Text

Rev 4 to Pump & Valve Inservice Test Program Plan,WPPSS-2.
	ML17286B179
Person / Time
Site:	Columbia
Issue date:	11/21/1991
From:	John Baker, Rana R; WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	;
Shared Package
ML17286B178	List: ML17286B177; ML17286B179;
References
	PROC-911121, NUDOCS 9112100281
	Download: ML17286B179 (269)
	v • d • e

HASHINGTON PUBLIC PONER SUPPLY SYSTEM NUCLEAR PLANT NO, 2,

,<< PUMP AND VALVE INSERVICE TEST PROGRAM PLAN PZ12100281 5'11203 PDR ADOCK 05000397 P PDR

PUMP AND VALVE INSERVICE TEST.

PROGRAM PLAN REV. 4 HASHINGTON PUBLIC POHER SUPPLY SYSTEM NUCLEAR PLANT NO. 2 Prepared by c7=

IST Program Engineer Date Reviewed by RRa ~ II - l3 - '> i Reviewing Engineer Date Concurrence // i5' Manager, Plant Technic 1 Date Concurrence I l I'Ecl(cl (

Manager, Plant Operations Date Concurrence l( zo el Manager, Plant QA Date Approved by i le(

Plan anager, HNP-2 Date Concurrence Authorized Nuclear Inservice Inspector Date

n V

RECORD OF PROGRAM'LAN REVISIONS ll/12/91 REVISION 3b 10/5/87 REVISION 3a 12/20/65 P,EVISIOfl 6/10/85 REVISION 11/3/83 REVISION 8/28/82 REVISION

+Aar 0 4/23/81 ORIGINAL Ho. i)ATE REV IS IONS CriK'0 APP '0 711

VI Deleted (Relief

-1)

Rel i ef

~in r Request RP-7 3.6-10 Records of

~v 3.6.11 Li st of Effective Pages iv Pump Test NA w CCH-P-1A vi Fl wP h CCH-P-18 Fl Table of DO-P-1A,18,2 Fl w h 4 Pump Test FPC-P-1A,18 Program 1 w P h n r i HPCS-P-1 Program Im- F w plementation 3.2-1 HPCS-P-2 1 w h LPCS-P-1 Program Ad- 1 w RCIC-P-1 Pump Refer- 1 wP h ence List 3.4-1 ,RHR-P-2A 1 w RHR-P-28 Pump Test Fl wP h Tables 3. 5-1 RHR-P-ZC w P 3.5-2 SLC-P-1A,18 F w 3.5-3 SH-P-1A Fl wP h SN-P-18 Pump Relief F w P Records of Relief T Request RP-1 3.6-2 Sample Pump Data Sheets 3.8-2 Rel ief 3.8-3 R

~RRelief Valve Test

~Re De 1 Relief eted (Re 1 i ef P-4 Program Inr u Program Im-i n 4.1-1 Req plementation 4.2-1 Relief

V N Program Ad-mi 1 in 4.4-26 Valve Test T 1 4. 4-1 4.4-27 Valve Test Tables Key 4.4-2 4.4-28 4.4-3 4.4-29 4.4-4 4.4-30 4.4-5 4.4-31 4.4-32 Valve Test Tables 4.4-7 4.4-33 4.4-8 4.4-34 4.4 9 4.4-35 4.4-10 4.4-36 4.4-11 4.4-37 4.4-12 4.4-38 4.4-13 4.4-39 4.4-14 4,4-4 Valve Test 4.4-15 Table Notes 4.4-41 4 4.4-16 4.4-42 4 4.4-17 4.4-43 4.4-18 4.4-44 4.4-19 4.4-45 4.4-20 4.4-46 4.4-21 4 4-47 Valve Relief 4.4-22 ~RRelief 4.

4.4-23 Request RV-1 4.5-2 4.4-24 4.5-3 4.4-25 4

TITL T TL H ET R VI I N Relief Relief Re-e V- 4.- quest RV-18 4.5-30 Rel i ef

~

Request RV-3 4.5-6 Deleted (Relief 4 -7 RV-1 4.

Re 1 i Relief Re-ef'equest RV-4 4.5-8 quest RV-20 4.5-33

4. 5-9 4.5-34 4.5-10 4.5-35 4.5-11 Deleted <Relief

4. 5-12 V- 1 4.

