/A TEST CAC-RV-65A 3 CAC-RV-658 3 D13 11/2x3 RV 1 1/2 x 3 RV SA SA C REFUEL BENCH N/A TEST C REFUEL BENCH N/A TEST System Name CONTAINHENT INSTRUHENT AIR CIA tkg.No.H556 Page Valve Number a ve Category Size Class Coordinates Inches Valve Actuator Normal Test Stroke T e T e Position Ourin Test Time Notes eques s For~Relief CIA-V-20 2 J6 X 3/4 GB HO 0 ALL S/T ()CIA-V-21 2 CIA-V-24 SERIES CIA-V-30A 2 CIA-V-308 2 J6 N4-K4 N6 F6 X X X X 3/4 1/2 1/2 1/2 CK CK GB GB SA SA HO HO 0 REFUEL S/E N/A C REFUEL S/E N/A TYP.OF 4 ALL S/T ()ALL S/T ()CIA-V-31A 2 CIA-V-318 2 CIA-V-36 SERIES CIA-V-39A 3 H6 84-II4 117 X X X X X X 1/2 1/2 1/2 1/2 CK CK SV SA SA SA SOL 0 REFUEL S/E N/A 0 REFUEL S/E N/A C REFUEL S/E N/A TYP.OF 18 ALL S/E N/A CIA-V-398 3 N7 1/2 SV SOL ALL S/E N/A CIA'-V-40 SERIES N5-85 X X 1/2 CK SA REFUEL 5/E N/A TYP.OF 7 CIA-V-41A 3 CIA-V-418 3 N7 X X X X'I/2 1/2 CK SA SA REFUEL S/E N/A REFUEI.S/E N/A 0

System tlame HAIN STEAM LEAKAGE COtlTROL MSLC Dug.No.M557 Page 1 of 1 a ve Valve Category Size Number Class Coordinates

~B C 0 Inches HSLC-V-lA 2 87 X 1-1/2 equests Valve Actuator Normal Test Stroke For T e T e Position Our in Test Time Notes Relief GT MO C ALL S/T ()MSLC-V-18 2 BS l-l/2 GT HO S/T ()MSLC-V-1C 2 D7 l-l/2 HO ALL 5/T ()HSLC-V-1D 2 05 1-1/2 GT HO C ALL S/T ()HSLC-V-2A 1 HSLC-V-28 1 CB CB 1-1/2 1-1/2 GT GT HO MO ALL 5/T ()ALL 5/T ()HSLC-V-2C 1 ES l-l/2 GT HO ALL S/T ()HSLC-V-20 1 HSLC-V-3A 1 HSLC-V-38 1 ES C9 CB 1-1/2 1-1/2 1-1/2 GT GT GT HO HO HO"ALL 5/T ()ALL S/T ()ALL S/T ()HSLC-V-3C 1 EB l-l/2 GT HO ALL 5/T ()HSLC-V-30 1 HSLC-V-4 2 HSLC-V-5 2 EB JS JS 1-1/2 l-l/2 1-1/2 GT GT GT HO HO HO ALL S/T ()ALL S/T ()ALL 5/T ()HSLC-V-9 2 II5 1-1/2 GT HO ALL S/T ()HSLC-V-10 2 ll5 1-1/2 GT IIO"ALL S/T ()

Page 4-43 Revision 0 (4.5 Requests for Relief from Certain Code Requirements Relief Requests are presented to document differences between the Code and MHP-2's~lalve Test Program.The requests include technical justification for the differences and, where appropriate, propose alternate testing.

Page 4-44 Revision 1 GENERAL RELIEF REQUEST (OELETED)

Page 4-45 Revision 1 REQUEST FOR RELIEF NO.RV-1 System Valves(s)ASME Classificati on Function Various Solenoid valves affected by this relief request are identified in TABLE A.Code Testing Requirement 1.Timing of valve stroke (IMV-3413)

Bases for Relief 1.Solenoid valves are very rapid acting, with stroke times much less than one second.It is meaningless to measure their stroke times"to the nearest second".Alternate Testing 1.to be Performed Valves will be full stroke tested.Satisfactory operation of equipment downstream of the solenoid valve will constitute satisfactory valve operation.

ualit/Safet Im act The only valves in Table A for which timing might be an important parameter are the Category A valves which are containment isolation valves.However, these valves have position indication displayed in the Control Room and on the Transient Data Acquisition System.Furthermore, each of the Category A valves have backup valves which can be used to isolate the line should it be required.The proposed exercise testing and regular position indication verification will provide adequate assurance of quality and public safety.

Page 4-46 R RV-1 TABLE A Valve Code Class Cate or Function HY-V-17A, 8 HY-V-18A, 8 HY-V-19A, 8 HY-V-20A, 8 HY-V-33A, 8 HY-V-34A, 8 HY-V-35A, 8 HY-V-36A, 8 Hydraulic supply for Reactor Recirculation Flow Control Valves RRC-V-19 RRC-V-20 Reactor recirculation sampling Iso valve.Reactor recirculation sampling Iso valve.CIA-V-39A C IA-V-398 Cross ties between air and nitrogen headers.DO-V-40A DO-V-408 DO-V-43 Diesel fuel oil day tank 3A inlet valve Diesel fuel oil day tank 38 inlet valve Diesel fuel oil day tank 3C inlet valve CRD-V-110A CR D-V-1108 Back-up Scram Valve (Air Supply)Back-up Scram Valve (Air Supply)

Page 4-47 Revision 0 RV-1 TABLE A (Cont'd}Valve Code Class Cate or Function PI-VX-251 P I-VX-250 PI-VX-253 PI-VX-256 PI-VX-257 PI-VX-259 Radiation moni or RAD-RE-128 inlet valve Radiation monitor RAO-RE-128 outlet valve Radiation monitor RAD-RE-128 outlet valve Radiation monitor RAO-RE-12A inlet valve Radiation monitor RAO-RE-1?A inlet valve Radiation monitor RAO-RE-12A outlet valve PI-VX-262 PI-VX-263 P I-VX-264 PI-VX-265 2 H2, 02 monitor inlet and outlet valves{S-SR-13)P I-VX-266 PI-VX-267 P I-VX-268 PI-VX-269 H2, 02 monitor inlet and ou.let valves (S-SR-14)CAS-V-453 Air supply to drywell-wetwell down-comer vacuum breakers.RHR-V-60A RHR-V-608 RHR-Y-75A RHR-V-758 RHR-V-182 8 8 Loop A sample (inboard)Loop 8 sample (inboard)Loop A sample (outboard)

Loop 8 sample{outboard)

Drain Vv between Valves isolating Service'~later from RHR RV-1 TA8l E A (Cont'd)Page 4-48 ReYi sion 0.Valve Code Class Cate or y Function SM-V-201 SM I 204 SM-Y-206 SM-V-209 SM-Y-210 SM-V-211 SLI-V-212 SM-V-213 Cooling Mater to H2, 02 analyzers S-SR-13, 14.

Page 4-49 Revision I REQUEST FOR RELIEF NO.RV-2 System Valve(s)ASME Cl assi f i cati on Function Various Emergency Core Cooling Systems Valves affected by this relief request are identified in TABLE 8.Code Testing Requirement Quarterly valve exercising (IWV-3411)

Bases for Relief 2.Valves cannot be opened against the differential pressure which exists across them during power operations.

Reactor coolant system pressure holds the valves closed.Valves are located inside containment and cannot be temporarily isolated to allow testing.Al ternate Testing l.to be Performed Valve exercising will be performed during cold shutdown.ualit/Safet Im act Nore frequent testing of the valves in Table 8 would require plant shutdowns solely to accommodate testing.Such requirements violate the intent of the Code (IWV-3412(a)), which recognizes that certain valve tests are not prac-tical during plant operation.

Furthermore, the redundancy of the emergency core cooling system ensures that no single failure of the valves in Table 8 will compromise the plant.The proposed testing and plant design, provide an acceptable level of quality and safety.

Page 4-50 RV-2 TABLE B Valve Code Class Cate or Function HPCS-V-5 A-C HPCS discharge to reactor vessel.LPCS-V-6 A-C LOCS discharge to reactor vessel.RHR-V-41A RHR-Y-41B RHR-V-41C RHR-V-50A RHR-V-50B RHR-V-209 RC IC-V-66 A-C A-C A-C A-C A-C A-C A-C RHR loop A discharge to reactor RHR loop B discharge to reactor RHR loop C discharge to reactor RHR loop A discharge to recirculation pump discharge.

RHR loop 8 discharge to recirculation pump discharge.

Pressure relief bypass around RHR-V-9.RCIC discharge to reactor vessel head.

Page 4-51 Revision System Valve(s)ASi~iE Classification Function RE(VEST FOR RELIEF NO.RV-3 Containment Instrument Air Valves affected by this relic request are identified in TA8LE C.Code Testing Requirement quarterly testing{INV-3412)Position indication ver i f i cat i on (IMV-3522)8ases for Relief 2.The 40 series, 36 series and 24 series valves are located inside containment and cannot be accessed during power operations.

There is no way to remotely isolate the valves and observe the pressure decay o, the accumulators.

There is no local or remote position indication for these check valves.Alter nate Testing 1.to be Performed 2.During refueling outages, pressure decay tests will be performed for the accumulators associated with the Hain Steam Isolation Valves and with the>lain Steam Safety/Relief Valves in order to verify closure abil-ity of 40 series, 35 series, and 24 series valves.Each accumulator will be tested at least every two years.Closure ability of CIA-V-21, 31A and 8, and 41A and 8 will be verified by normal 10CFR i', Appendix J (Type C)testing.ualit/Safet~Imoact The proposed testing qualitatively verifies valve closure on the most prac-tical regular basis.This satisfies the intent of the Code (IMV-3412).

Valve opening is verified when the accumulators are pressurized in preparation for the pressure decay test.The valves in Table C are in the pneumatic supply to the auto-depressurization System valves, a safety related system.However, the proposed alternate testing together with the redundancy of the pneumatic supplies and individual accumulators, of the AOS valves themselves and of the high pressure iniections systems assures an acceptable level of quality and public safety.

Page 4-52 Revision 1 RV-3 TABLE C Valve Code Class Cate or Function C IA-V-31A C IA-V-31B C IA-V-41A C IA-V-41B 8-C B-C 8-C B-C"2 supply to ADS valves (0/C)Cross tie between air and N2 line CIA-V-40 series 2 (7 valves)CIA-V-36 series 2 (18 valves)CIA-V-24 series 2 (4 valves)C IA-V-21-2 A-C A-C A-C 8-C N2 to AOS Accumulators (inside containment Air supply to Main Steam Relief Valves'ccumulators (inboard check valve)Air supply to Main Steam Isolation Valves (Inboard)Instrument air supply to containment (outboard check valve).

Page 4-53 Revision 1 REQUEST FOR RELIEF NO.RV-4 System Valve(s)ASME Classification Function Standby Liquid Control (SLC)SLC-V-6, SLC-V-7 Code Class: 1 Category: A-C Standby Liquid Control discharge to reactor vessel.Code Testing Requirement I)Quarterly exercising (IWV-3521) 2)Cold shutdown exercising (IWV-3522)

Basis for Relief l.Valves have no operator with which they may be stroked.2.Exercising the valves require the initiation of the SLC system and full flow injection into the reactor vessel.Initiation of SLC flow involves the discharge of Class D explosive activated valves.Alternate Testing At least once per 18 months, one of the Standby Liquid Con-to be Performed trol System loops, including the associated explosive valve, will be initiated.

A flow path to the Reactor Vessel will be verified by pumping demineralized water to the vessel.Valve closure capability will be verified in conjunction with 10CFR50 Appendix J (Type C)testing.ualit/Safet Im act The purposed testing complies fully with the intent of the Code (IWV-3522).

Additionally it is noted that the SLC system will be required to perform its safety function only under very infrequent circumstances (ATWS).The proposed testing provides adequate assurances of quality and public safety.

Page 4-54 Revision I REQUEST FOR RELIEF NO.RV-5 System Valve(s)ASME Class if ication Function Main Steam MS-V-37 series (18 total), MS-V-38 series (18 total)Code Class: 3 Category: A-C Vacuum Breakers for main steam relief line downcomers.

Code Testing Requirement Quarterly exercising (IWV-3521)

Bases for Relief 2.Valves have no power operator by which they may be stroked remotely.Valves are located inside primary containment and, consequently, are inaccessible during power operations.

Alternate Testing Valves are accessible during cold shutdown and will be to be Performed exercised at that time in accordance with the requirements of paragraph IWV-3522.Valves will be verified to be closed at the completion of exercise testing.ualit/Safet Im act The proposed testing complies fully with the intent of the Code (IWV-3522) which allows less frequent testing if"such operation is not practical during plant operation".

Further, each downcomer has redundant vacuum breakers for additional reliability.

The alternate testing and valve redundancy assure acceptable levels of quality and safety.

Page 4-55 Revision 1 REQUEST FOR RELIEF NO.RV-6 System Valve(s)ASME C1 ass if i cati on Function Reactor Feedwater (RFW)Valves affected by this relief request are identified in TABLE 0.Code Testing Requirement Quarter ly exercising (IWV-3411, IWV-3521)Bases for Relief 2.Closure of either Category A valve (RFW-V-65A, 65B)would result in a loss of flow to the reactor vessel and cause a significant reduction of reactor coolant inventory.

Category A-C valves are held open by feedwater flow and cannot be closed during power operations.

Alternate Testing Valves will be exercised during cold shutdown.to be Performed ualit/Safet Im act The Code does not require disruption of plant operation to support valve testing (IWV-3412, IWV-3522).

The proposed testing is the maximum practical during normal power operations and, together with a system design featuring three valve in series, assures acceptable levels of quality and safety.

Page 4-56 R RV-6 TABLE D Valve.Code Class Cate ory Function RFW-V-10A RFW-V-108 A-C A-C Reactor Feedwater inboard check valves.RFW-Y-32A RFW-V-32B A-C A-C Reactor Feedwater outboard check valves.RFW-V-65A RFW-V-65B Reactor Feedwater stop valves.

Page 4-57 Revision 1 RE(VEST FOR RELIEF HO.RY-7 System Valve(s)ASME Classifi cati on Reactor Recirculation Coolant (RRC)Valves affected by this relief request are identified in TABLE E.Functi on Code Testing Requirement quarterly exercising (IWV-3411 and IWV-3521)Bases for Relief 2.Closure of Category A valves (RCC-V-16A,-16B)would terminate seal purge water, flow to recirculation Pump 1A or 18, respectively.

Loss of purge flow may result in excessive seal wear and possibly failure of the seal.The risk associated with seal failure are greater than the benefits gained by quarterly valve testing.Category A-C valves are held open by purge water flow and cannot be closed during power operations.

Alternate Testing Valves will be exercised during cold shutdown.to be Performed gualit/Safet Im act NRC Guidance (i.e., Oraft Reg.Guide MS901-4)states that"valves which when exercised (cycled)could put the plant in an unsafe condition" should be excluded from testing.The valves in Table E, if cycled, would endanger the reliability of the Reactor Recirculation pumps and, consequently, cause unsafe conditions.

Postponing, therefore, contributes to assuring acceptable levels of quality and safety.

Page 4-58 R RV-7 TABLE E Valve Code.Class Cate ory Function RRC-V-13A RRC-V-138 A-C A-C Recirculation pumps'eal purge line inboard isolation valve.RRC-V-16A RRC-V-16B Recirculation pumps'eal purge water supply line outboard isola-tion valve.

Page 4-59 R RE(VEST FOR RELIEF NO.RV-8 System Valve(s)ASME Classification Function Reactor Closed Coolant (RCC)Valves affected by this relief request are identified in TABLE F.Code Testing Requirement quarterly exercising (IWV-3411 and IWV-3421).

Basis for Relief Closure of any isolation valve will interrupt coo'iing water flow to the Reactor Recirculation (RRC)Pump seals, to the RRC pump motor coolers and to the Drywell Air Coolers pos-sibly causing equipment failure or disruption of reactor operation.

The risks associated with these consequences outweigh any potential benefits derived from quarterly testing of these valves.Alternate Testing Valves will be exercised during cold shutdown.to be Performed ualit/Safet Im act Failure of any one of the valves in Table F would terminate cooling water flow to equipment inside containment.

NRC guidance suggests that such valves are not required to be tested to normal IWV schedules.

Therefore, granting of this relief request will contribute to acceptable levels of quality and safety by increasing the reliability of plant equipment.

Page 5-1 Revision 1 5.0 qua lity Assu'rance Program The WNP-2 Pump and Valve Inservice Test Program activities will be conducted in accordance with Topical Report WPPSS-gA-004, the Supply System's Operational quality Assurance Program description.

Page 6-1 Revision 1 6.0 Flow Diagrams The Flow Diagrams used to generate this Program are included for user reference.

Oue to the time required for Program publication, an administrative cut-off date of June>1982 was chosen to"freeze" drawing revisions used for Revision 1 of the Program.However, system design is not expected to change radically, and, in any case, more current diagrams will be provided as the Program is updated.

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OCC-v<45')a(eve)~RuvtRL t.4 ISC gl covlecooLCR StCV0 4SL.M/g~SYPIAPI c a)CCIACX~4 Oft R%4 4 I Rt~4 t/coo IR 5(U'RC~(4 514 t)caeees(R WAV INC PRODUCT NCLT tv()ELM ct IL Ruvl I'5%er(SC WC tR rrtcuao ea Acc(EI)I',RCC Rv 4A COL Iee CCC.v IISL 1 C~%(trvswf b 4 L'T~(ltlCL (Coact a4,1O I" ccc(54 4~OCY.NN t)rO((()s.l (tcc()o 4 SllteelC Ccoalt A(CVel 5 Rcr.(%%1.1 ace(st)v RurV 154L 4444)4>>la(Too%El%.IOV P slaw wel Eeevswl t'RCC (4)I N 5)QR5 RCC Vro~~+~-Ao(R)e I 5 Ru(%0 I)RCCVI)L TIE'1 EO 0 RCCCS)M (S)e~ecov)(lc I RCC'5 I ICCYVC I'aCC(SOI er ISV ONA 5~$RCCRrNC)I 5 oeo v ltt OYCVLIICIR RCC Na IC~~RCCELN IC vr 0'Nc(ON~pet V.Sc Idt(C(SQ Rccv)us g RCC I evacode rwanda%(oc crocoo FOR tee coo atcc wLecea ll(LT llac alvrlt e(C~ve'I~1 ters er(CO 4 y~Rcov el I~coty~CCU)4 J R(Der)+CYM 10'RCC(5)4 I'RCC 5))~I 54~~eeaaceoa SMM.caocso FCR wLYSR vle1 eceveroce t c.eex IL 8 eltleer-~4.ql Ei-m-0--"~ 'RCC 11 I reevv\I I I I I I I I I I[V I I I I I I I ul I I I I i I I I POR VALVE P t II.LtTTtaf t OCTLEL NCC V 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DLD(5%TARTAR%PR(M TNR%54CY(fl SEILDIE)cr wtST WELL, C(HERC CAT%CONY Ir.~a.rr COOS CROUP D (5 4 ALL PIPOA(5>VALVRS JMO ASSOC)RIND ~%II(R)ETC OQ TN(5 OAHAHTS(Cr~NR, RCC SYCTRM,P(TNC.ERA>>TOE OE)LCWO.SEILLL OC CEASSPKO AS~Rxcctr As Non(N SRrswrc cATE>>OLY (5~OVMI TV COAS 5~()CODS OROUF'~At SCC'WN I)0, COEITRLCT%15 F All Pit)>>4 VLLYSS LEO LIOOCIAT(0 con ONOI1rs oN rxrf IRANENC tcctprAINCTEO ADOYR~SCISLAIC CLTCOC RY<gaWP CLASS Z C TNCSE YALvtd WCL DE ONCLUOCD IM TME~ISOLATNN VALVE POSlno" DISPLAY PANCIA 1 RCCrV'ICSL O Yacc(4)I)C)tert(IOIS toert(5 4)RCCVI)A 5~rc Ae Ir t((041)MNILTION Conc(RTCAT CCKFC aft R Mwt.u'I SL 4a toolL V%(COPV SSL~044 y gv!~4 RCCVCQ(0 C 0+4!CCV)\red;N)M SIL'S y F VIIN1045 ZONE (54r)0 DECONTAMINATION CONC(el CATIA(coco(NSE 4 aev>>.nxoo OCCCP44 locust Rc(ELVA%Y.ECRCC(5(OI 4 RCC(44 Oa eco41 Drr~~CC NOT%1)DN IINSMSSS Snr.l CLYCOL aaMC Ifttoeo MSOS 4(A r)E (SEC NOTE R-.---~5 Rcc(f5>>III ON DWO)AS%5 SNL)tea VVO SALL PIPINS DOWNSTRCAM 05 TNE LA'CT ISOLATNIN VALVE Al(D ottN To TN'C ATMOS'Pntat WITH TNC c'vdsvsTSSA Dts14NATIDM SYSTEM ($0)TNRU($8)SHALL$%CLASSIFltd A%COD'RCPDVPD I wITN 4(UALIT Y cLAss AIED%tlsl4K CA'1'CRONY PR(FVIDED SY TH'APPLICADLL TIDTCS ON THS DRAW)144.<<ZV T)S nACPMS O.Sr.'COCO%NCC RC(rl 04 I q a6 St%NO)tk 11 OS c u&DwsMs)$5RCI obltr)c D 14 OC.CF>>oc (Tvt)lit sws call%or(z TDNc Nvt PGR IOCNTIPICATION OP LEAF ND tovetlateaT 5 atc Yet ts'FR(CI ((Sag()))(V)EQUAL A%F4'VENT VALVS RACE TAS NOTRD R ALLvALvts svps(KED weTH A (()NA(UAL raag DRHN VALVE RVRNS AND NDC.)N(4)ecostts LM)c0451wlcloes cceoNL~L clvleloa 4 Y.UN owaca cnp FLOW DIACRAN ctoscd coouno'RATER ETSTEN 5(CACTDR HCI RAONASTR OUI(DIN%wAsNOKT(N(PUsuc rowcR SUPPLY STSTEN aaevooo sc 5 cove CION R Eve ce oee~le\Ives aav va o<<vwa eM ee'vc 15.14.:13(":-,"%'".Q'..".">"(.rv.11~10 7tR TLIK SOEOPCOS AVPLYOE(C Sl I)oc<<t()tr)vwsrprfrs)ron)04444 MS~4701', wr v av M e y a~~'I l 15 14 13 12 2 coNTAAcf ros DOto WW h>C N O>>Pt L ALL COC)SVVCSIT, VNVTSI SPCCILLTI($ .ASO DOTRIASCNTATSON W'Cse(KOCH 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RCYSSCDS)CYCSCASOED ALYc llc PSR Y)OA,)455 toIE(oscs P aa<<PIO D 4 Ptl(PC>>'555 oslT<<CT tol A()oc(x Na Z.~4$."4('2 AA14 X'NO JIL s v~)<<')so o so<<a~vvalal5 W.O.2808 sv'v D}E((455 b07'N2 g'c '4 f I WASHINGTON PUBLI'C POWER SUPP SYSTEM NUCLEAR PROJECT NO 2 PUMP D VALVE INSERVICE TEST ROGRAM PLAN c) Ta'~ PUMP AND VALVE INSERVICE TEST'ROGRAM PLAN-REV.2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO.2 Prepared by Operations Support ngineering Date Reviewed by Senior Mechanical Engineer Ir 3S Date Concurrence Supervisor, ode grams)I 3 83 Date Manager, System Design Engineering Date Concurrence Manager, Plant QA/QC Date Approved by Concurrence lant Ma ager, WNP-2 Author ize Nuclear Inservice Inspector a~erg~Date 0$$~~g~j~I~F~I'SHRED RS J 4 TITLE Title Sheet Si n Ori.Recor s of Revision 1.0 Intro.2.Tab e of Contents 3.Pump est Pro ram SHEET 2-1 3-1 3-2 3~3 3-4 3-5 3-6 3-7 3-8 3-9 REVISION N/A was 3.8 TITLE ump est Pro ram Contd 4.0 WNP-2 SHEET 3-12 3-13 3-14 3-15 3-16 3-17 3-18 3-19 3-20 3-21 3-22 3-23 3-24 3-25 3-26 3-27 3-28 4-1 REVISION was 3-12b was 3-10 was 3-14 was 3-25 3-10 Valve Inservice 4-2 3-11 1 was 3.12a Test Pro ram 4-3 4-4 4-5 iv TITLE SHEET REVISION TITLE SHEET REVISION 4.0 WNP-2 4-6 a ve Inser vice 4-7 es Pro r am 4-8 on 4-9 4-10 4-11 4-12 4-13 4-14 4-15 4-16 4-17 4-18 4-19 4-20 4-21 4-22 4-23 4-24 4-25 4.0 WNP-2 4-26 a ve Inservice 4-27 es Pro ram 4-28 on 4-29 4-30 4-31 4-32 4-33 4-34 4-35 4-36 4-37 4-38 4-39 4-40 4-41 4-42 4-43 4-44 4-45 0 was 4-43 TITLE 4.0 WNP-2 SHEET 4-46 REVISION TITLE SHEET REVISION a ve Inservice 4-47 Test Pro ram 4-48 Contd 4-49 4-50 4-51 4-52 4-53 4-54 4-55 4-56 , 4-57 4-58 4-59 TITLE 5.0 ua1 it Assurance Pro ram SHEET 5-1 REVISION TITLE SHEET oor rain Radioactive M 539*ontainment Coolin EPur e M 543*ontainment Atmos.Control M 554*REVISION 46 39 29 6.ow Dia rams 6-1 Diesel Oil 5 Misc.S stems M 512*32 ontainment Instru.Air M 556*Main Steam Leaka e Cont.M 557*26 Reactor Core Iso.Coolin M 519*ow ressure Core S ra M 520*High Pressure Core S ra M 520*Residual Heat Removal M 521*tand y iq.Control M 522*Reactor Water Cleanu M 523*Standby Service Water M 524*Reactor C osed Coo lin M 525*Fuel Pool Coolin M 526*Control Rod Drive M 528*Main Steam M 529*Reactor Feedwater, M 529*Reactor Recirc.Coo lin M 530*Equip.Drain Radioactive M 537*37 38 38 44 18 50 42 36 46 32 40 40 36 41 Steam an Li uid Sam.M 607*sh.2 12*Burns 8 Roe Flow Dia ram Number vii Page 1-1 R

1.0 INTRODUCTION

This Pump and Valve Inservice Test Program Plan is applicable to the WPPSS Nuclear Project No.2, hereinafter referred to as WNP-2.A single unit Boiling Water Reactor (BWR), the power plant is located ll miles north of Richland, Washington, on the Hanford Reservation. The plant employs a General Electric (GE)supplied nuclear steam supply system designated as BWR/5.The reactor is contained within an over-under drywell/wetwell con-tainment vessel designated Mark II.The plant rated electrical output is 1,094 MWe.This program plan is referenced in the WNP-2 FSAR, Section 3.9.6, and has been prepared as the controlling document governing Pump and Valve Inser-vice Testing at WNP-2.The requirements for Pump and Valve Inservice Testing are outlined in the ASME Boiler and Pressure Vessel Code, Section XI, entitled"Rules for Inservice Inspection of Nuclear Power Plant Com-ponents." The scope of this plan encompasses the testing of ASME Section III Nuclear Class 1, 2 and 3 pumps and valves, as defined by Subsections IWP and IWV of the ASME Code Section XI.This program plan complies with the requirements of the ASME Code 1980 Edition, with addenda through Winter, 1980 (and with addenda through Winter, 1981).This is consistent with FSAR commitments and with federal requirements for component testing as stated in Title 10, Code Federal Regulations, part 50 (10CFR50.55a(g)3-This Program Plan is comprised of two subprograms -'-the Pump Inservice Test Program and the Valve Inservice Test Program.The detailed descrip-tion of the scope, implementation, and administration of these two pro-grams is detailed in subsequent sections (3.0 and 4.0). Page 2-1 Revision 2 I 2.0 TABLE OF CONTENTS Record of Revisions 1.0 Introduction 2.0 Table of Contents 3.0 Pump Inservice Test Program Description 3.1 Program Development Philosophy 3.2 Program Implementation 3.3 Program Administration 3.4 Pump Reference List 3.5 Pump Inservice Test Tables 3.6 Requests for Relief from Certain IWP Requirements 3.7 Proposed Pump Test Flow Paths 3.8 Records of Inservice Tests 4.0 Valve Inservice Test Program Description 4.1 Program Development Philosophy 4.2 Prognam Implementation 4.3 Program Administration 4.4 Valve Test Tables 4.5 Request for Relief from Certain IWV Requirements 4.6 Records of Valve Inservice Tests 5.0 equality Assurance Program 6.0 Piping and Instrument Diagrams Page 3-1 R 3.0.WNP-2 Pump Inservice Test Program 3.1 Introduction Highly reliable safety related equipment is a vital consideration in the operation of a nuclear generating station.To help assure operability, the WNP-2 Pump Inservice Test Program has been developed. The Program is designed to detect and evaluate significant hydraulic or mechanical changes in the operating parameters of vital pumps and to initiate corrective action when necessary. The Program is based on the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWP.To the maximum extent practical the Program complies with the specifications of the approved Codes(l), Regulations (2), and Guidelines(3). Consistent with the intent of Subsection IWP, the Supply System has incorpor-ated into this program certain requirements which exceed the specifications of the Code.In particular, the Diesel Fuel Oil Transfer Pumps are included for testing due to their potentially significant impact on plant safety.The Supply System recognizes that design differences among plants may render impractical certain Code requirements. For example, it is not always practi-cal to require suction pressure measurement on vertical turbine ("deep well")type pumps.Where such impracticalities exist, they have been substantiated as exceptions as allowed by the Code.Alternate testing requirements have been proposed when warranted. The Relief Requests which document the excep-tions comprise Section 3.6.The Supply System is confident that the WNP-2 Pump Inser vice Test Program complies with the intent of the approved Codes(1), Regulations(2), and Guidelines(3) and contributes to ensuring the safety of the general public.1.ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWP, (1980 Edition with Addenda through Winter, 1980 and 1981).2.10CFR 50:55 a(g).3.NRC Staff Guidelines for complying with certain provisions of 10CFR 50:55 a(g)"Inservice Inspection Requirements".

Page 3-2 R 3.2 Pro'ram Im lementation Surveillance testing is performed to detect equipment malfunction or de-gradation and to initiate corrective action.Since the safety related pumps are normally, in a standby mode, periodic testing of this equipment is especially important. The WNP-2 Pump Inservice Test Program provides a schedule for testing safety related pumps and will be implemented as part of the normal surveillance routine.Reference values will be determined in accordance with paragraph IWP-3110 of the ASME Code.It is anticipated that reference data will be gathered during initial surveillance tests.In most cases, test parameter s will be measured with normal plant instrumentation. This approach will simplify the test program and will promote timely completion of surveil-lance testing.When permanently installed instrumentation is not availa-ble, portable instrumentation will be used to record the required para-meters.During subsequent surveillance tests, flow rate will normally be selected as the independent test parameter and will be set to match the reference flow rate.Then other hydraulic and mechanical performance parameters will be measured and evaluated against the appropriate reference values.The results of such evaluations will determine whether or not corrective action is warranted. Each pump in the Pump Test Program will be tested according to a detailed test procedure. The procedure will include, as a minimum: a)Statement of Test Purpose.This section will identify test objec-tives, reference applicable Technical Specifications and may note the operating modes for which the test is appropriate. b)Prerequisites for Testing.System valve alignment, equipment for proper pump operation (cooling water, ventilation, etc.)and addi-tional instrumentation (e.g., portable temperature or vibration monitors)will be noted.Identification numbers, range and cali-bration verification of additional instrumentation will be recorded.c)Test Instructions. Directions will be sufficiently detailed to as-sure completeness and uniformity of testing.Instructions will include provisions for returning system to its normal standby con-figuration following testing.(For informational purposes, proposed flow paths are illustrated in Section 3.7.)d)Acceptance Criteria.The ranges within which test data will be con-sidered acceptable will be established by the Supply System and in-cluded in the test procedure. In the event that the data fall outside the acceptable ranges, operator action will be governed by approved Administrative Procedures. Finally it is recognized that the Pump Inservice Test Program sets forth minimum testing requirements. Additional testing will be performed, as required, after pump.maintenance or as determined necessary by the Plant Staff. Page 3-3 Revision 3.3 Pro ram Administration The operations staff of WNP-2 is responsible for the administration and execution of the Pump Inservice Test Program.The Program will be offi-cially implemented upon the issuance of an Operating License and will govern pump testing for a 120 month period.Prior to that time, the Pro-gram will be reviewed and upgraded periodically to assure continued com-pliance with 10CFR 50:55a (g)(4).The Program may also be used as part of the pre-fuel loading surveillance testing program.