Relief Re-4 -1 V-

'Deleted <Relief Relief Re-4 4 V-Re 1 i ef Relief Re-4 V- 4 4, -4 Re 1 i ef Relief Re-R V- 4. -1 quest RV-25 4.5-41 Re 1 i ef 4,

Rel ief Relief Re-Request RV-9 4.5-18 c 4 V- 4. -4 Relief Re-4, quest RV-27 4.5-44 Deleted (Re'lief V- 4. 4.5-45 Relief Re-

-11 4.

Deleted (Rel i ef Record of V-1 4 Relief Re- Samp1 e Va1 ve

-1 4. Data Sheet 4.6-2 Relief Re-V-14 Re 1 i ef Re- Quali ty quest RV-15 4.5-25 Assurance 4.5-26

4. Piping E Inst.

Deleted (Relief i r m R RV-1 4.

Relief Re-RV-17 4.

TITLE SHEET REVISION TITLE SHEET REVISION oor rain 5.0 equality Radioactive M539* 52 Assurance Containment Pro ram Coolin 8 Pur e M543* 50 ontainment Atmos. Control M554* 38 ow ontainment Dia rams 6-1 Instru. Air M556* 34 ontro ain Steam Service Air M510* Leaka e Cont. M557* 18 lese 1 eutron Misc. S stems M512* 38 Monitoring (Not Dem nera i ze a Flow Dia ram) M604* 13 Water M517* 57 Steam an eactor ore Li uid Sam. M607* 17/16/10 Iso. Coolin M519* 44 mergency i e ig ow ressure Water M775*

Core S ray M520* ri. ontainment esi ua ea Nitro en Inertin M783*

Removal M521* 50/51 ost Acci ent tan y iq. Sam lin M896*

Control M522* 20 eac or ater Cleanu M523* 59 tan y ervice Water M524* 52/51 Reactor ose Coolin M525* 42 ue oo Coolin M526* 54 ontro o Drive M528*

Main Steam an Reactor Feedwater M529*

eactor Recirc.

Coolin M530* 47 Equip. Drain Radioactive M537*

Burns 8 Roe Flow Dia ram Number vii

a~

Revision 4

1.0 INTRODUCTION

This Pump and Valve Inservice Test Program Plan is applicable to the HPPSS Nuclear Project No. 2, hereinafter referred to as HNP-2. A single unit Boil-ing Hater Reactor (BWR), the power plant is located 11 miles north of Richland, Hashington, on the Hanford Reservation. The, plant employs a General Electric (GE) supplied nuclear steam supply system designated as BHR/5. The reactor is contained within an over-under drywell/wetwell containment vessel designated Hark II. The plant rated electrical output is 1,145 MHe.

This program plan is referenced in the HNP-2 FSAR, Section 3.9.6, and has been prepared as the controlling document governing Pump and Valve Inservice Test-ing at HNP-2. The requirements for Pump and Valve Inservice Testing are out-lined in the ASHE Boiler and Pressure Vessel 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 Subsections IHP and IHV of the ASHE Code Sec-tion XI. This program plan complies with the requirements of the ASHE Code 1980 Edition, with addenda through .Hinter, .1980 (and with addenda through Hinter, 1981), GL 89-04 and WNP-2 IST SER dated Hay 7, 1991. Specific exceptions to the Code, GL 89-04 and SER are handled on a case by case basis and documented either by reference in this IST plan or by separate corre-spondence. This is consistent with FSAR commitments and 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 subprograms the Pump Inservice Test Program and the Valve Inservice Test Program. The detailed description of the scope, implementation, and administration of these two programs is detailed in subsequent sections (3.0 and 4.0).

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Revision~

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 Introduction 3.2 Program Implementation 3,3 Program Administration 3.4 Pump Reference List 3.5 Pump Inservice Test Tables 3.6 Relief Requests from Certain IHP'Requirements 3.7 Proposed Pump Test Flow Paths e 3.8 Records of Inservice Tests.,

4.0 Valve Inservice Test Program Description 4.1 Introduction 4.2 Program Implementation 4.3 Program Administration 4.4 Valve Test Tables 4.5 Relief Requests from Certain INV Requirements 4.6 Records of Valve Inservice Tests 5.0 guality Assurance Program 6.0 Piping and Instrument Diagrams

4 Revision 3.0 HNP-2 Pump Inservice Test Program 3.1 Highly reliable safety related equipment is a vital consideration in-the oper-ation of a nuclear generating station. To help assure operability, the HNP-2 Pump Inservice Test Program has been developed. The Program is designed to detect and evaluate significant hydraulic or mechanical changes in the operat-ing parameters of vital pumps and to initiate corrective action when neces-sary. The Program is based on the requirements of the ASME Boiler and Pres-sure Vessel Code,Section XI, Subsection IHP. To the maximum extent practical the Program compli es wi th the specifications of the approved Codes< 1>, Regu-lations <2), and Generic Letters<3>.