Page 3-4 3.4 Pum Reference List This list gives a brief description of each pump identified in the Pump Test Tables, Section 3.5.HPCS-P-1 The High Pressure Core Spray pump provides emergency cooling spray to the reactor core.It is capable of injecting coolant at pressures equal to or above normal reactor operating pressures. The pump can take suction from the Condensate Storage Tank or from the Suppression Pool.HPCS-P-2 This pump is dedicated to providing cooling water to the HPCS Emergency Diesel Generator, the standby power source for the High Pressure Core Spray System.HPCS-P-2 is located in the Pump House and takes suction from the spray pond.LPCS-P-1 A high capacity, low head pump, the Low Pressure Core Spray pump provides cooling spray to the reactor core upon receipt of loss of coolant sig-nal.LPCS-P-1 takes suction from the suppression pool except when test-ing to the Reactor Pressure Vessel.RHR-P-2A, 2B,.2C The Residual Heat Removal pumps are high capacity, low head pumps which.have multiple uses during normal and emergency plant conditions. Briefly the system: a)In conjunction with other systems, restores and maintains reactor*coolant inventory in the event of a LOCA b)Removes decay heat after shutdown c)Cools the suppression pool d)Can provide cooling spray to upper and lower drywell and to the wetwe 1 1 e)Can assist in fuel pool cooling f)Can provide a condensing spr ay to the reactor head g)Provides a flow path for Standby Service Water in case containment flooding is required.Pumps take suction from the suppression pool in the standby operating mode. Page 3-5 R SLC-P-1A, 18 The Standby Liquid Control pumps are used to inject negative reactivity (sodium pentaborate) into the core independently of the control rod system.Suction is obtained from a storage tank containing the sodium pentaborate solution.SW-P-1A, 18 The Standby Service Water pumps supply cooling water to separate trains of safety related equipment. The pumps take suction on their respective spray ponds but eventually discharge to the opposite pond.The two ponds are the ultimate heat sink during loss of offsite power conditions. RCIC-P-1 The turbine driven Reactor Core Isolation Cooling pump supplies coolant to the core in the event of reactor vessel isolation. It can take suc-tion from either the Condensate Storage Tank or from the suppression pool.00-P-lA, 18, 2 These pumps transfer diesel generator fuel oil from the subterranean storage tanks to the diesel's Day Tanks.Pump 2 is dedicated to the HPCS Diesel.The discharge lines of Pump 1A and 18 are cross tied, and each pump can supply fuel to either Diesel lA or 18.FPC-P-1A, 18 The Fuel Pool Circulation (FPC)pumps take suction on the spent fuel pool and discharge through the FPC heat exchangers and, during normal opera-tion, through the Fuel Pool Filter/Demineralizers. Page 3-6 R 3.5 Pump Inservice Test Tables The Test Table is the heart of the Pump Test Program.It presents a graphic display of the type and frequency of testing which the Supply System intends for its Class 1, 2 and 3 pumps.The Table incorporates the exceptions requested in Section 3.6 (Relief Requests). P~ge 3-7 R~Le end Q A N/A=NR Quarterly (92 day interval)test'nnual test Not applicable. See Relief Requests Not required IWP-4400 does not require pump speed measurement if pump is directly coupled to a constant speed motor driver.Note A: Storage Tank levels will be recorded and correlated to pressure in order to determine Pi and d P Note B: The Fuel Pool Cooling System is not expected to be in service until the first refueling outage at which time this testing program will be implemented. Inservice Test Table IWP Parameter Pump Ident.ASNE Code Inlet Discharge Differential Class Pressure, Pressure, Pressure, Pi Po AP Flowrate, Vibration, Bearing~Temperature Tb Lubrication Pump Level/Speed, Pressure N Relief Request(s) HPCS-P-1 2 N/A HPCS-P-2 3 N/A N/A 1,3 LPCS-P-1 2 N/A RHR-P-2A 2 RHR-P-28 2 R%-P-2C 2 N/A SLC-P-1A 2 N/A N/A N/A 1,2 SLC-P-18 2 N/A N/A 1,2 SW-P-lA 3 N/A N/A 1,3 SW-P-18 3 N/A N/A N/A 1,3 RCIC-P-1 2 N/A DO-P-lA 3 Q See Note A'N/A DO-P-18 3 Q See Note A Q N/A DO-P-2 FFC-P-1A 3 See Note 8 FPC-P-18 3 See Note 8 Q See Note A Q N/A N/A N/A CD Clc C CO~CD C/C 4P I O CO Page 3-9 3.6 Pump Test Pro ram Relief Requests Relief Requests identify Code requirements which are impractical for WNP-2 and provide technical justification for the requested exception. Where appropriate, they also propose alternate testing to be performed in lieu of the Code requirements. Page 3-10 R RELIEF RE(VEST RP-1~Pum (s)HPCS-P-1, HPCS-P-2, LPCS-P-1, RHR-P-2A$RHR-P-2B, RHR-P-2C, SLC-P-1A, SLC-P-1B, SW-P-1A, SW-P-1B)DO-P-1A, DO-P-1B, DO-P-2)FPC-P-1A, FPC-P-1B, RCIC-P-1, Section XI Code Requirement for which Relief is Re uested Measure bearing temperature and vibration.(IWP-3100) Bases for Re uest l.Except for FPC and RCIC pumps, these pumps are vertical turbine (" deep well")type pumps and are immersed in the fluid being pumped.This precludes measuring pump bearing vibration except for inboard bear ings.2.IWP-4300 only requires temperature measurement of"centrifugal pump bearings outside the main flow path".The outboard and intermediate bearings of all pumps are in the main flow path.Therefore, temperature measurement of these bearings is not required.The inboard bearings of the RHR pumps, LPCS-P-1 and HPCS-P-l, are cooled by the seal injection water which returns internally to the discharge flow.The inboard bearing on HPCS-P-2 (the head bearing), SW-P-1A and 18, and DO-P-1/A, 18, and 2 are cooled by the pumped fluid which returns to the discharge flow with no provision for temperature measurement. 3.Although the bearings for the FPC, SLC, and RCIC pumps are accessible, bearing housing temperature is not necessarily an accurate predictor of bearing condition. Hence, temperature measurement is an unnecessary requirement with unreliable results.Alternate Testin Pro osed 1.Except for FPC, SLC, and RCIC pumps, axial and radial vibration velocity measurement will be taken at the outboard bearing of the pump's motor.Radial vibration velocity measurements will be taken as close as practi-cal to the inboard'ump bearing.2.Vibration velocity measurements will be taken on the inboard and outboard bearings of the FPC, SLC, and RCIC pumps.3 Alert level will be 0.157~Vba 0.314 in/sec.Required action level will be Vb&0.314 in/sec.The General Machinery Vibration Severity Chart is provided for information purposes. Page 3-11 R RP-1 gualit/Safet Im act Measurement of vibration velocity provides more concise and consistent information with respect to pump and bearing condition. The usage of vibration velocity measurements can provide information as to a change in the balance of rotating parts, misalignment of bearings, worn bearings, changes in internal hydraulic forces and general pump integrity prior to the condition degrading to the point where the component is jeopardized. Bearing temperature does not always predict such problems.An increase in bearing temperature may not occur until the bearing has deteriorated to a point where additional pump damage may occur.Bearing temperatures are also affected by the temperatures of the medium being pumped, which could yield misleading results.Vibration readings are not affected by the temperature of the medium being pumped, thus the readings are more consistent. The proposed alternate testing will result in the maximum meaningful data regarding pump bearing condition. Since vibration velocity analysis is more predictive in nature than bearing temperature measurement, the alternate testing serves to increase levels of safety and quality.

Page 3-1 2 Revision RP"1 GENERAL MACHINERY VIBRATION SEVERITY CHART For use as a GUIDE in judging vibration as a warning of impending trouble.0.00 8;00 6.00 4.00 3.00 8 o o o IVI o8 8O ore co 8'OOOO 8 NIOOO 8 VIBRATION FREOUBNCY CPM 8 I o 8 o A O o VAVVCS SNO'IIN ARC POR IIII TCRCO RCAOINOS TAKCN ON TNC MACNINC STRVCTVRC R bCARINO CAP, 8 8 1.00 0.8it 0.60 o.0 40 0 0.30 a.0.20 I I-0.10 0.08 II 0.06 C 0.04 0 o 0.03 I It 0.02 0,01 0.008 0,006 0,004 0,003 0,002'dp/y Jp'ap cp~/y~avI 4p~a/@IF a Jp'-aa rp/+de b L I I V 0 C 0.001 s305D 8.8 ev co O IRD MECHANALYS15, INC.6150 Huntley Road Columbus, Ohio 43229 Figure 15.This chart can be used to cross-reference displaceIsent with freguency to deterIIIine vibration se<<r<<y'

Page 3-13 RELIEF RE(UEST RP-2 Pump(s)SLC-P-1A SLC-P-1B Section XI Code Requirement f or whi ch Rel i ef i s reques ted Measure pump inlet pressure, Pi, and pump differential pressure, 4 P.(IWP-3100)Bases for Re uest 1.The SLC pumps are positive displaceme'nt pumps which, at a constant speed, deliver essentially the same capacity at any pressure within the capabi 1-ity of the driver and the strength of the pump.The SLC pumps are di-rectly coupled to constant speed drive motors.2.Surveillance requirements specify system alignments which assure adequate HPSH for the pumps.3.There is no provision for suction pressur e instrumentation. 4.Acceptable discharge pressure and flowrate will suffice as proof of adequate suction pressure.Alternate Tes'ting Proposed Pump discharge pressure and flowrate will be measured and r ecorded during testing.uality/Safet Impact Measurement of these parameters assures acceptable level of quality and safety since inadequate suction pressure would be indicated by erratic discharge pressure indication, subnormal flow rates and increased pump vibr ation and noise.These abnormal indications will be investigated and corrected as r equired by IWP-3200. Page 3-14 Revision 2 RELIEF RE(VEST RP-3 Pump(s)HPCS-P-2 SW-P-1A SW-P-1B Section XI Code Requirement for which Relief is Re uested measure pump inlet pressure, Pi, and differential pressure, b P.(IWP-3100)Bases for Re uest (1)SW-P-lA, 18 and HPCS-P-2 are vertical turbine type pumps which are im-mersed in their water source.They have no suction line which can be instrumented. (2)Technical Specifications will state minimum allowable spray pond level to assure adequate NPSH and cooling water supplies.(3)Difference between allowable maximum pond level and minimum level is only six (6)inches of water or 0.2 psi.This small difference will not be significant to the Test Program and suction pressure will be considered essentially constant.(4)Acceptable flowrate and discharge pressure will suffice as proof of adequate suction pressure.Alternate Testin Pro osed Spray pond level and pump discharge pressure will be recorded during the test-ing of these pumps.(}ualit/Safet Im act The effect of granting this request will be to introduce an error of 0.5 ft./500 ft.=0.1%at rated discharge flow for SW-P-1A and 1B and an error of 0.5 ft/135 ft.=0.37K for HPCS-P-2.These small errors will not signifi-cantly impact the quality of test results nor jeopardize the safety of the public. Page 3-15 Revision 1 3.7 Pro osed Pum Test Flow Paths These flow paths are proposed for use during pump testing and may be used during the valve test program.The valve alignment shown on these draw-ings reflect valve position during testing.Valve position during opera-tions may be different. Surveillance procedures will define actual flow paths. REACTOR VESSEL RO-4 12 V-12 V-60 V-1 SUPPRESSION POOL 20 V-1 14 CST 10 V-1 I V-10 V-2 L CS MPCS FE-2 ST-1 ST-1 FE-7-16 24 24 16 (D%<tQ~e O 12 LPCS-P-1 12 HPCS-P-1 V-24 REFERENCES< BK R DMG.H520 HIGH PRESSURE CORE SPRAY LOP PRESSURE CORE SPRAY P8'V A 18 V-47A 20 FE-14A 18-RO-3A V-3A REACTOR VESSEL RHR-HX-1A V-24A V-172A 20 18 V-GA V-4A SUPPRESSION POOL 18 24 REFERENCES'8 R DMG.18 V-31A 14 I RO-SA RHR-P-2A 24 Q ST-2A RESIDUAL HEAT REHOVAL PCV 8 18 FE-148 V-478 20 18 REACTOR-VE55EL RO-38-V-38 V-1728 V-248 RHR-HX-1B SUPPRESS1ON POOL V-48 V-GB 18 20 REFERENCESE BR RDWG.H521 24 18 RESJDUAL HEAT REHOVAL ST-28 Q XI U I m (EA 8 0 24 RO-58 RHR-P-28 V-318 V-110B PRY C FE-14C RO-4 V-21 18 V-174 V-4C 24 REACTOR VESSEL-VENT STRA1NER SUPPRESS10N POOL REFERENCESs B 8 R DUG.MS21 18 V-110C V-31C 14 I RO-SC RHR-P-2C 24 Q ST-2C RESJDUAL HEAT REMOVAL Kl a ID A ((Q~0 PRV 0 DENIM MATER SUPPLY V-9 V-17 SLC-TK-2 REACTOR VESSEL V-lG 1 1/2 1 1/2 V-31 V-4A V-3A V-33A SLC-P-1A SUPPRESSION POOL 1 1/2 3 V-2A V-48 1 1/2 V-38 V-338 SLC-P-18 REFERENCESE 8 R RDMG.M522 3 STANDBY L I QUID CONTROL V-28 V-28 V-1B SM-P-18 20 16 RHR-V-688 RHR-HX-18 18 RHR-V-148 PUHP HOUSE B SPRAY POND 8 12 PUMP HOUSE MALL KX PC V-388 V-128 18 18 20 FE-18 V-1708 18 RO-28 PUMP HOUSE A SPRAY POND A SERV1CE MATER REFERENCESs BR RDWG.P&V V-2A V-1A 20 16 RHR-HX-1 A 18 3 2 1/2 (TYP)2 8 V-80 V-89 FLX-3 V-29 HPCS-V-2B RHR-V-68A RHR-V-14A FE-6A D/G COOLERS~UJ+a 8 O/G ENG HPCS-P-2 SM-P-1A 20 FLX-4 2 PUPfP HOUSE A SPRAY POND A FE-BA-FE-BB V-709 8 18 20 V-88 2 V-87 8 12 PC V-38A V-12A PUMP HOUSE WALL 3 3 2 FE-9 FE-1A SM-P-18 V-170A Kl (D O REFERENCESS V-4C RO-2A PUMP HOUSE 8 SPRAY POND B B E R OMG N524 SERVlCE MATER PRY G RO-12 CST V-59 V-23 V"22 V-191 RO-6 6 I FE-1 V-12 REACTOR VESSEL V-101 ST-1 SUPPRESSION POOL RCIC-P-1 V-16 8 A7~iD&C ELI lD lh O CST V-10 V-11 REFERENCESI 8 8 R DMG N519 REACTOR CORE ISOLATION COOLING PgV H V-43 V-12 1'1/2 V-11 V-10 DO-P-1C DO-TK-4C DO-TK-2C II 1 1/2 V-701 B DO-TK-38 V-408 V-48 V-28 V-18 1/2 DO-P-18 1/2 1 1/2 V-5.V-44 DO-TK-18 V-701 A DO-TK-3A REFERENCES'R RDIIG H512 V-40A V-4A DlESEL FUEL OIL V-2A V-1A.1/2 DO-TK-1A II II DO-P-1A X7 C7 CD CD (CQ CD 0 4 FPC-TK-1A 4 FPC-TK-18 8 V-145A V-146A 8 V-745B V-1468]r 10 FE-16 4 V-130 8 10 10 Gg~DIFFUSERS~ FUEL PIT V-142 8 Cl V-187A ST-1A FPC-P-1A V-I 12A V-1 16A FPC-MX-1A 8 RO-6 V-147 10 V-11BA 6 8 V-175 V-140 8 y V-1818 D ST-78 FPC-P-1B V-712B Gg V-1168 FPC-MX-1B V-724 V-172 V-184 REFERENCES B 8 R DMG.H526 FUEL POOL COOLING V-118B 6 V-173 Page 3-26 R 3.8 Records of Inservice Tests Records of Pump Inservice Test results will be maintained in accordance with Article IWP-6000 of the Code.A file wi 11 be established for each pump and will include: 1)Pump identification by equipment piece.number, manufacturer, and ser ial number.2)Inservice test plans.This may be by reference to the surveillance test procedure by which the pump is tested.3)Summaries of corrective action.The Pump Inservice Test Program, associated surveillance test procedures and results will be kept at the WNP-2 plant site.For informational purposes, a sample pump test data sheet is provided. Page 3-27 Revision 2 HYDRAULIC DATA SAMPLE DATA SHEET PUMP OPERABILITY EPN LPCS-P-1 Item Inst.No.Calib.Void Date I Measured Value Init.Suc.Press Before Start PSIG LPCS-PI-1 Suet.Press (At Test Flow)PSIG LPCS-PI-1 Disch.Press (At Test Flow)PSIGI LPCS-PI-2 Diff.Press, PSI Flow, gpm Fluid Temp., oF MECHANICAL KATA Item Pmp.Brg.Temp.,'F Inbd.(Obd.)Dvr.Brg.Temp.,'F (Inbd.)(Obd.)Pmp.Lubrication: Sat.vr.Lubrication: Sat.ELECTRICAL DATA Inst.No.N/A N/A W130 W 28 W 29 Unsat.Unsat.Calib.Void Date N/A N/A N/A Pump Speed Inst.No.Measured Value Init.N/A N/A RPM Col Void Bus Voltage: Inst.No.Calib.Void Date VAC Motor Current: Inst.No.LPCS-AM-1 Calib.Void Date Amp Completed by Date mme ACCEPTANCE CRITERIA Parameter Flow Delta P(l)Suet.Press(1)Bearing Temp.Value Value Refer.I Meas.Hi Lo Alert Range Hi Lo Action Range Shift Mgr.Init./Date Reviewed by: Date/Time (l)If deviations fall within the ALERT RANGE, the test frequency is increased to once each 45 days;if within the ACTION RANGE, the pump shall be declared inoperable and the deviation investigated and/or cor'rected. ~RRRRRRRRRRRRRRRR EEEEEEEEE~RRRRRR~RRRRRR RRRRRRRmm aaaaaaH raraa~55555ia~RRRRRRRR EEEEEEEEEEEE raaaaaaaeaa ~'~I.n~ESSES aaaasaaaaaaaaaaaaaaaa ~RRRRRRRRKIIIIIRRRRRRRRRRRRRRRRRRRR w5%h~%%%%%RRRRRRReeRRRRRRR ari~a KLViFsaÃRRRRRRR RRRRRR RRRRRRRRR~RRReeORRRRRRRRR ~SEERS s~a~E EEEREEJIEIIEEE EEEEEEEE~Elaaasasa Ea KES%aaaa RRRR R~ima.RRRRRRLIBIIJKRR RRRR RRSRRR R..RRRRRrmR R mary~RRR ss as EEREREEREEREEEE ~Esaaaa EEEEREEEEEEEEEE ~Easasssaaaaaaasasssass ~RRRRR RRRRRRR~aaaaaaaaaaaaaaaaaaaaaasasasasa aaRKKWRRNRRKKRRRRKRRR%%% Page 4-1 R 4.0 WNP-2 Valve Inservice Test Program 4.1 Introduction I Washington Public Power Supply System Nuclear Project Unit 2 (WNP-2)is a Boiling Water Reactor constructed in compliance with the ASME Boiler and Pressure Vessel Code.Section XI of the Code requires periodic testing of certain safety related valves in order to verify their operability and leak tight integrity. The WNP-2 Valve Inser vice Test Program satisfies these requirements and conforms to FSAR commitments and Technical Speci-fications for ASME valve testing.The Program will detect potentially adverse changes in the mechanical condition of valves within the scope of Section XI, Subsection IWV of the Code.The scope includes all valves"which are required to perform a specific function in shutting down a reactor to the cold shutdown condi-tion or in mitigating the consequences of an accident". Many valves used in normal shutdown operations are not necessarily"required" nor would they necessarily be available for that purpose.Hence, the scope of IWV is restricted to valves required to shutdown the reactor in emergency situations and to mitigate accident consequences. The Code recognized that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements. The relief requests for the Valve Inser vice Test Program (Section 4.5)identify testing impracticalities, provide technical basis for the request and propose alternate testing where warranted. The Supply System is confident that the WNP-2 Valve Inservice Test Pro-gram complies with the intent of all applicable Codes, Regulations(1), and Guidelines(2) and contributes to ensuring the safety of the general public.(1)10CFR 50:55 a(g)(2)(2)NRC Staff'uidelines for excluding exercising (cycling)tests of certain valves during Plant operations. Page 4-2 Revision 24.2 Pro ram Im lementation The Valve Inservice Test Program will be executed as part of the normal plant surveillance routine.Two types of tests will be conducted as part of this Program: I)Valve Operability Tests 2)Valve Leak Rate Tests Valve Operability Tests are only applicable to active valves of cate-gories A, B, C, and D.These valves are listed in the Valve Test Tables provided in Section 4.4 of this Program.The Valve Operability Tests based on the requirements specified in Section XI, Subsection IWV of the Code will verify 1)the valve responds to control commands including its failsafe response if applicable, 2)the valve stroke time is within specific limits and, 3)remote position indi-cation accurately reflects the observed valve position.Baseline data for stroke times will be obtained from initial Valve Operability Tests.The initial Valve Operability Tests will meet the requirements for pre-service testing (IWV-3100). The limiting values of test results such as stroke times and leakage rates are stated in the test procedures. Fail safe valves as identified by the valve test tables will be tested by observing the valve operation upon loss of electrical, pneumatic or hydraulic actuating power.In most cases, loss of electrical power causes loss of actuating fluid and can be accomplished using normal con-trol circuits.Subsubarticle IWV-3420 of the Code specifies that valve leak rate tests are required for category A valves.At WNP-2 there are three divisions of category A valves: Division I-Those valves listed in the WNP-2 FSAR, Table 6.2-16, as being containment isolating valves.These valves will be leak tested using the requirements of 10CFR50, Appendix J.The Appendix J require-ments specifically address test and acceptance criteria for valves func-tioning as containment isolation valves.Division II-Those valves not listed in the FSAR, but listed in the Valve Test Tables, Section 4.4.These valves will be leak tested using the requirements of IWV-3420.Division III-Those valves listed not only in the FSAR, but also listed in the WNP-2 Technical Specification as being reactor coolant system pressure isolation valves.These valves shall be leak tested using the requirements of both 10CFR50, Appendix J and IWV-342g.The category A valves identified in this program and their associated leak testing requirements are implemented using a unified leak testing program which will maximize compliance with the various requirements and commitments, provide consistency in test methodology and reduce duplica-tion of effort. Page 4-3 Revision Valves in the Valve Test Program will be tested according to detailed procedures. The procedure will include, as a minumum: a)Statement of Test Purpose.This section will identify test objectives, reference applicable Technical Specifications and note the operating modes for which the test is appropriate. b)c)Prerequisites for Testing.System valve alignment and additional instrumentation (e.g., stop watch)will be noted.Identification numbers, range and calibration verification of additional instrumentation will be recorded.Test Instructions. Directions will be sufficiently detailed to assure completeness and uniformity of testing.Instructions will include provisions for returning the system to its normal standby configuration following testing.d)Acceptance Criteria.The ranges within which test data will be considered acceptable will be established by the Supply System and included in the test procedure. In the event that the data fall outside the acceptable ranges, operator action will be governed by approved Administrative Procedures. Finally it is recognized that the Valve Inservice Test Program sets forth minimum testing requirements. Additional" testing will be performed, as required, after valve maintenance or as determined necessary by the Plant Staff.4.3 Pro ram Administration The Valve Inservice Test Program will be administered in a manner analogous to the Pump Inservice Test Program.4.4 Valve Test Tables The Valve Test Tables are the essence of the Supply System's Program to meet ASME Section XI, Subsection IWV requirements. The Tables only in-clude active valves which are required to operate in order to safely shutdown the reactor or mitigate the consequences of an accident.Pas-sive Category A valves required to be leak tested are listed in the FSAR as described in Section 4.2.The Tables reflect the positions taken in support of the relief requests.Unless noted otherwise the following requirements apply to valves listed in the Valve Test Tables: a.All valves with remote position indicators shall be tested in accordance with IWV-3300'. All valves with fail safe actuators shall be tested in accordance with IWV-3415 at the fr equency noted in the Tables.c.As described in Section 4.2 of this program, all valves identified as category A will be leak tested in accordance with IWV-3420 requirements or 10CFR50, Appendix J requirements or both. Page 4-4 R To Aid the in the interpretation of the Tables, brief explanations of the Table headings and abbreviations are provided.(I)Valve Number Each piece of equipment in the plant has a unique"tag" number which identifies the system to which the equipment belongs, the type of equipment (flow control valve=FCV, relief valve=RV, rupture disc=RD, etc.), and a unique serial number.(2)Class ASME Code Class per Section III of the ASME Boiler and Pressure Vessel Code.These are roughly equivalent to the safety'classes defined in Chapter 3 of the FSAR.(3)Coordinates The specific coordinates of each valve are supplied to facilitate location of the valves on the flow diagram provided.(4)Valve Category Categories are defined by ASME Section XI, subsection IWV.Each valve has specific testing requirements which are determined by the category to which it belongs.The letter"F" in the column for category"A" identifies those valves listed in WNP-2 FSAR, Table 6.2-16 and will be leak tested using lOCFRSO, Appendix J requirements. The letter"T" in the column for category"A" identifies those valves listed not only in the FSAR, but also in WNP-2 Technical Specifications and will also be leak tested using the requirements of IWV.NOTE: The designation of Category A valves with a"T" or"F" is intended to be an in-formational courtesy.A change to the referenced portion of the Technical Speci-fication and FSAR'ay not necessitate a revision to this Program. Page 4-5 Revision 2 (5)Size Nominal pipe diameter to which the valve connects is given in inches.(6)~Vg T The following abbreviations are used to describe valve type: BF=Butterfly valve CK=Check valve DIA=Diaphragm valve GB=Globe valve SC=Stopcheck valve GT=Gate Valve RD=Rupture disc.RV=Relief Valve S/R=Safety/Relief Valve SV=So 1 eno i d Valve (6)~At T The following abbreviations are used to describe actuator types.Valves may be actuated in more than one way.AO=Air operated HO=Hydraulic operated MAN=Manually operated MO=Motor operated SA=Self actuated (actuated by a change in system parameters such as flow or pressure, e.g., check and relief valves).SOL=Solenoid operated (8)Normal/Failed Position This column identifies the valve's normal position and failed position.This is used to identify valves with fail safe actuators for testing per IWV-3415: NO=Normally Open NC=Normally Closed FO=Failed Open NA=Not Applicable FC=Fail ed Close FAI=Fail As Is Page 4-6 Revision 2 (9)~T<<D This column defines the operating modes as defined by the Technical Specifications, during which the valve may be safelytested.See below for the definition of"all,""CSD" and"Refuel." Leceend Meaninc[Al 1 Testing is approved during all operating modes and will be conducted on a quarterly basis, as permitted by plant status.CSD Cold shutdown.Guidance for Inservice valve testing at cold shutdown is: Valve testing should commence within 24 hours after cold shutdown is achieved and con-tinue until complete or until plant is ready to return to power.Completion of all valve testing is not a prerequisite to return to power.Any testing not completed at one cold shutdown should be performed during the subsequent cold shutdowns to meet the Code specified testing frequency. Refuel Test will be conducted during refueling outages but at least every two years.Cer-tain work which is nominally scheduled for a refueling outage may be performed at other times when plant conditions permit.The two year minimum frequency will be maintained. Page 4-7 Revision 2 IWV-3620 Test frequency will be according to vendor specifications. (10)Test Testing requirements identified for the valve are identified here.S/E Stroke exe}cise;valve timing not relevant.S/T Stroke time;valve must meet stroke timing requirements specified in the test procedure. Bench Test Relief valves will be tested in accordance with IWV-3500 requirements. , IWV-3620 Rupture disc will be tested in accordance with Section XI, Subsection IWV, paragraph 3620.(12)Notes This column is used to provide reference to explanatory notes located at the end of the Valve Test Tables.(13)Re uests for Relief This column is used to cross reference documentation which requests waiver of certain code requirements. A valve may have more than one associated relief request.