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 HNP-2 Pump Inservice Test Program compiles with the intent of the approved Codes<1>, Regulations<2>, and Generic Letters<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 Hinter, 1980 and 1981).

2. 10CFR 50.55 a(g).

3. Generic Letter 89-04

3.2 Pr P II ~

Revi sion Surveillance testing is performed to detect equipment malfunction or de-gradation and to initiate corrective action. Since the safety related 4

pumps are normally in a standby mode, periodic testing of this equipment is especially important. The HNP-2 Pump Inservice Test Program provides a schedule for testing safety related pumps. It will be implemented as part of the normal surveillance routine.

Reference values are established and maintained in accordance with IWP-3110 and measured in accordance with IWP-4000 of the ASHE Code. In most cases, test parameters are measured with permanently installed plant instrumentation. This approach simplifies the test program and promotes timely completion of surveillance testing. When permanently installed instrumentation is not available, portable instrumentation is used to record the required parameters.

During subsequent surveillance tests, flow rate is normally, selected as the independent test parameter and is set to match the reference flow rate. Then other hydraulic and mechanical performance parameters are measured in accordance with IHP-4000 and evaluated against the appro-priate reference values in accordance with IHP-3200. The results of such evaluations determine whether or not corrective action is warranted.

Each pump in the. Pump, Test..Program is tested according. to a detai.led. test procedure. The procedure includes, as a minimum:

a) Statement of Test Purpose. This section identifies test objectives, references applicable Technical Specifications and may note the op-erating 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 mon-itors) is noted. Identification numbers, range and calibration ver-ification (IHP-4140) of instrumentation are recorded.

c) Test Instructions. Directions are sufficiently detailed to assure completeness and uniformity of testing. Instructions include provi-sions for returning system to its normal standby configuration fol-lowing testing. (For informational purposes, proposed flow paths are illustrated in Section 3.7.)

d) Acceptance Criteria. The ranges within which test data 'is consid-ered acceptable is established by the Supply System and included in the test procedure. In the event that the data fall outside the acceptable ranges, operator action is governed by approved Admini-strative Procedures.

Revision 4 e) Test Instruments. A description of instruments used.

f) Reference Values.

Finally it is recognized that the Pump Inservice Test Program sets forth minimum testing requirements, Additional testing wl11 be performed, as required, after pump maintenance or as determined necessary by the Plant Staff.

Page~~

Revision 4 3' i r Management of the IST Program Plan is controlled through NOS-34

("Inservice Testing of Pumps and Valves" ). The NNP-2 Plant Manager is responsible for implementing the testing requirements of the Program Plan. The Plant Technical Manager is responsible for development and maintenance of the Program Plan.

The IST Engineer has responsibility for preparation, review, revision and control (including distribution) of the IST Program Plan, These responsibili'ties are controlled by plant procedures. The IST Engineer will maintain the Master Copy of the Program Plan, which will contain the most recent changes to the plan.

Changes to the IST Program Plan that do not require a relief request for impractical Code requirements will be accomplished consistent with Generic Letter 89-04 and will be submitted to the Authorized. Nuclear Inspector Inservice for concurrence prior to incorporation into the Program Plan. (SER REQUIREMENT)

Changes to the IST Program Plan involving a relief request from impractical Code requirements will be accomplished consistent with 10CFR50.55a and Generic Letter 89-04. These Relief Requests will be submitted to the NRC .for review and approval prior to implementation.

(SER REQUIREHENT)

Components failing to meet test requirements will be dispositioned by the Plant's Problem Evaluation Request program, Specific responsibilities are defined in the Plant procedures.

lf U

Revision 4 3.4 P fr This list gives a brief description of each pump identified in the Pump Test Tables, Section 3.5.

CCH-P-1A, 18 The emergency chilled water pumps circulate water i'n a hydraulically closed loop. The pumps discharge into an evaporative heat exchanger and then to cooling coils used in the emergency air conditioning system for the Control Room and back to pump suction.