System Name DIESEL OIL AND NISC.DO Dwg.No.H 512 Page 1 of 1 Valve Number a ve Cate<~or Size Class Coordinates ~B CCC Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief DO-V-IA 3 D3 X X 1 1/2 NC/NA ALL S/E DO-V-IB 00-V-10 3 03 H5 X X X X 1 1/2 1 1/2 CK SA SA NC/NA ALL S/E NC/NA ALL S/E 00-V-40A 3 E3 1 1/2 SOL NC/FC ALL S/E 00-V-40B 3 E3 1 1/2 SV SOL NC/FC ALL S/E 00-V-43 H6 1 1/2 SV SOL NC/FC ALL S/E System Name REACTOR CORE ISOLATION COOLING SYSTEM RCIC Dog.No.H 519 Page 1 of 2 Valve Number a ve tatetaoorr Size Class Coordinates A 8 C D Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief RCIC-V-1 2 Ell X 3 GT HO NO/FAI ALL S/E RCIC-V-8 1 F6 GT HO NO/FAI ALL S/T RCI C-V-10 2 RCIC-V-11 2 RCIC-V-13 1 814 813 H7 X X GT GT HO NO/FAI ALL S/T NC/NA ALL S/E NC/FAI CSD S/T lk RCI C-V-19 2 E7 GB HO NC/FAI ALL S/T 4, 5 RCIC-V-21 2 RCIC-V-22 2 RCIC-V-28 2 EB JB X X F X 1 1/2 GB CK MO NC/NA ALL S/E NC/FAI ALL S/T NC/NA'LL S/E RCI C-V-30 2 C7 X X NC/NA ALL S/E RCIC-V-31 2 RCIC-V-40 2 RCIC-V-45 2 C7 Fll F X 10 GT GB HO HO NC/FAI ALL S/T NC/NA ALL S/E NC/FAI ALL S/T 2, 4 RCIC-V-46 2 Fll GB HO NC/FAI ALL S/T RCIC-V-59 2 J9 GT MO NC/FAI ALL 5/T System Name REACTOR CORE ISOLATION COOLING RCIC Dwg.No.H 519 Page 2 of 2 a ve Valve~Cate or Size Number Class Coordinates A B C 0 Inches orma Valve Actuator Failed Test T e T e Position Ourin Test Notes Requests For Relief RCIC-V-63 1 H3 F 10 GT HO NO/FAI ALL S/T RCIC-V-65 1 RCIC-V-66 1 H6 X X T X AO/SA NC/NA CSO S/E AO/SA NC/NA CSD S/E 1b, 2 1b 4, 5 RCI C-V-68 2 E7 10 GT NO/FAI ALL S/T RCIC-V-69 2 RCIC-V-76 1 RCIC-V-086 2 D7 A13 X X 1-1/2 GT GB HO NO/FAI ALL S/T NO/FAI ALL S/T NC/NA ALL S/E RCIC-V-110 2 E7 GT HO NO/FAI ALL S/T RCIC-V-111 2 E7 RCIC-V-112 2E7 X X X X CK NC/NA ALL S/E NC/NA ALL S/E 2, 4a 2, 4a RCIC-V-113 2 E6 GT NO/FAI ALL S/T RCIC-RO-1 2 D11 10 RO NC/NA IWV-3620 IWV-3620.2 RCIC-RD-2 2 C12 10 RD NC/NA IKV-3620 IWV-3620 2 RCIC-RV-17 2 RCIC-RV-19 2 C13 09 1 x 1 RV 1 x 1 1/2 RV NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST System Name LOW PRESSURE CORE SPRAY SYSTEM LPCS Owg.No.H520 Page 1 of 1 Valve Number a ve tatetaoorr Size Cl ass Coordinates A B C 0 Inches orma Valve Actuator Failed Test T e T e Position Ourin Test Notes eques s For Relief LPCS-V-1 2 Oll F 24 GT HO NO/FAI ALL S/T LPCS-V-3 2 B13 X X 16'CK SA NC/NA ALL S/E LPCS-V-5 1 Gll 12-GT HO NC/FAI ALL S/T 4, 5 LPCS-V-6 1 Hg T X 12 AO NC/NA CSO S/E lb 4, 5 LPCS-V-12 2 F14 12 GB HO NC/FAI ALL S/T LPCS-V-33 2 C12 X X 1 1/2 CK NO/NA ALL S/E LPCS-V-34 2 LPCS-FCV-ll 2 C12 B13 X X 1 1/2 GB NC/FAI SC SA/HAN NO/NA ALL S/E ALL S/T LPCS-RV-18 2 LPCS-RV-31 2 F12 C12 F X F X 11/2x2 RV RV SA NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST System Name HIGH PRESSURE CORE SPRAY SYSTEH HPCS Owg.No.H520 Page 1 of 1 Valve Number a ve Cat~e~or Size Class Coordinates ~W~Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief HPCS-V-1 2 C6 X 14 GT HO NO/FAI ALL S/T HPCS-V-2 2 HPCS-V-4 1 HPCS-V-5 1 C6 G7 HB X X T X 20 12 12 AO NC/NA ALL S/E NC/FAI ALL S/T NC/NA CSD S/E 1b 4, 5 4, 5~HPCS-V-6 2 X X 1 1/2 SC SA/MAN NO/NA ALL S/E HPCS-V-7 2 HPCS-V-10 2 HPCS-V-ll 2 C5 E3 X X 1 1/2 10 10 CK GB GB HO NO/NA ALL S/E NC/FAI ALL S/T NC/FAI ALL S/T HPCS-V-12 2 B5 GT NC/FAI ALL S/T HPCS-V-15 2 07 18 GT HO NC/FAI ALL S/T 4-HPCS-V-16 2 E6 X X 24 NC/NA ALL S/E HPCS-V-23 2 12 GB NC/FAI ALL 5/T HPCS-V-24 2 85 X X 16 NC/NA ALL S/E HPCS-RV-14 2 HPCS-RV-35 2 C6 C4 F X F X 1X1 1x2 RV RV NC/NA REFUEL BENCH C TEST NC/NA REFUEL BENCH TEST a CD&C IQ~ID I M System Name RESIDUAL HEAT REMOVAL SYSTEM RHR Dwg.No.H521 Page 1 of 6 Valve Number a ve Category Size Class Coordinates ~~6 Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief RHR-V-3A SH 1 HIO X 18 GT HO NO/FAI ALL S/T RMR-V-38 2 RHR-V-4A 2 RHR-V-48 2 RHR-V-4C 2 RHR-V-6A 2 RHR-V-68 2 SH 2 Jg SH 1 B6 SH 2 812 SH 2 811 SH 1 BB SH 1 87 18 24 24 24 18 18 GT GT GT GT GT GT HO HO HO HO HO NO/FAI ALL S/T NO/FAI ALL S/T NO/FAI ALL S/T NO/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T RHR-V-8 SH 1 E6 20 GT MO NC/FAI CSD S/T lc 4, 5 RHR-V-9 RHR-V-16A 2 SH 1 DS SH 1 H7 20 16 GT HO GT.HO NC/FAI CSD S/T NC/FAI ALL S/T 1c 4, 5 RHR-V-168 2 RHR-V-17A 2 RHR-V-178 2 RHR-V-21 2 SH 2 DIO SH 1 H6 SH 2 011 SH 2 E7 16 16 16 18 GT GT GT GB HO HO HO NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T 4 R7 M CD Dt C Cl~Q System Name RESIDUAL HEAT REMOVAL SYSTEH RHR Dwg.No.H521 Page 2 of 6 a ve Valve Cateqory Size Number Class Coordinates A lI PD Inches orma Valve Actuator Fai led Test T e T e Position Durin Test Notes eques s For Relief RHR-V-23 1 SH2 T 6 K13 GB HO NC/FAI CSO S/T lc 4, 5 RHR-V-24A 2 RHR-V-248 2 RHR-V-27A 2 RHR-V-278 2 SH 1 EIO SH 2 C10 SH 1, D7 SH 2 010 18 18 GB GB GT GT HO HO HO NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T RHR-V-31A 2 SH 1 D14 X X 18 NC/NA ALL S/E RHR+318 2 RHR-V-31C 2 RHR-V-40 2 RHR-V-41A 1 RHR-V-418 1 RHR-V-41C 1 RHR-V-42A 1 RHR-V-428 1 SH 2 C3 SH 2 D5 SH 2 G4 SH 1 GS SH 2 G13 SH 2 E13 SH 1 G7 SH 2 G12 X X X X T X T X T X 18 18 14 14 14 14 14 GB GT GT SA HO AO AO AO HO HO NC/NA ALL S/E NC/NA ALL S/E NC/FAI ALL S/T NC/NA CSD S/E NC/NA CSO S/E NC/NA CSO S/E NC/FAI ALL 5/T NC/FAI ALL S/T 1b 1b Ib 4, 5 4, 5 4, 5 4, 5 4, 5 System Name RESIOUAL HEAT REMOVAL SYSTEM RHR Dwg.No'.M521 Page 3 of 6 Valve Number a ve Cateq~or Size Class Coordinates ~C II Inches orma Valve Actuator Failed Test T e T e Position Ourin Test Notes eques s For Relief RHR-V-42C 1 SH 2 Ell T 14 GT MO NC/FAI ALL S/T 4, 5 RHR-V-46A 2 RHR-V-46B 2 RHR-V-46C 2 SH 1 C10 SH 2 C6 SH 2 EB X X X X X X NC/NA NC/NA NC/NA ALL S/E ALL S/E ALL S/E RHR-V-47A 2 RHR-V-478 2 RHR-V-48A 2 RHR-V-488 2 RHR-V-49 2 SH 1 J13 SH 2 J3 SH 1 Jll SH 2 JB SH 2 G4 18 18 18 18 GT GT GB GB GT MO MO MO NO/FAI ALL 5/T NO/FAI ALL S/T NO/FAI ALL S/T NO/FAI ALL S/T NC/FAI ALL S/T RHR-V-50A 1 RHR-V-50B 1 SH 1 F5 SH 2 F13 T X T X 12 12 CK AO NC/NA NC/NA CSO S/E CSD S/E lb lb 4, 5 4, 5 RHR-V-53A 1 SH 1 E6 12 GB NC/FAI CSO S/T lc 4, 5 RHR-V-538 1 RHR-V-60A 2 SH 2 Ell SH 1 Hll 12 3/4 GB SV MO SOL NC/FAI NC/FC CSO S/T ALL S/E lc g, 5 RHR-V-608 2 SH 2 HB 3/4 SV SOL NC/FC ALL S/E System Name RESIDUAL HEAT REMOVAL SYSTEM RHR Owg.No.M521 Page 4 of 6 Valve Number a ve Category Size Class Coordinates l~C II Inches orma Valve Actuator Failed Test Stroke T e T e Position Durin Test Time Notes equests For Relief RHR-V-75A 2 SH 1 Gll X 3/4 SV SOL NC/FC ALL S/E RHR-V-758 2 RHR-V-84A 2 RHR-V-84B 2 RHR-V-84C 2 SH 2 G9 SH 1 014 SH 2 83 SH 2 C6 X X X X X X 3/4 1 I/2 1 1/2 1 1/2 CK SOL NC/FC ALL S/E NC/NA ALL S/E NC/NA ALL S/E NC/NA ALL S/E RHR-V-85A 2 SH I 014 X X 1 I/2 SC SA/MAN NO/NA ALL 5/E RHR-V-85B 2 RHR-V-85C 2 SH 2 B3 SH 2 C6 X X X X 1 1/2 1 1/2 SC SA/MAN NO/NA SC SA/MAN NO/NA ALL S/E ALL S/E RHR-V-89 2 RHR-V-101A 2 SH 2 J10 SH 1 E12 X X X X 14 AO NC/NA ALL S/E NC/NA ALL S/E RHR-V-1018 2 RHR-V-103A 2 RHR-V-103B 2 SH 2 G3 SH 1 E12 SH 2 G4 X X X X X X CK NC/NA NC/NA NC/NA ALL S/E ALL S/E ALL S/E RHR-V-115 2 RHR-V-116 2 SH 2 JB SH 2 J9 14 14 GT GB MO MO NC/FAI ALL S/T NC/FAI ALL S/T System Name RESIDUAL HEAT REMOVAL SYSTEM RHR Dwg.No.H521 Page g of a ve Valve Category Size Number Class Coordinates 7M%5 Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes equests For Relief RHR-V-124A 2 SH 1 814 GB HO NC/FAI ALL S/T RHR-V-124 B 2 RHR-V-125A 2 RHR-V-125 B 2 RHR-V-134A 2 RHR-V-134B 2 SH I C12 SH 2 04 SH 1 03 SH 1 F14 SH 2 F5 1-1/2 1-1/2 1-1/2 GB GB GT GB GB HO HO NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T RHR-V-182 2-RHR-V-209 1 SH 2 J8 SH 1 05 T X 3/4 3/4 SV SOL NO/FO ALL S/E NC/NA REFUEL S/E 4,5,8 RHR-FCV-64A 2 RHR-FCV-64B 2 RHR-FCV-64C 2 RHR-RV-IA 2 RHR-RV-IB 2 SH 1 C12 SH 2 C6 SH 2 E6 SH 1 H13 SH 2 H5 F X 3/4 x 1 1/2 F X 3/4 x 1 1/2 GB GB GB RV RV HO HO NO/FAI ALL S/T NO/FAI ALL S/T NO/FAI ALL S/T NC/N REFUEL BENCH TEST NC/N REFUEL BENCH TEST 4,5 RHR-RV-5 2 RHR-RV-25A 2 SH 1 CB SH 1 E12 F X F X 1x2 1x2 RV RV NC/NA REFUEL BENCH TEST NC/N REFUEL BENCH TEST 0 fga gga C ggg~fgg System Name RESIDUAL HEAT REHOVAL SYSTEH RHR Dwg.No.H521 Page 6-of'Valve Number a ve Categ~or Size Class Coordinates ~I~Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief RHR-RV-25B 2 SH2 F X 1x2 C10 RV SA NC/NA REFUEL BENCH TEST RHR-RV-25C 2 RHR-RV-30 2 RHR-RV-36 2 RHR-RV-BBA 2 RHR-RV-888 2 RHR-RV-BBC 2 SH 2 EB SH 2 C4 SH 1 F12 SH 1 C7 SH 2 88 SH 2 08 F X F X F X F X F X F X 1x2 1 x 2 6x8 3/4 x 1 3/4 x 1 3/4 x 1 RV RV RV RV RV NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST System Name STANDBY LI UID CONTROL SLC Dwg.No.H522 page l of Valve Number a ve Cateqory Size Class Coordinates ~I HD Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes equests For Relief SLC-V-1A 2 E4 X 4 GB HO NC/FAI ALL S/T SLC-V-18 2 HO NC/FAI ALL S/I'LC-V-4A 1 SLC-V-4B 1 FB DB X 1-1/2 X 1-1/2 SHEAR SQUIBB NC/NA REFUEL IMV PLUG 3610 SHEAR SQUIBB NC/NA REFUEL INV PLUG 3610 4 SLC-V-6 SLC-V-7 SLC>>V-33A 2 Fll F13 F7 X X F X X X l-l/2 1-1/2 l-l/2 CK SA NC/NA REFUEL S/E NC/NA REFUEL S/E NC/NA ALL S/E 2, 4 SLC-V-33B 2 07 X X 1-1/2 NC/NA ALL S/E SLC-RV-29A 2 SLC-RV-29B 2 E6 06 lx2 1 x 2 RV NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST A gg fga gaa C Cl~ggg System Name REACTOR WATER CLEANUP RWCU Dwg.No.H523 Page 1 of 1 Valve Number a ve Cateq~or Size Class Coordinates A B 0 5 Inches orma Valve Actuator Failed Test T e T e Position Burin Test Notes equests for Relief RWCU-V-1 1 F15 F 6 GT HO NO/FAI ALL 5/T RKCU-V-4 E15 GT HO NO/FAI ALL S/T RWCU-V-40 1 H11 GT NO/FAI ALL S/T System Name STANDBY SERVICE WATER SW Dwg.No.H524 Page 1 of 3 Valve Number MPCS-V-28 3 Sh G6 X X 8 a ve~tate or Size Class Coordinates A 8 C 0 Inches orma Valve Actuator Failed Test T e T e Position Durin Test CK SA NC/NA ALL S/E Notes equests For Relief RHR-V-68A 3 RHR-V-688 3 SW-V-1A SM-V-18 SW-V-2A SW-V-28 SM-V-4A SW-V-48 SM-V-4C SW-V-12A 3 SW-V-128 3 SM-V-24A 3 SW-V-248 3 SW-V-24C 3 SW-V-29 D13 Sh 2 G14 Sh 2 GS Sh H6 Sh G6 h E9 Sh 2 G9 h Fl Sh G3 h 2 G3 Sh 1 G9 Sh F10 Sh 2 K10 Sh 1 G6 X X X X 16 16 20 20 20 20 18 18 GT GT CK BF BF GT GT GT GT GT GT GT GT BF NO/FAI ALL S/T NO/FAI ALL S/T NC/HA ALL S/E HC/HA ALL S/E.3 NC/FAI ALL S/T NC/FAI ALL S/T NO/FAI ALL 5/T NO/FAI ALL S/T NO/FAI ALL S/T N NC/FAI ALL S/T NC/FAI ALL S/T NO/FAI ALL S/T HO/FAI ALL S/T HO/FAI ALL S/T HC/FAI ALL S/T System Name STANDBY SERVICE MATER SW Dwg.No.N524 H607 Page 2 of 3 Valve Number a ve~Cate or Size Class Coordinates A 8 C D Inches orma Valve Actuator Failed Test T e T e Position Durin Test'otes eques s For Relief SW-V-34 3 C11 X 1 1/2 GB SV NO/FO ALL S/T SM-V-44 SM-V-54 SM-V-69A 3 SW-V-698 SW-V-70A h E9 h F7 h G3 F3 h G2 18 18 18 GT GT GT GT GT NO/FAI ALL S/T NC/FAI ALL 5/T NO/FAI ALL S/T NO/FA I ALL S/T NO/FAI ALL S/T SM-V-708 SM-V-90 SW-V-92 9 o SW-V-201 3 9 o SM-V-202 3 9 o SM-V-203 3 gH, h SW-V-204 3 9 SW-V-206 3 9 SW-V-207 3 g o SK-V-208 3 F3 H9 C14 C14 C14 C14 815 815 815 X X 1&1/2 1/2 1/2 1/2 1/2 1/2 1/2 GT GT SV SV SV NO/FAI ALL S/T NC/FAI ALL S/T NC/NA ALL S/E SOL NC/FC ALL S/E NC/NA ALL S/E NO/NA ALL S/E SOL NO/FO ALL S/E SOL NC/FC ALL S/E NC/NA ALL S/E NO/NA ALL S/E System Name STANDBY SERVICE MATER SW Dwg.No.I624 H607 Page Valve Number Dwg H607, Sh 2 SM-V-209.3 815 X 1/2 a ve Cat~eo~r Size Class Coordinates A (WC 6 Inches Valve Actuator T e T e orma Failed Test Position Durin Test SV SOL NO/FO ALL S/E Notes equests For Relief Dwg N , Sh SW-V-210 3 1/2 SV SOL NO/FO ALL S/E Dwg H60, Sh 2 SM-V-211 3 Dwg , h CHS-V-212 3 Dwg H607, Sh 2 SM-V-213 3 Dwg SW-V-214 3 811 A14 813 1/2 1/2 1/2 SV SV SV BF SOL SOL NC/FC ALL S/E NO/FO ALL S/E NC/FO ALL S/T SOL NC/FC ALL S/E SM-V-215 SW-V-216 SM-V-217 SW-V-75A 3 SW-V-758 3 SW-V-187A 3*SW-V-1878 3*SW-V-188A 3 SW-V-1888 3 SM-RV-001A 3 SM-RV-0018 3 h 2 HB Sh 2 HB Sh A13 Sh 2 814 h G14 Sh 2 C13 h H13 h 2 D12 Sh C14 Sh 2 F14 X X X X BF BF BF GB GB GT GT GT GT RV RV AO AO NC/FO ALL S/T NC/FO ALL S/T NC/FO ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL 5/T NC/FAI ALL S/T NC/NA ALL BENCH TEST NC/NA ALL BENCH TEST 5, 3 5, 3 System Name REACTOR CLOSED COOLING RCC Owg.No.H525 Page 1 of 1 a ve Valve Cat~e~or Size Number Class Coordinates ~~C D Inches Norma Valve Actuator Failed Test T e T e Position Ourin Test Notes equests For Relief RCC-V-5 2 D10 F 10 GT HO NO/FAI CSD S/T Id RCC-V-21 2 D10 10 GT HO NO/FAI CSD S/T Id RCC-V-40 2 RCC-V-104 2 RCC-V-129 3 D10 E10 E5 10 10 GT GT GT HO HO MO NO/FAI CSO S/T NO/FAI CSO S/T NO/FAI ALL S/T 1d 1d RCC-V-130 3 E6 GT HO NO/FAI: ALL S/T RCC-V-131 3 E6 GT HO NO/FAI ALL S/T RCC-RV-34A 3 RCC-RV-348 3 F5 X X X X 3/4 x 1 3/4 x 1 RV RV NC/NA ALL BENCH TEST NC/NA ALL BENCH TEST System Name FUEL POOL COOLING SYSTEM FPC Dwg.No.M526 Page 1 of 1 Valve Number a ve~Cate or Size Class Coordinates A B C D Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes equests For Relief FPC-V-112A 3 012 X 6 CK SA NO/NA ALL S/E FPC-V-112B 3 FPC-V-153 2 012 Bll GT MO NO/NA ALL S/E NC/FAI g ALL S/T FPC-V-154 2 Bll GT MO NC/FAI ALL S/T FPC-V-156 2 FPC-V-172 FPC-V-173*Cll C9 CB GT GT GT HO HO MO NC/FAI ALL S/T NO/FAI ALL S/T NO/FAI ALL S/T 5, 3 5, 3 FP C-V-175 C9 GT NC/FAI ALL S/T 5, 3 FPC-V-181A

• D14 GT HO NO/FAI ALL S/T 5, 3 FPC-V-181B
• D14 GT NO/FAI ALL S/T 5, 3 FPC-V-184*C9 X GT MO NO/FAI ALL S/T 5, 3 FPC-RV-117A 3 FPC-RV-117B 3 Dll Cll 3/4 x 1 3/4 x 1 RV RV NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST System Name CONTROL ROD DRIVE Dwg.No.H528 Page 1 of 1 Valve Number a ve Categ~or Size Class Coordinates l~C 6 Inches orma Valve Actuator Failed Test T e T e Position Dur in Test Notes eques s For Relief CRD-V-11 2 F6 CRD-V-10 2 K6 X 1 GB AO GB AO NO/FO ALL S/T NO/FO ALL S/T CRD-V-110A 2 D13 1-1/2 SV SOL NO/FO CSD S/E la CRD-V-110B 2 013 1-1/2 SV SOL-NO/FO CSD S/E la CRD-V-ill 2 013 X X 1-1/2 CK N C/NA CSD S/E r la CRD-V-180 2 CRD-V-181 2 K6 F6 GB GB AO AO NO/FO ALL NO/FO ALL S/T S/T System Name HAIN STEAH SYSTEH HS Dwg.No.H529 gogo t or Valve Number a ve~Cate or Size Class Coordinates A 8 C 0 Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief HS-V-16 1 813 F 3 GT HO NC/FAI ALL 5/T HS-V-19 814 GT NC/FAI ALL 5/T HS-V-22A 1 F12 26 GB AO NO/FC ALL 5/T HS-V-228 1 E12 26 GB AO-NO/FC ALL 5/T HS-V-22C 1 F5 26 GB AO NO/FC ALL S/T HS-V-22D 1 E5 26 GB AO NO/FC ALL 5/T HS-V-28A 1 HS-V-288 1 HS-V-28C 1 F13 E13 F4 26 26 26 GB GB GB AO AO AO NO/FC ALL 5/T NO/FC ALL 5/T NO/FC ALL 5/T4 HS-V-28D 1 E4 26 GB AO NO/FC ALL 5/T HS-V-37 5ERIES HS-V-38 SERIES HS-V-67A 1 C6-Cll C6-Cll F13 X X X X 10 10 l-l/2 GT HO NC/NA CSD S/E NC/NA CSD 5/E NC/FAI ALL 5/T le le HS-V-678 1 F13 1-1/2 GT NC/FAI ALL 5/T HS-V-67C F4 1-1/2 GT NC/FAI ALL 5/T 4 ttg C tQ~ttt System Name MAIN STEAM SYSTEM MS Dwg.No.M529 Page 2 of 3 Valve Number a ve Cate or Size Class Coordinates A B C D Inches Norma Valve Actuator Failed Test T e T e Position Durin Test Notes Requests For Relief HS-V-67D 1 04 F 1-1/2 GT HO NC/FAI ALL S/T HS-RV-lA 1 HS-RV-1B 1 HS-RV-1C 1 HS-RV-1D 1 HS-RV-2A 1 HS-RV-28 1 HS-RV-2C 1 HS-RV-2D 1 HS-RV-3A 1 HS-RV-3B 1 HS-RV-3C 1 HS-RV-30 1 FIO Ell F6 E7 Flo E10 F7 E7 F9 E9 F7 EB X X X X X X X X X X X X X X X X X X X X X X X X 6x10 6x10 6x10 6 x 10 6x10 6 x 10 6x10 6x10 6 x 10 6x10 6x10 6x10 S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL S/R AO/SA NC/NA REFUEL BENCH TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST BENCH TEST AOS HS-RV-4A 1 , F9 X X 6 x 10 S/R AO/SA NC/NA REFUEL BENCH TEST ADS HS-RV-48 1 E9 X X 6 x 10 S/R AO/SA NC/NA REFUEL BENCH TEST ADS HS-RV-4C 1 FB X X 6 x 10 S/R AO/SA NC/NA REFUEL BENCH-TEST ADS I CO System Name HAIN STEAH SYSTEH HS Dug.No.H529 Page Valve Number Va ve Catecl~or Size Class Coordinates

~C 5 Inches Norma/Valve Actuator Failed Test T e T e Position Durin Test Notes Requests For Relief HS-RV-4D 1 EB X X 6x10 S/R AO/SA NC/NA REFUEL BENCH TEST ADS HS-RV-5B Eg X X 6x10 S/R AO/SA NC/NA REFUEL BENCH TEST ADS HS-RV-5C FB X X 6x10 S/R AO/SA NC/NA REFUEL BENCH TEST ADS System Name REACTOR FEEDMATER SYSTEM RFW Dwg.No.H529 Page 1 of I Valve Number a ve Categonr r Size Class Coordinates ~B~D Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief RFW-V-10A 1 G12 F X 24 CK SA NO/NA CSO S/E RFW-V-10B 1 GS F X 24 NO/NA CSD S/E RFW-V-32A 1 RFW-V-328 1 G13 F X F X 24 24 AO AO NO/NA NO/NA CSD 5/E CSD S/E RFM-V-65A 1 G13 24 GT MO NO/FAI CSO 5/T RFW-V-65B 1 G4 24 GT MO NO/FAI CSD 5/T System Name REACTOR RECIRCULATION COOLING RRC HY Owg.No.H530 Page Valve Number a ve Cate or Size Class Coordinates A D Inches Norma Valve Actuator Failed Test T e T e Position Durin Test Notes equests For Relief RRC-V-13A 2 C13 F X 3/4 NO/NA CSD S/E RRC-V-138 2 RRC-V-16A 2 RRC-V-168 2 813 C14 814 F X 3/4 3/4 3/4 CK GT GT HO HO NO/NA CSO NO/NA CSD NO/NA CSO S/E S/T S/T RRC-V-19 1 F11 3/4 SV SOL MC/FC ALL S/E 1, 4 RRC-V-20 1 HY-V-17A, 8 2 F12 E4, E13 F 3/4 3/4 SV GT SOL SOL NC/FC NO/FC ALL S/T CSO S/E lg 1, 4 1, 4 HY-V-IBA)8 2 E4, E13 F 3/4 GT SOL NO/FC CSO S/E 1g 1, 4 HY-V-19A, 8 2 E4, E13 F 3/4 GT SOL NO/FC CSD S/E 1g 1, 4 HY-V-20A, 8 2 HY-V-33A, 8 2 HY-V-34A, 8 2 E4, E13 F E4, E13 F E4, E13 F 3/4 3/4 3/4 GB GT GT SOL SOL SOL NO/FC NO/FC NO/FC CSD S/E CSD S/E CSO S/E lg lg 1g 1, 4 1, 4 1, 4 HY-V-35A, 8 2 E4, E13 F 3/4 GT SOL NO/FC CSO S/E 1g 1, 4 HY-V-36A, 8 2 E4, E13 F 3/4 GB SOL NO/FC CSD S/E 1g 1, 4 System Name E UIPHENT DRAIN RADIOACTIVE EDR Dwg.No.M537 Page t PC Valve Number a ve Cat~ear S f ze Class Coordinates ~W~Inches orma Valve Actuator Failed Test T e T e Position Ourin Test Notes equests For Relief EDR-V-19-2 09 F 3 GT AO NO/FC ALL S/T EOR-V-20 2 09 GT AO NO/FC ALL S/T System Name FLOOR DRAIN RADIOACTIVE FOR Dwg.Ho.H539 Valve Number a ve~Cate er Size Class Coordinates A 8 C 0 Inches orma Valve Actuator Failed Test T e T e Position Ourin Test Notes equests For Relief FOR-V-3 2 06 F 3 GT AO NO/FC ALL S/T FDR-V-4 F GT AO NO/FC ALL S/T

System Name PRIMARY CONTAINMENT COOLING 5 PURGE CSP CEP Owg.No.M543 Page 1 of 3 Valve Number a ve Category Size Class Coordinates lM!C II Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief CSP-V-1 2-06 F 30 BF AO NC/FC ALL S/T CSP-V-2 CSP-V-3 06 C5 30 24 BF BF AO AO NC/FC ALL S/T NC/FC ALL S/T CSP-V-4 C5 24 BF AO NC/FC ALL S/T CSP-V-5 CSP-V-6 814 24 24 BF BF AO AO NC/FO ALL S/T NC/FO ALL S/T CSP-V-7 F X 24 CK AO/SA NC/NA ALL S/E CSP-V-8 814 F X 24 CK AO/SA NC/NA ALL S/E CSP-V-9 86 24 BF AO NC/FO ALL S/T CSP-V-10 2 86 F X 24 AO/SA NC/NA ALL S/E CEP-V-1A 2 J13 30 BF AO NC/FC ALL 5/T CEP-V-2A 2 CEP-V-3A 2 CEP-V-4A 2 CEP-V-18 2 J13 C14 C14 J13 24 24 BF BF BF GB AO AO AO AO NC/FC ALL S/T NC/FC ALL S/T NC/FC ALL S/T NC/FC ALL S/T System Name PRIMARY CONTAINMENT COOLING&PURGE CEP CVB Dwg.Ho.M543 Page Valve Number a ve~cate or Size Class Coordinates A 8 C 0 Inches orma Valve Actuator Failed Test T e T e Position Ourin Test Notes eques s For Rel ief CEP-V-28 2 J13 F 2 GB AO NC/FC ALL S/T CEP-V-38 2 CEP-V-48 2 C14 C14 GB GB AO AO NC/FC ALL S/T NC/FC ALL S/T CVB-V-1A 2 812 X X 24 AO/SA NC/NA ALL S/E CVB-V-18 2 612 X X 24 AO/SA NC/NA ALL S/E CVB-V-1C 2 CVB-V-10 2 CVB-V-1E 812 X X 811 X X 612'X 24 24 CK AO/SA NC/HA ALL S/E AO/SA HC/NA ALL S/E AO/SA NC/HA ALL S/E CVB-V-1F 811 X X 24 CK AO/SA NC/NA ALL S/E CVB-V-1G CVB-V-1H CVB-V-1J 811 811 89 X X X X X X 24 24 24 AO/SA NC/NA ALL S/E AO/SA NC/NA ALL S/E AO/SA NC/NA.ALL S/E CVB-V-1K 2 89 X X 24 AO/SA NC/HA ALL S/E CVB-V-1L 2 CVB-V-1M 2 68 88 X X X X 24 24 AO/SA NC/NA ALL S/E AO/SA HC/NA ALL S/E ct cd cte<Cl~cD I tea O System Name PRINARY CONTAINMENT COOLING 5 PORGE CVB PI Dwg.No.M543 Page 3 of 3 Valve Number a ve~Cate or Size Class Coordinates A 8 C D Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief CVB-V-1N 2 88'X X 24 CK AO/SA NC/HA ALL S/E CVB-V-1P 2 88 X X 24 CK AO/SA NC/HA ALL S/E CVB-V-lg 2.87 X X 24 CK AO/SA NC/HA ALL S/E CVB-V-1R 2 CVB-V-1S 2 87 87 X X X X 24 24 CK CK AO/SA HC/NA ALL S/E AO/SA NC/NA ALL S/E CVB-V-1T 2 87 X X 24 CK AO NC/HA ALL S/E PI-VX-250 2 F13 SV SOL NO/FC ALL S/E 1, 4 PI-VX-251 2 F13 SV SOL NO/FC ALL S/E 1, 4 PI-VX-253 2 PI-VX-256 2 F13 F7 SV SV SOL NO/FC ALL S/E SOL NO/FC ALL S/E 1, 4 1, 4 PI-VX-257 2 F7 SV SOL NO/FC ALL S/E 1, 4 PI-VX-259 2 F7 SV SOL NO/FC ALL S/E 1, 4 PI-CVX-72f 2 PI-CVX-73e 2 F12 F7 F X F X CK NC/HA CSD S/E NC/NA CSD S/E 1h 1h Cta Cta<EQ tta System Name CONTAINMENT ATHOSP HERE CONTROL CAC ACCIDENT HITIGATION Dwg.No.H554 Page 1 of 2 Valve Number a ve Catego~r Size Class Coordinates ~II~Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes eques s For Relief CAC-V-1A 2 F15 X 2 DIA HO NC/FC ALL 5/T CAC-V-18 Fl DIA HO NC/FC ALL S/T CAC-V-2 G10 GT HO NC/FAI ALL S/T CAC-V-2A 2 CAC-V-28 2 F12 FS DIA DIA HO HO NC/FC ALL S/T NC/FC ALL S/T CAC-V-4 E10 GT HO NC/FAI ALL 5/T CAC-V-6 HIO GT HO NC/FAI ALL 5/T CAC-V-8 CAC-V-11 2 D10 G6 GT HO HO NC/FAI ALL S/T NC/FAI ALL S/T CAC-V-13 2 E6 GT NC/FAI ALL S/T CAC-V-15 2 CAC-V-17 2 CAC-FCV-IA 2 H6 H10 2-1/2 GT GT GB HO HO HO NC/FAI ALL S/T NC/FAI ALL S/T NC/FC ALL S/T CAC-FCV-18 2 H6-F 2-1/2 GB HO NC/FC ALL S/T CAC-FCV-2A 2 GIO 2-1/2 GB HO NC/FC ALL S/T 4 C lQ~m