DO-P-1A, 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 th'e spent fuel pool and discharge through the FPC heat exchangers and, during normal opera-tion, through the..Fuel Pool Filter/Demineralizers.

HPCS-P-1 The High Pressure Core Spray pump provides emergency cooling spray to the reactor core. It is capable of in]ecting 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.

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.

RHR-P-2A, 2B, 2C The 9 ~

Revision Residual Heat Removal pumps are high capacity, low head pumps, which 4

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 wetwell e) Can assist in fuel pool cooling f) Can provide a condensing spray to the reactor head g) Provides a flow path for Standby Service Hater in case containment flooding is required.

Pumps take suction from the suppression pool in the standby operating mode.

SLC-P-lA, 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 Hater 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.

Pg~

Revision 4 35 P m I rvi 'T T 1 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 3g6 (Relief Requests).

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Revision 4

~c~ni Q Quarterly (92 day interval) test A Annual test N/A Not applicable. See Relief Requests NR Not required IHP - 4400 does not require pump speed measurement if pump is directly coupled to a constant speed motor driver.

~'

I

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IWP Parameter Lubrication Pump ASHE Code Inlet Oischarge Oifferential Flowrate, Vibration, Pump Level/ Relief Ident. Class Pressure, Pressure, Pressure, Speed, Pressure Request(s)

Pi Po- P V N RCIC-P-1 RHR-P-2A 2 RHR-P-2B 2 NR RHR-P-2C 2 NR SLC-P-1A 2 N/A N/A NR 1,2 SLC-P-1B 2 N/A N/A NR 1,2 SW-P-1A N/A N/A 1,3 SW-P-1B N/A N/A . NR 1,3

if Frm r ir 9~

Revision 4 3.6 R u NP Relief Requests identify Code requirements which are impractical*for NNP-2 and provide technical justification for the requested exception.

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

RELIEF REQUEST RP-1 n~

Revision 4

~Pm (s)

CCH-P-1A, 18 HPCS-P-1, 2 RHR-P-2A, 28, 2C OO-P-iA, 18, 2 LPCS-P-1 SLC-P-1A, 18 FPC-P-lA, 18 RCIC-P-1 SH-P-lA, 18 Section XI Code Requirement frwi h li f i Measure bearing temperature and vibration. (INP-3100)

~B

l. Except for FPC, SLC, CCH, and RCIC pumps, these pumps are vertical line shaft ("deep well" ) type pumps and are immersed in the fluid being pumped. This precludes measuring pump bearing vibration except for in-board bearings or pump motor bearings as specified in ASME/ANSI OMa-l988, Part 6.

2. INP-4300 only requires temperature measurement of "centrifugal pump bear-ings outside the main flow path". The outboard and intermediate bearings of all pumps are in the main flow path. Therefore, temperature measure-ment 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 in]ection water which returns internally to the discharge flow. The inboard bearing on HPCS-P-2 (the head bearing), SH-P-lA and 18, and OO-P-lA, 18, and 2 are cooled by the pumped fluid which returns to the discharge flow wi th no provision for temperature measurement.

3. Although the bearings for the FPC, SLC, CCH, and RCIC pumps are acces-sible, bearing housing temperature is not a good predictor of bearing condition. Hence, temperature measurement is an unnecessary requirement with unreliable results.

The Fuel Pool Cooing (FPC) and Diesel Fuel Oil (DO) transfer pumps have a history of operating at high vibration levels. These pumps are currently being evaluated by the Supply System to try and reduce vibration levels to the OM-6 upper limits . The limits established in Alternate Testing Proposed, Item 4, will ensure that required action is taken if vibration levels increase, and also ensure the pump isn't prematurely declared inoperable. The Supply System will use these higher limits until the vibration is decreased and new limits, or those of OMa-1988, Part 6 can be used. These limits are based on a reasonable deviation from the reference valve.

N'I V

'I t ~

I I!

I 4

I'

RP-1 (Continued)

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Revision 4 r in Pr All pumps will be tested at approxiately the design flow rate of the pump. Hydraulic parameters wi 11 be taken in accordance wi th ASME Section XI; and the acceptance criteria of Section XI wi 11 be used.

2. Vibration testing will be conducted in accordance with all the vibration measurement requirements of ASME/ANSI OMa-1988, Part 6.