System Name CONTAINMENT ATMOSPHERE CONTROL CAC Dwg.No.M554 Page Valve Number a ve Cate or Size Class Coordinates 8 C 0 Inches orma Valve Actuator Failed Test T e T e Position Durin Test Notes equests For Relief CAC-FCV-28 2 G6 F 2-1/2 GB HO NC/FC ALL S/T CAC-FCV-3A 2 DIO 2-1/2 GB HO NC/FC ALL S/T CAC-FCV-38 2 2-1/2 GB HO NC/FC ALL S/T CAC-FCV-4A 2 CAC-FCV-48 2 CAC-FCV-5A 2 FIO E6 F14 2-1/2 2-1/2 GB GB'GB HO HO HO NC/FC ALL S/T NC/FC ALL S/T NC/FC ALL S/T CAC-FCV-58 2 F2 GB HO NC/FC ALL S/T CAC-RD-1A 2 D12 RD SA NC/NA IWV-3620 IWV-3620 CAC-RD-18 2 RD NC/NA IWV-3620 IWV-3620 CAC-RV-63A 2 CAC-RV-638 2 E12 E4 1 x 2 lx2 RV RV NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST CAC-RV-65A 2 CAC-RV-658 2 D13 11/2x3 RV 11/2x3 RV NC/NA REFUEL BENCH TEST NC/NA REFUEL BENCH TEST System Name CONTAINMENT INSTRUMENT AIR CIA Dwg.No.M556 Page"1 of 2 Valve Number a ve Ca~te~or Size Class Coordinates A B~Inches orma Valve Actuator Failed Test T e T e Position Ourin Test Notes eques s For Relief CIA-V-20 2 J6 F 3/4.GB MO NO/FAI ALL S/T CIA-V-21 J4 F X 3/4 CK*SA NO/NA REFUEL S/E 3, 4 CIA-V-30A 2 1/2 GB MO NO/FAI ALL S/T CIA-V-30B 2 F6 1/2 GB MO-NO/FAI ALL S/T CIA-V-31A-2 H5 F X 1/2 HO/NA REFUEL S/E 3, 4 CIA-V-318 2 CIA-V-36M 2 CIA-V-36H 2 CIA-V-36P 2 E6 B4 B4 B4 F X X X X X'X X.1/2 1/2 1/2 1/2 CK CK NO/HA REFUEL S/E HC/HA REFUEL S/E NC/NA REFUEL S/E NC/NA REFUEL S/E 3, 4 3, 7 3, 7 3, 7 CIA-V-36R 2 B4 X X 1/2 NC/NA REFUEL S/E 3.7 CIA-V-365 2 B4 X X 1/2 NC/HA REFUEL S/E 3.7 CIA-V-36U 2 X X NC/HA REFUEL S/E 3, 7 CIA-V-36V 2 B4-X X 1/2 SA NC/NA REFUEL S/E 3.7 CIA-V-39A 3 H7 1/2 SV SOL NO/FC CSD S/E CIA-V-39B 3 F7 1/2 SV SOL HO/FC CSD S/E , C ld~0 System Name CONTAINNENT INSTRUMENT AIR CIA Dwg.No.H556 Page 2 of 2 Valve Number Valve Cate or Size Class Coordinates A 8 0 Inches Valve T e Norma Actuator Failed Test T e Position Ourin Test Notes equests For Relief CIA-V-40 2 H5-85 X X 1/2 SERIES NO/NA REFUEL S/E TYP.OF 7 3, 7 CIA-V-41A 3 CIA-V-418 3 H7 F7 X X X X 1/2 1/2 CK NO/NA CSD NO/NA CSO S/E S/E CIA-SPV-18 3 thru 198 CIA-SPV-1A 3 thru 15A C IA-V-528 3 thru 708 CIA-V-52A 3 thru 66A CIA-RV-5A 3 CIA-RV-58 3.C IA-V-103A 3 EB EB FB H9 X X X X X X 1/2 I 1/2 1/2 1/2 3/4 3/4 1/2 SN SN CK RV RV Sol Sol NC/FO ALL S/E NC/FO ALL S/E NC/NA ALL S/E NC/NA ALL S/E NC/NA ALL BENCH TEST NC/NA ALL BENCH TEST NC/NA ALL S/E CIA-V-1038 3 F9 X X 1/2 NC/NA ALL S/E System Name HAIK STEAM LEAKAGE CONTROL MSLC Dug.No.H557 Page 1 of 1 a ve Valve Ca teraCor Size Number Class Coordinates A 8 C 0 Inches HSLC-V-1A 2 87 X 1-1/2 orma Valve Actuator Failed Test T e T e Position Durin Test NC/FAI ALL S/T Notes eques s For Relief HSLC-V-18 2 HSLC-V-1C 2 HSLC-V-ID 2 85 07 DS 1-1/2 1-1/2 1-1/2 GT GT GT HO HO NC/FAI ALL S/T NC/FAI ALL S/T NC/FAI ALL S/T HSLC-V-2A 1 GT HO NC/FAI ALL S/T HSLC-V-2B 1 1-1/2 GT HO NC/FAI ALL S/T HSLC-V-2C 1 HSLC-V-20 1 EB EB 1-1/2 1-1/2 GT HO MO NC/FAI ALL S/T NC/FAI ALL S/T HSLC-V-3A 1 Cg 1-1/2 GT NC/FAI ALL S/T MSLC-V-3B 1 HSLC-V-3C 1 EB 1-1/2 1-1/2 GT GT NC/FAI ALL S/T NC/FAI ALL S/T HSLC-V-3D 1 EB 1-1/2 GT HO NC/FAI ALL S/T HSLC-V-4 2 J5 1-1/2 GT HO NC/FAI ALL S/T HSLC-V-5 2 J5 1-1/2 GT HO NC/FAI ALL S/T HSLC-V-9 2 HSLC-V-10 2 H5 H5 1-1/2 1-1/2 GT GT HO HO NC/FAI ALL S/T NC/FAI ALL S/T Page 4-41 Revisson 1..Valve Exercisin Test Fre uenc-Exce tions IWV-3411 states that category A and 8 valves shall be exercised at least once every 3 months, except as provided by IWV-3412(a). IWV-3412(a) states: Valves shall be exercised to the position required to fulfill their func-tion unless such operation is not practical during plant operation. If only limited operation is practical during plant operation, the valve shall be part-stroke exercised during plant operation and full stroke exercised during cold shutdowns. Valves that cannot be exercised during lant operations shall be specifically identified by the Owner and shall e full-stroke exercised during cold shutdowns. Furthermore, NRC Guideance, Draft Reg.Guide NS901-4, states"valves which when exercised (cycled)could put the plant in an unsafe condition" should be excluded from testing or deferred until appropriate plant test conditions are provided.The following valves are specifically identified by the Owner as being impractical to exercise during plant operations and will therefore be full-stroke exercised during cold shutdowns. The testing of these valves shall commence immediately (within 24 hours)following the establishment of cold shutdown conditions in accordance with the owner's established schedule.Testing shall continue only as long as the plant is scheduled to be in cold shutdown to perform required maintenance. During each cold shutdown, testing shall commence with the next valve in succession after the previous cold shutdown.All of these valves will be tested during each refueling outage.The valves are identified by unique valve numbers and Code identification as to Code Class and Valve Category.a)Valve Number Code Id.Function CRD-V-110A, 8 2, 8+Provides a redundant means of depressurizing the CRD-V-111 2, 8-C J scram valve diaphragms. Justification -Cycling the valves would result in scramming the reactor, therefore this testing shall be done during cold shutdown plant conditions. b)Valve Number Code Id.Function RCIC-V-65, 66 1, A-C RCIC discharge to the reactor vessel head LPCS-V-6 1, A-C LPCS discharge to the reactor vessel HPCS-V-5 1, A-C HPCS discharge to the reactor vessel RHR-V-41A, B.C 1, A-C RHR Loop A, 8, C discharge to the reactor vessel RHR-V-50A, 8 1, A-C+RHR Loop A, 8 discharge to the recirculating pump L discharge Justification -Valves cannot be opened against the differential pressure which exists across them during power operations. Reactor coolant system pressure holds the valves closed.Also, valves are located inside the containment (except RCIC-V-65) and cannot be temporarily isolated to allow testing. P' Page 4-42 Revisson c)Valve Number Code Id.Function RHR-V-8 RHR-V-9 RHR-V-23 RHR-V-53A, B I, A I, A 1, A 1, A 1 Isolation valves in RHR shutdown cooling suction line from recirculation loop A RHR supply to vessel head spray (Loop A, B outborad isolation valve for shutdown cooling return Justification -Valves are interlocked with reactor coolant system pressure RRR p I 11 f elevated reactor coolant system pressures. Opening circuit is disabled by the same pressure interlocks. Over pressurization of the suction line may cause the loss of shutdown RHR cooling capability. Interlocks cannot be bypassed with normal control circuits.d)Valve Number Code Id.Function RCC-V-5 RCC-V-21 RCC-V-40 RCC-V-104 2, A 2, A 2, A 2, A Isolation valves for reactor closed cooling water lines Justification -Closure of any isolation valve will interrupt cooling water R I I I (RRC)P p I, t 5 RRC p p t coolers and to the Drywell Air Coolers possibly causing failure of this equip-ment.The risks associated with failure of this equipment outweigh any poten-tial benefits from quarterly testing of these valves.e)Valve Number Code Id.Function MS-V-37 Series 2, BC P Vacuum breakers for 18 main steam relief line MS-V-38 Series 2, BC J downcomers. Justification -Valves have no power operator by which they may be stroked remotely.Valves are located inside primary containment and, consequently, are inaccessible during power operations. f)Valve Number Code Id., Function RFW-V-10A, 8 1, A-C RFW-V-32A, B 1, A-C RFW-V-65A, B 1, A Reactor feedwater inboard check valves Reactor feedwater outboard check valves Reactor feedwater stop valves Justification 6~I 5 FII-F-RRR, 65)16 of flow to the reactor vessel and cause a significant reduction of reactor coolant inventory. 2)Category A-C valves are held open by feedwater flow and cannot be closed during power operations. Page 4-43 Revis)on g)Valve Number Code Id.Function HY-V-17A, 8 HY-V-18A, 8 HY-V-19A, 8 HY-V-20A, 8 HY-V-33A, 8 HY-V-34A, 8 HY-V-35A, 8 HY-V-36A, 8 2, 8 2, 8 2, 8 2~8 2, 8 2, 8 2, 8 2, 8 Valves provide hydraulic control fluid to the reactor recirculation flow control valve hydraulic operators. Recirculation flow control valves are RRC-V-60A and RCC-V-608. Justification -Exercising of the hydraulic valves may cause repositioning of the reactor recirculation flow control valve, causing undesirable reactivity changes in the core.h)Valve Number Code Id.Function PI-CVX-72f 1, A-C P Containment isolation, located on discharge PI-CVX-73e 1, A-C J lines of Radiation Leak Detection Monitors, penetr ations X-73e, X-72f.Justification -These containment isolation check valves are located inside the containment and can only be observed/tested during cold shutdown conditions. i)Valve Number Code Id.Function CIA-V-39A$8 CIA-V-41A, 8 3, 8+These valves cross connect the normal nitrogen 3, 8-C 3 supply for the Main Steam Isolation Valves and Main Steam Relief Valves (including the 7ADS Valves)accumulators to the backup nitrogen sup-ply for the 7ADS valves.Justification -Testing these valves requires securing the backup nitrogen sup-1" 1" 1.111 1 1 d 111 1 11 operating. j)Valve Number Code Id.Function RRC-V-13A, 8 RRC-V-16A) 8 2, A-C+Inboard and outboard isolation valves for the 2, A J recirculation pumps seal purge line.Justification -Closure of Category A valves (RCC-V-16A, 8)would terminate 1 1 1 1 1 pip 1, 1 1.1 purge flow may result in excessive seal wear and possibly failure of the seal.The risk associated with seal failure are greater than the benefits gained by quarterly valve testing.Category A-C valves (RRC-V-13A, 8)are held open by purge water flow and can-not be closed.during power operations. k)Valve Number Code Id.Function RCIC-V-13 1, A RCIC pump discharge isolation valve and contain-ment isolation. Justification -Opening this valve during normal power operations will result in tripping the main turbine generator off line. Page 4-44 Revisson 2.Only those valveq which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident are required to be tested per Subsection IWV of the Code.Using this criteria the following valves are not re-quired to be tested per Subsection IWV, but due to their functional importance are included in the valve list.RCIC-V-1, 10, 11, 21, 22, 30, 45, 46, 59, 65, 086, 111, 112 RCIC-RV-17, 19 RCIC-RD-1, 2 3.These valves are not ASME Class III.They have been assigned Washington State Special Numbers and are considered as SA105 material welded to an ASNE code system pressure boundary.SW-V-187A, B FPC-V-172, 173, 175, 181A, 181B, 184 4.Valve closes automatically if Reactor Vessel pressure is less than 47 psig.Therefore, if cold shutdown conditions extend beyond a 3 month period, IWV testing frequency may not be, met.However, valves will be tested prior to resuming power operations as per IWV-3416.RCIC-V-8, 45, 63, 76, 110, 113 a.RCIC-V-ill and V-112 are check valves isolated by RCIC-V-110 and V-113 which close automatically if reactor vessel pressure is less than 47 psig.5.These valves are not required to be in service until the fuel pool cool-ing system is placed in service.It is not expected to be placed in ser-vice until the first refueling outage at which time this test program'ill be implemented as per IWV-3416.SW-V-75A, 75B, 187A, 187B, 188A, 188B RCC-RV-34A, B FPC-V-112A, 112B, 153, 154, 156, 172, 173, 175, 181A, 181B, 184 FPC-RV-117A, B Page 4-45 R 4.5 Re uests for Relief from Certain Code Re uirements Relief Requests are presented to document differences between the Code and WNP-2's Valve Test Program.The requests include technical justifi-cation for the differences and, where appropriate, propose alternate testing. Page 4-46 R REQUEST FOR RELIEF NO.RV-1 System Valve(s)ASIDE Classification Function Various Valves affected by this relief request are identified in TABLE A.Code Testing Requirement 1.Timing of valve stroke (IWV-3413) Basis for Relief 1.Solenoid valves and the RCIC turbine throttle trip valve are very rapid acting, with stroke times much less than one second.It is meaningless to measure their stroke times"to the nearest second".Alternate Testing 1.to be Performed Valves will be full stroke tested.Satisfactory operation of equipment downstream of the solenoid valve will constitute satisfactory valve operation. ualit/Safet Im act The only valves in Table A for which timing might be an important parameter are the Category A valves which are containment isolation valves.However, these valves have position indication displayed in the Control Room and on the Transient Data Acquisition System.Furthermore, each of the Category A valves have backup valves which can be used to isolate the line should it be required.The proposed exercise testing and regular position indication verification will provide adequate assur ance of quality and public safety. Page 4-47 Revisson RV-1 TABLE A Valve Code Class Cate or Function HY-V-17A, 8 HY-V-18A, 8 HY-V-19A, 8 HY-V-20A, 8 HY-V-33A, 8 HY-V-34A, 8 HY-V-35A, 8 HY-V-36A$8 Hydraulic supply for Reactor Recirculation. Flow Control Valves RRC-V-19 RRC-V-20 Reactor rec ircul ati on samp 1 ing Iso val ve.Reactor recirculation sampling Iso valve.C IA-V-39A CIA-V-398 8 P Cross ties between air and nitrogen 8 J headers.DO-V-40A DO-V-408 DO-V-43 Diesel fuel oil day tank 3A inlet valve Diesel fuel oil day tank 38 inlet valve k Diesel fuel oil day tank 3C inlet valve CRD-V-110A CRD-V-1108 Back-up Scram Valve (Air Supply)Back-up Scram Valve (Air Supply)CIA-SPV-18 thru 198 Nitrogen Bottles'solation Valves C IA-SP V-1A thru 15A 3 Nitrogen Bottles'solation Valves Page 4-48 Rev>sion RY-1 TABLE A (Cont'd)Valve Code Class Cate or Function PI-VX-251 PI-VX-250 P I-VX-253 P I-VX-256 P I-VX-257 P I-VX-259 A A~A A A A Radiation monitor RAO-RE-12B inlet valve Radiation monitor RAD-RE-12B outlet valve Radiation monitor RAD-RE-12B outlet valve Radiation monitor RAD-RE-12A inlet valve Radiation monitor RAD-RE-12A inlet valve Radiation monitor RAD-RE-12A outlet valve P I-VX-262 PI-VX-263 P I-VX-264 PI-VX-265 A A A A 2, 02 monitor inlet and outlet valves (S-SR-13)PI-VX-266 PI-VX-267 P I-VX-268 P I-VX-269 2, 02 monitor inlet and outlet valves (S-SR-14)RHR-V-60A RHR-V-60B RHR-V-75A RHR-V-75B RHR-V-182 Loop A sample'inboard) Loop 8 sample (inboard)Loop A sample (outboard) Loop B sample (outboard) Drain Vlv between Valves isolating Service Matet from RHR RV-1 TABLE A (Cont'd)Page 4-49 R Valve Code Class Cate ory Function SW-V-201 SW-V-204 SW-V-206 SW-V-209 SW-V-210 SW-V-211 SW-V-212 SW-V-213 Cooling Water to H2 02 analyzers S-SR-13, 14.RCIC-V-1 RCIC Turbine Throttle Trip Valve. Page 4-50 Revisson REQUEST FOR RELIEF HO.RV-2 System Valve(s)ASME Cl ass if i cati on Standby Liquid Control (SLC)SLC-V-6, SLC-V-7 Code Class: I Category: B-C (SLC-V-6)A-C (SLC-V-7)Function Standby Liquid Control discharge to reactor vessel.Code Testing Requirement I)Quarterly exercising (IWV-3521) 2)Cold shutdown exercising (IWV-3522)Basis for Relief l.Valves have no operator with which they may be stroked.2.Exercising the valves require'the initiation of the SLC system and full flow injection into the reactor vessel.Initiation of SLC flow involves the discharge of Category 0 explosively activated valves.Alternate Testing At least once per 18 months, one of the Standby Liquid Con-to be Performed trol System loops, including the associated explosive valve, will be initiated. A flow path to the Reactor.Vessel will be verified by pumping demineralized water to the vessel.Valve closure capability will be verified in conjunction with 10CFR50 Appendix J (Type C)testing.ualit/Safet Im act The proposed testing complies fully with the intent of the Code (IWV-3522). Additionally it is noted that the SLC system will be required to perform its safety function only under very infrequent circumstances (ATWS).The proposed testing provides adequate assurances of quality and public safety.

Page 4-51 Revisson RE(VEST FOR RELIEF NO.RV-3 System Valve(s)ASME Classification Function Containment Instrument Air Valves affected by this relief request are identified in TABLE C.Code Testing Requirement quarterly testing (IWV-3412)Position indication verification (IWV-3522) Basis for Relief 2.The 40 series and 36 series valves are located inside the containment and are inaccessible during power operations. There is no way to remotely isolate the valves and observe the pressure decay of the accumulators. There is no local or remote position indication for these check valves.Alternate Testing 1.to be Performed 2~During refueling outages, pressure decay tests will be performed for the accumulators associated with the Main Steam Safety/Relief Valves in order to verify closure ability of 40 series and 36 series valves.Each accumulator will be tested at least every two years.Closure ability of CIA-V-21, 31A, and 31B will be verified by normal 10CFR50, Appendix J (Type C)testing.ualit/Safet Im act The proposed testing qualitatively verifies valve closure on the most practi-cal regular basis.This satisfies the intent of the Code (IWV-3412). Valve opening is verified when the accumulators are pressurized in preparation for the pressure decay test.The valves in Table C are in the pneumatic supply to the auto-depressurization System valves, a safety related system.However, the proposed alternate test-ing together with the redundancy of the pneumatic supplies and individual accumulators, of the ADS valves themselves and of the high pressure injections systems assures an acceptable level of quality and public safety. Pagq 4-5 Revs RV-3 TABLE C Valve Code Class Cate or Function CIA-V-31A CIA-V-31B A-C A-C Instrument air supply to ADS valves (outside containment) CIA-V-40 series 2 (7 valves)A-C Instrument air to ADS Accumulators (inside containment) CIA-V-36M, N, P, 2 R, S, U, and V A-C Instrument air supply to Main Steam Relief Valves'ccumulators (inboard check valve)CIA-V-21 A-C I Instrument air supply to containment (outboard check valve). Page 4-53 Revision 2 RE(VEST FOR RELIEF NO.RV-4 System Valves, ASME Classification Function Various See WNP-2 FSAR, Table 6.2-16 Code Class: 1 and 2 Category: A, A-C Containment Isolation Code Testing Requirement 1.Leak Test Requirements (IWV-3420)Basis for Relief 1.The purpose of leak rate testing is, ultimately, to assure that the limits of 10CFR100 are not exceeded.Hence the overall leakage from the containment is the critical parameter in leak rate testing, not indivi-dual valve leak rates.Appendix J Leak Test require-ments specifically address leakage requirements for valves functioning as containment isolation valves.Alternate Testing 1.These valves will be leak tested using the requirements to be Performed of 10CFR50, Appendix J in lieu of IWV-3420.ua1 i t/Saf et Im act These valves are all category A valves and whether active or passive perform a common safety function of containment isolation. The Appendix J requirements recognize this safety function and provides leak test requirements based on this safety function.The proposed alternate testing provides adequate assur-ance of quali ty and pub 1 i c safety.

Page 4-54 Revision RE(UEST FOR RELIEF NO.RV-5 System Valves ASME Classification Various See WNP-2 Technical Specification (Table 3.4.3.2-1) Code Class: 1 and 2 Category: A, A-C Function Reactor Coolant System Pressure Isolation and Containment Isolation Code Testing Requirement l.IWV-3427, Corrective Action Basis for Relief 1.The WNP-2 Technical Specification establishes limit-ing leak rates for each valve and describes the neces-sary corrective action if these limits are exceeded.Furthermore, these valves are additionally leak tested using Appendix J requirements to verify the valves'afety function as a containment isolation valve.Alternate Testing 1.These valves will be leak tested at least once every to be Performed 18 months and if the leakage exceeds the specified limit, the corrective actions specified in the WNP-2 Technical Specification will be followed.ualit/Safet Im act These valves perform a dual safety function.They are identified in the WNP-2 FSAR as containment isolation valves and as such, will be leak tested using the requirements of 10CFR50, Appendix J.In addition to this, the WNP-2 Tech-nical Specification identifies these valves as reactor coolant system pressure isolation valves and as such, will be leak tested again using the IWV require-ments.Compliance with the WNP-2 Technical Specification and Appendix J leak test requirements provides adequate assurance of material quality and public safety. Page-4-55 Revision 2 RE(VEST FOR RELIEF NO.RV-6 System Valves ASNE Classification Function Primary Containment Cooling and Purge CVBV lA, 8, C, D, E, F, G, H, J, K, L, N, N, P, g, R, S, T Code Cl ass: 2 Category: A-C To break vacuum on the drywell to suppression chamber down-comers and to limit steam leaka e from the downcomer to the~dr e11.Code Testing Requirement l.IWV-3426, That the owner assign limiting leak rates for a specific valve.2.IWV-3427, Corrective Action Basis for Relief 1.These check valves cannot be tested individually, therefore, assigning a limiting leakage rate for each valve is not practical. The purpose of this leak rate test is to assure that the leakage from the suppres-sion pool chamber to the drywell does not exceed Tech-nical Specification limits.The WNP-2 Technical Specification specifies conservative corrective actions commensurate with the importance of the safety function being performed by these valves.Alternate Testing 1.to be Performed These valves will be leak tested according to WNP-2 Technical Specifications, at least once per 18 months by conducting a drywell-to-suppression chamber bypass leak test.Corrective actions will be as specified in the Technical Specification. ualit/Safet Im act The leakage criteria and corrective actions specified in the WNP-2 Technical Specification is the most practical approach to assessing the adequacy of these valves in performing their specified safety function.Following the WNP-2 Technical Specification provides adequate assurance of material quality and public safety.

Page 4-56 Revision 2 REQUEST FOR RELIEF NO.RV-7 System Valves ASME Classification Function Containment Instrument Air CIA-V-36M, N, P, R, S, U, V CIA-V-40M, N, P, R, S, U, V Code Class: 2 Category: A-C These valves isolate the accumulators for the Auto Depres-surization System (ADS)valves in the event that the supply line is broken or the pressure source is depressurized. Code Testing Requirement l.IMV-3426, That the owner assign a limiting leak rate to a specific valve.Basis for Relief 1.These check valves cannot be tested individually, therefore, assigning a limiting leakage rate for each valve is not practical. Alternate Testing l.to be Performed These check valves will be leak tested during a pres-sure decay test on the accumulators. Acceptance cri-teria will be based on the valves'bility to perform their safety function.ualit/Safet Im act The valves will be divided into groups and tested.The acceptance criteria will be based on the valves'bility to perform its safety function.The pro-posed alternate testing provides adequate assurance of material quality and public safety. Pace 4-57 R RE(UEST FOR RELIEF NO.RV-8 System Valves ASME Classification Function Residual Heat Removal RHR-V-209 Code Class: Category: A-C Containmept isolation and Reactor Coolant System Pressure Boundary and ressure relief for i in between valves RHR-V-8 and 9.Code Testing Requirement l.IWV-3411, that each category A valve be exercised at least once every 3 months.Basis for Re 1 ief 1.This check valve is located inside the containment does not have valve position indication or an operator of any type.It cannot be tested without interrupting RHR shutdown cooling flow.During power operations, access is prohibited. During cold shutdown condi-tions, RHR cannot be out of service more than 2 hours per an 8 hour interval (per WNP-2 Technical Specifica-tion).Additionally, containment will not be de-inerted during all cold shutdowns. Alternate Testing l.to be Performed These check valves will be exercised at refueling out-ages.Furthermore, this check valve is verified to shut by being leak tested at least once every 18 months in compliance with Appendix J and IWV requirements. ualit/Safet Im act This valve is normally closed and is verified to be adequately seated by leak tests at least once every 18 mbnths (both Appendix J and IWV leak rate tests).This valve performs the passive safety functions of containment isolation and reactor coolant system pressure isolation. Its active function of relieving pressure between valves RHR-V-8 and RHR-V-9 is a very unlikely situation and could only occur during time periods where both RHR-V-8 and 9 are shut and containment temperature is significantly above normal (i.e., LOCA condition). The proposed alternate testing avoids extraordinary testing efforts with in-herent potential for violations of the WNP-2 Technical Specification. This will provide adequate assurance of material quality and public safety. Page 4-58 Revision 2 4.6 Record of Valve Inservice Tests Records and reports pertaining to Valve Inservice Testing will be main-tained according to Article IWV-6000 of the Code.

SAMPL E Page 4-59 Revision Z DATA SHEET VALVE STROKE Valve Stroke Measured Data Acce tance Criteria en Close 0 en Close I Measured B Acce ted B ILPCS-V-1 I LPCS-FCV-1 I I LPCS-V-12 I.ILFCS-V-r I ILPCS-V-rS/I ILPCS-V-S4 I I I 0 ens I I 0 ens I I I Closes Closes I.I I I I I I I I I t I~I I I I I I I I I I I I I I I I Reviewed by: Accepted by: Date/Time: Date/Tioa: Page 4-60 Revision 1 RV-8 TABLE F Valve Code Class Cate or Function RCC-V-5 RCC-V-104 RCC-V-21 RCC-V-26 RCC-V-40 A A A-C A Isolation valves for closed Cooling water lines. Page 4-61 R REQUEST FOR RELIEF NO.RV-9 System Valve(s)ASME Classification Function Control Rod Drive Hydraulic Control Unit (HCU)n Valves affected by this relief request are identified in TABLE G.Code Testing Requirement Quarterly exercising (IWV-3411 and IWV-3521)Cold shutdown exercising (IWV-3412 and IWV-3522)Valve timing for scram valves, HCU-V-126 and HCU-V-127 (I WV-3413)Bases for Relief 2.3.Technical Specifications require that control rods be tested for operability at least every seven days.Acceptable operation the control rod drive mechanisms during Technical Specifications required testing will constitute acceptable operation of the associated valves.During col'd shutdown, control rods will be fully inserted into the core.Technical Specifications explicitly state the maximum insertion time for individual control rods and the average scram insertion time for groups of rods.Scram insertion times are measured for 10K of the control rods, on a rotating bases, every 120 days.Since control rod insertion times are very sensitive to scram valve actuation times, acceptable insertion time measurement results will constitute acceptable scram valve actuation times.Alternate Testing 1.Control Rod Drive Hydraulic Control Unit valves will to be Performed be tested in accordance with plant Technical Specifications. Page 4-62 Revision 1 RV-9 ualit~/Safet Im act Both IWV and the Technical Specifications are intended to increase the safety and reliability of the plant.Since the ultimate purpose of the valves in Table G is to position the control rods, proper rod operation is sufficient. assurance that these valves are ooerating properly.Since the intent of IWV is being met by Technical Specification requirements, granting this relief request will maintain acceptable quality and safety levels. Page 4-63 Revision 1 RV-9 TABLE G Valve Code Class Cate ory Function HCU-V-114 B-C HCU discharge to scram header reverse flow check valve.HCU-V-115 B-C CRD charging water reverse flow-check valve.HCU-V-117 HCU-V-118 Instrument air to scram valves.HCU-V-120 HCU-V-121 HCU-V-122 HCU-V-123 Control Rod Drive supply to rod drive mechanisms (normal operation). HCU-V-126 HCU-V-127 Control Rod Drive scram valves.HCU-V-137 Rod dr ive cooling water reverse flow check valve.HCU-V-138 Control Rod Drive water reverse flow check valve. Page 4-64 Revision 1 REQUEST FOR RELIEF NO.RV-10 System Valve(s)ASCIE Cl ass if i cati on Function Reactor Recirculation Control Yalves affected by this relief request are identified in TABLE H.Code Testing Requirement Quar ter ly exercising.(IWV-3411) Basis for Relief Exercising of the hydraulic valves may cause repositioning of the reactor recirculation flow control valve, causing undesirable reactivity changes in the core.Alternate Testing Yalves will be exercised during cold shutdown.to be Per formed ualit/Safet Im act The valves in Table H affect the reactor recirculation flow control valve position and, hence, significantly contribute to core reactivity control.Ouring power operations, failure of these valves to re-open after exercising would adversely affect plant operation by reducing the reliability of the recirculation system.The proposed alternate testing contributes to accept-able levels of safety and quality by reducing the possibility of unnecessary reactivity control problems. Page 4-65 RV-10 TABLE H Valve Code Class Cate or Function HY-V-17A HY-V-178 HY-V-18A HY-V-188 HY-V-19A HY-V-198 HY-V-20A HY-V-208 HY-V-33A HY-V-338 HY-V-34A HY-V-348 HY-V-35A HY-V-358 HY-V-36A HY-V-368 Valves provide hydraulic control fluid to the reactor recircul a-tion flow control valves'ydrau-lic operators. Recirculation flow control valves are RRC-V-60A and RRC-V-608. Paqe 4-66 Revision RE(UEST FOR RELIEF NO.RV-ll System Valve(s)ASi4E Classification Residual Heat Removal Valves affected by this request are identified in Table I.Function Code Testing Requirement quarterly exercising (IWV-3411) Rasis for Re 1 i ef 2.3.Valves are interlocked with reactor coolant system pressure such that valves automatically close to protect the RHR pump suction line ,rom elevated reactor coolant system pressures. Opening circuit is disabled by the same pressure interlocks. Over pressurization of the suction line may cause the loss of shutdown RHR coolina capability. Interlocks cannot be bypassed with normal control circuits.Alternate Testing Valves will be exercised during cold shutdowns..o be Per ormed ualit~/Safety Im act NRC guidance recognized the potential hazards associated with testing high pressure-low pressure interface valves.Specifically mentioned is the potential of subjecting low pressure piping to pressures above their design pressure, thus compromising the integrity of the plant.The proposed alternate testing is consistant with NRC guidance, reduces the possibility of adverse plant effects and assures acceptable levels of quality and safety. Page 4-67 RV-11 TABLE I Valve Code Class.Cate or Function RHR-V-8 RHR-V-9 Isolation valves in RHR shutdown cooling suction line from recir-culation Loop A RHR-V-23 RHR supply to Vessel head spray RHR-V-53A RHR-V-53B Shutdown cooling return Loop A outboard isolation valve Shutdown cooling return Loop B outboard isolation valve Page 4-58 Revision 0 4.6 Listin of Cate orv A Valves ASt/E 8oiler and Pressure Vessel Code, Section XI, Subsection IMV defines a"Category A" valve as one"for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of its function". For his type of valve, individual leak rate test will be performed to determine leakage oast the valve seat.Tests will be conducted in accordance with the requirements of 10CFR50, Appendix J, Section XI, or both, as indicated on the following table. Page 4.69 Revision 0 Listin of Cate or A Valves Leak Rate Testing Required Valve Class Appendix J.Section XI Valve Function RCIC-V-8 RC I C-V-13 RCIC-V-19 RCIC-V-31 RCI C-V-63 RC IC-V-64 RCIC-V-66 RC IC-V-68 RCIC-V-69 RCIC-V-76 RCIC-V-110 RCIC-V-113 LPCS-V-1 LPCS-V-5 LPCS-V-6 LPCS-FCV-11 LPCS-V-12 HPCS-V-4 HPCS-V-5 HPCS-V-12 HPCS-V-15 HPCS-V-23 RHR-V-4A RHR-V-4B RHR-V-4C RHR-V-8 RHR-V-9 RHR-V-11A RHR-V-118 RHR-V-16A RHR-V-168 RHR-V-17A RHR-V-178 RHR-V-21 Steam to RCIC Turbine RCIC injection (outboard) RCIC minif low to'r!etwel1 RCIC suction from kletwell Steam from Rx to RHR Hx's E RCIC Turbine Steam to RHR Hx's Vessel head soray Ch.vv Turbine Exhaust to lletwell Vacuum pumo return to Wetwell RCIC-V-63 Bypass valve Turbine Exchange line vacuum breaker Turbine Exchange line vacuum breaker LPCS suction from'Netwell LPCS injection (outboard) LPCS injection (inboard)LPCS Minif low valve Test line Iso.valve HPCS injection (outboard) HPCS injection (inboard)HPCS minif low valve HPCS suction from"!etwell HPCS test return to Metwell RHR suction from Metwell RHR suction from'r!etwel 1 RHR suction from Metwell Shutdown cooling suction Valves Condensed steam return from Hx's to Aetwell Orywell spray lines'solation valves Orywell spray lines'solation valves Loop C test line return to'.<etwell Page 4-70 R Listin of Cate or A Valves Leak Rate Testing Required Valve Cl ass A endix J.Section XI Valve Function RHR-V-23 RHR-V-24A RHR-V-248 RHR-V-27A RHR-V-278 RHR-V-41A RHR-V-418 RHR-V-41C RHR-V-42A RHR-V-428 RHR-V--42C RHR-V-50A RHR-V-508 RHR-V-53A RHR-V-538 RHR-FCV-64A 2 RHR-FCV-648 2 RHR-FCV-64C 2 RHR-V-124A RHR-V-1248 RHR-V-125A RHR-V-1258 RHR-V-134A RHR-V-1348 RHR-V-209 SLC-V-4A SLC-V-48 SLC-V-6 SLC-V-7 RHR to head spray line Loop A test line return to Wetwell Loop 8 test line return to Wetwell RHR to suppression pool spray header RHR to suppression pool spray header RHR injection to reactor vessel RHR injection to reactor vessel RHR injection to reactor vessel RHR injection Iso.valve RHR injection Iso.valve RHR injection Iso.valve Shutdown cooling return check valves Shutdown cooling return isolation valves RHR pump minif low valves RHR pump minif low valves RHR pump minif low valves RCIC steam to RHR Hx steam line drip pot drain valves H2 recombiner scrubber drains to Wetwell Pressure relief bypass around RHR-V-9 SLC pump explosive-actuated discharge valve SLC injection line isolation valves Page 4-71 Revison 1 Listinq of Cate ory A Valves Leak Rate Testing Required Valve Class endix J.Section XI Valve Function R!ACU-V-1 RWCU-V-4 RllCU-V-40 RCC-V-5 RCC-V-21 RCC-V-26 RCC-V-40 FPC-V-153 FPC-V-154 FPC-V-156 MS-V-16 MS-V-19 MS-V-22A MS-V-228 MS-V-22C MS-V-220 MS-V-28A MS-V-288 MS-V-28C MS-V-280 MS-V-37 Series MS-V-38 Series MS-V-67A MS-Y-678 MS-V-67C MS-V-670 RFM-V-10A RFM-V-108 RFM-V-32A RFM-V-328 RFM-Y-65A RFM-V-658 Cleanup Mater Pump suction line isolation valves RMCU discharge containment isolation valve Closed cooling water supply to containment equipment isolation valves Suppression pool cleanup outlet and return line isolation valves Main steam line draim isolation valves Main steam lines'nboard isolation valves Main steam lines'utboard isolation valve S/RV discharge downcomer vacuum breakers.Main steam line drains{outside containment) Feeduater line isolation valves Paoe 4-72 Revision 0 Listin of Cate or A Valves Leak Rate Testing Required Val v.e Class Aopendix J.Section XI Yalve Function EOR-V-19 EOR-V-20 FOS-V-3 FOR-Y-4 CEP-V-18 CEP-V-28 CEP-V-3B CEP-V-48 CSP-Y-5 CSP-V-6 CSP-Y-7 CSP-V-8 CSP-V-9 CSP-V-10 CVB-Y-1A through CVB-V-1T CAC-Y-2 CAC-V-4 CAC-V-6 CAC-V-8 CAC-V-ll CAC-V-13 CAC-Y-15 CAC-V-17 CAC-FCY-1A CAC-FCV-18 CAC-FCV-2A CAC-FCY-28 CAC-FCV-3A CAC-FCV-38 CAC-FCV-4A CAC-FCV-48 2'2 2 2 2 X X X, X X X X X Orywell equipmen.drain sump discharge line iso-lation valves Floor drain sump discharge line isolation valves Containment purge exhaust isolation valves Contairment purae suoply isolation valves Vacuum breakers for drywell-wetwell down comers.H2 recombiner inlet/exhaust stop valves H2 recombiner inlet/exhaust throttle valves Paae 4-73 Rev 1 sl on 1 Listin of Cate@or A Valves Leak Rate Testing Required Valve Class Ap endix J.Section XI Valve Function CIA-V-30A CIA-V-308 C IA-V-31A CIA-V-318 CIA-V-36 (series)C IA-V-40 (series)MSLC-V-2A MSLC-V-28 MSLC-V-2C MSLC-V-20 MSLC-V-3A. MSLC-Y-38 MSLC-V-3C MSLC-V-30?2 CIA-V-20 2 CIA-V-21 CIA-V-24 2 Containment instrument air outboard Iso.valve Containment instrument air inboard Iso.valve Inboard MSIY Instrument air supply check valve Backup N2 supplv to con-tainment Iso.valves (outboard) Backuo N2 supply to ADS valves (inboard Iso.valve)Main steam safety/relief valve instrument air supply check valve N2 supply to AOS valves MSLC line isolation valve (first off)MSLC line isolation valve (second off) Cl Page 4-74 Revision I 4.7 Record of Valve Inservice Tests Records and reports pertaining to Valve Inservice Testing will be main-tainedd according to Article IWV-6000 of the Code. Page 5-1 Revisson 5.0 guality Assurance Program The WNP-2 Pump and Valve Inservice Test Program activities will be conducted in accordance with Topical Report WPPSS-(A-004, the Supply System's Operational guality Assurance Program description.

Page 6-1 Revision 2 6.0 Flow Diagrams The Flow Diagrams used to generate this Program are included for user reference. Due to the time required for Program publication, an adminis-trative cut-off date of November 2, 1983 was chosen to"freeze" drawing revisions used for Revision 2 of the Program.All subsequent changes to system design shall be evaluated for impact on the PVT Program Plan and new revisions to this Program shall be issued accordingly.

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