3. Vibration alert levels and Required Action levels in accordance with OMa-1988, Part 6 will be individually established for each pump and will be specified in the surveillance procedures. An exception is for DO-P-1A, 18, 2 and FPC-P-lA, 1B. See Item 4 following.

4, The upper limit for vibration velocity for the following pumps shall not exceed:

ALERT REQUIRED ACTION FPC-1A; 1B .55 in/sec .7 in/sec 00-P-1A; 1B, 2 1.4 in/sec 1.6 in/sec 11 "/ m Measurement of vibration velocity provides more concise and consistent information with respect to pump and bearing cond) tion, 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 misleadin'g 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.

NR A n / d M 7 1 1 SER/TER

Reference:

2.1.2.1, 2.1.3.1, 2.1.4.1, 2.1.5.1 This relief request was granted with provisions that 1) all vibration requirements in ASME/ANSI OMa-1988, Part 6 be met and 2) that the pumps FPC-P-lA and -18 and OO-P-lA, -18 and -2 vibration limits specified in the relief request be reviewed and ]ustified or reestablished by May 13, 1992, or the next refueling outage (R-7) whichever is later.

P L

'1

RELIEF REQUEST RP-2

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Revision 4

~Pm (s)

SLC-P-1A SLC-P-18 Section XI 'Code Requirement rw li Measure pump inlet pressure, Pi, and pump differential pressure, DP.

(IWP-3100).

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'equirements specify system alignments which assure adequate NPSH for the pumps.

3. There is no provision for suction pressure instrumentation.

4. Acceptable discharge pressure Zuf flowrate wi 11 suffice as proof of adequate suction pressure.

1 n T i Pr Pump discharge pressure and flowrate will be measured and recorded during testing.

li f 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 re-quired by IWP-3200.

N A / 0 M 7 1 1 SER/TER

Reference:

2.2.1 This relief was granted as requested.

RELIEF REQUEST RP-3 Pg~

Revision 4

~(s)

HPCS-P-2 SW-P-1A SW-P-1B Section XI Code Requirement r whi eli f Measure pump inlet pressure, Pi, and differential pressure, P. (IWP-3100)

~B~R (1) SW-P-lA, 1B and HPCS-P-2 are vertical line shaft type pumps which are immersed in their water source. They have no suction line which can be instrumented.

(2) Technical Specifications 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 eighteen (18) inches of water or 0.7 psi. This small difference will not be significant to the Test Program and suction pressure will be con-sidered essentially constant.

(4) Acceptable flowrate and discharge pressure will suffice as proof of adequate suction pressure.

1 rn T i Pr Spray pond level and pump discharge pressure wi 11 be recorded during the test-ing of these pumps.

li /

The effect of setting the Code Acceptance Criteria on discharge pressure instead of differential pressure as specified in the Code will have no negative impact on detecting pump degradation. A review of the discharge gauge reading, which is uncorrected for elevation, compared to differential pressure readings shows that basing corrective action on discharge pressure is slightly more conservative than basing it on differential pressure for these pump installations'R A an / 0 e Ma 7 1 1 SER/TER

Reference:

2.3.1 This relief was granted with the provision that acceptance criteria be assigned to discharge pressure that gives equivalent protection provided by the Code for D P.

Revision 4 RELIEF REQUEST RP-4 DELETED PRIOR TO 'ER REVI H' f

Revision 4 RELIEF REQUEST RP-5 00-P-1A DO-P-1B DO-P-2 Section XI Code Requirement F r Hhi R f IHP-4600. Flow rate shall be measured using a rate or quantity meter instal-led in the pump test circuit."

i r A rate or quantity meter is not installed in the test circuit. To have one installed would be costly and time consuming with few compensating benefits.

Al rn in Pr Pump flow rate wi 11 be determined by measuring the volume of fluid pumped and dividing by the corresponding pump run time. The volume of fluid pumped will be determined by the difference in fluid level in the day tank at the begin-ning and ending of the pump run time (day tank fluid level corresponds to volume of fluid in the tank). The pump flow rate calculation methodology meets the accuracy requirements of IHP-4110-1.

1 i f Im The day tanks are horizontal cylindrical tanks with eliptical ends. The tank fluid volume is approximately 3,200 gallons. Fluid level measurement is accurate to an eighth inch which corresponds to an average volume error of approximately 11 gallons. The test methodology used to measure pump flow rate will provide results consistent with code requirements. This will provide adequate assurance of material quality and public safety.

NR A / 0 M 7 1 1 SER/TER Reference 2.4.1 The relief request was granted with the provision that the calculated pump flow rate meets the accuracy requirements of Table IHP-4110-1 for flow rate.

+

I Revision RELIEF REQUEST RP-6 DO-P-1A DO-P-1B DO-P-2 Section XI Code Requirement F W i i IWP-3100. Inlet pressure (Pi) shall be measured before pump startup and during test.

I I f

The storage tanks from which these pumps take suction are horizontal cylindrical tanks, twelve feet in diameter, and a volume of 60,000 gallons (except for DO-TK-2 which is 50,000 gallons). The storage tanks are significantly larger than the 3200 gallon capacity day tanks to which these pumps discharge. The change in storage tank level during the course of a pump operability test results in an insignificant change to suction pressure.

Since the system is not instrumented for suction pressure measurement, suction pressure is determined by measuring storage tank level. Storage tank level increases when the pump starts, so accurate suction pressure measurements cannot be determined while the pump is running.

1 T Pr Suction pressure will only be determined prior to pump startup. This will contribute to uniform fluid density and accurate level measurements resulting in an accurate suction pressure measurement, ,The calculated pump inlet pressure meets the accuracy requirements of IWP-4110-1.

Qu li / m Not measuring pump inlet pressure during test for these pumps will have no adverse effect on determining the operational readiness of these pumps. The relevant pump operability parameters are measured and evaluated consistent with code requirements. This will provide adequate assurance of material quality and of the operational readiness of these pumps in the i nterest of public safety.

SER/TER

Reference:

2.4.2 Relief request granted provided pump inlet pressure is calculated based on the height of the fluid level above pump suction and the calculation accuracy meets Table IWP-4110-1 accuracy requirements.

RELIEF REQUEST RG-1 g~

Revision 7 1 Relief request denied.

SER/TER 2.1.1.1

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Revision 4 REQUEST FOR RELIEf NO. RP-7 Al 1 Section XI Code Requirements FrHi hR li f R IWP-3100 - Vary the system resistance until either the measured differential pressure or measured flow rate equal s the corresponding reference value.

8

l. It is very difficult to adjust flow on some systems such as Service Hater. These systems must be flow balanced to achieve proper performance.

2. Inaccuracies can result if a system is set close to the reference flow but not precisely on it.

3. The Code allows multiple reference points. This is an expansion of that philosophy.

1 i p A reference curve is established for each pump from data taken on that pump.

The pump data is taken with the pump in its normal lineup that will be used in subsequent inservice tests.

The reference curves are based on flow rate with the acceptance criteria curves based on 'differential or discharge pressure as appropriate. See the attached sample SH-P-1A Acceptance Criteria Sheet. Area 1, 2, 3, 4 is the acceptable range for pump performance. Areas outside 1, 2, 3, 4 but within 5, 6, 7, 8 are the Alert area, and the area outside of 5, 6, 7, 8 is the Required Action range.

For RCIC-P-1, a variable speed pump, flowrate is set (currently +21., -lX of the reference flow rate) and'he reference curve is based on speed with acceptance criteria based on differential pressure. This is done because of the difficulty in setting speed as specified by the Code.

If a minimum flow rate is applicable, e.g. Technical Specification limits, it wi 11 be shown as to bound the required action area.'he reference curve is established only for the area of anticipated testing.

This is typical.ly within, plus 5'/ or minus 101. of the reference flow. Host systems will be tested at a very near (+2'1) of a particular flow point.

RP-7 All (Continued) pumps are tested at essentially full design flow rate.

P II ~

Revision 4 Vibration data is taken at the reference point which is anticipated to be used during subsequent tests. It is not expected that pump vibration would change over the narrow range of the curve. Note that the code only requires vibration data at the reference point and if the pump degraded to 957.'f the reference point additional data is not requir'ed.

i f The effect of granting this relief will have no adverse impact on plant safety. It is expected that the quality of the testing program will be enhanced by getting slightly better, more trendable data.

'1 Pending

I A

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RP-7(continued) P, ~6-12 Revision 4 SW-P-5 ACCEPTANCE CRITERIA 230 225 220 215 210

~205

~

200

+~ .195 190 180 8800 9000 9200 9400 9600 9800 10000 10200 10400 FLOWRATE - GPM ALERT RANGE = Area Outside 1-2-3-4 ACTION RANGE = Area Outside 5-6-7-8

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Revision 4 3.7 r These flow paths are proposed for use during pump and valve testing.

Surveillance procedures define actual system lineup for testing pumps and valves.

V-78 I 8 V-78 I A

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/3 r V-823A ~ FE-35A TCV-I IA V-1 040 r'-227A CCH 3

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3,8 r n vj T Records, of Pump Inservice Test results will be maintained in accordance with Article IWP-6000 of the Code . The files wi 1 1 contain the following:

1) Pump identification by equipment 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 WNP-2 plant site. For informational pur-poses, a sample pump test data sheet is provided.

P Revision 4 AMP 0 TA H T PUMP OPERABILITY DATA SHEET FOR LPCS-P-1 Refer Action hlett Measured A!crt Amion Test Parameters Value Lo(+ 1) Lo(+1) Value K(+ 1) K(+ 1)

Driver Lubrication NA SAT NA NA NA UNSAT Suction Pressure before pump PSIG 16.6 7.7 NA start per LPCS-Pf-1 Pump Lubrication iVA SAT NA NA NA UNSAT Suction Pressure at test flow PSIG 16.0 NA iVA per LPCS-Pf-1 Discharge Prcssure pcr PSIG NA NA iVA TDAS lSS or (LPCS-PI-3)

DiPcicntial prcssure dp PSID 31$ (+2) (+3) (+3) (4 2)

(Discharge Pressura4uction Prcssure)

Howrate per TDAS 164 GPM 6350 l 6350 Nh 6541 (or LPCS-HAOO)

Fluid Temperamre N* NA NA NA iVA CMS-TR-5 FP"0 hfotor Voltage Per E.FI-SM7 NA NA iVA ViA Motor Current Per LPCS-AM-1 AMP NA iVA NA iNA NA Outboard Motor Bearin 'F NA ViA NA Nh iVA Tcmperamre Per W12S Outboard Motor Bearing NA Nh NA iVA Temperature per W129 Inboard Motor Bearing Nh NA Nk Temperature per W130

(+ 1) For measured values beyond the Alert Value or Action Value refer to Precaution and Limitations 4.6 or 4.7, respectively.

(+2) The ACTION RANGE is defined as outside the area dcsert~ by points S, 6, 7 and S on Aaachmcnt 9.4.

(+3) Tha ALERT RANGE is denned as outside the ara described by points 1, 2, 3 snd 4 on hnachmcnt 9.4.

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Page 4.1-1 Revision 4 4.0 WNP-2 Valve Inservice Test Program 4.1 Hashington Public Power Supply System Nuclear Pro]ect Unit 2 (HNP-2) is a Boiling Hater 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 HNP-2 Valve Inservice 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 IWY 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 gr 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 IHV 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 Inservice 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 HNP-2 Valve Inservice Test Pro-gram complies with the intent of all applicable Codes, Regulations(1),

and Generic Letters(2) and contributes to ensuring the safety of the general public.

(1) 10CFR 50.55 a(g)(2)

(2) Generic Letter 89-04

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Revision 4 4.2 The Valve Inservice Test Program is executed as part of the normal plant surveillance routine. Two types of tests are conducted as part of this Program:

1) 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 INV of the Code will verify 1) the valve responds to control commands including its fail safe response if applicable,

2) the valve stroke time is within specific limits and, 3) remote posi-tion indication accurately reflects the observed valve position. Base-line data for stroke times has been obtained from initial Valve Operability Tests. The initial Valve Operability Tests have met the requirements for preservi ce testing (INV-3100) . The limiting values of stroke times are stated in the test procedures.

Reference values, as. stated above,. are obtained from baseline tests or post maintenance tests. Many times the reference values are more accurately determined by an average of stroke times. This practice is in accordance with postion 5 of GL 89-04.

Fail safe valves as identified by the valve test tables are 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.

Subarticle INV-3420 of the Code specifies that valve leak rate tests are required for category A valves.

The category A valves identified in this program and their associated leak testing requirements are implemented using a leak testing program which maximizes compliance with the various requirements and commitments, provides consistency in test methodology and reduces duplication of effort.

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Valves in the Valve Test Program are tested according to detailed proce-dures. The procedure includes as a minimum a) Statement of Test Purpose. This section identifies test ob]ectives, references applicable Technical Specifications and notes the operat-ing modes for which the test is appropriate.

b) Prerequisites for Testing. System valve alignment and additional instrumentation (e.g., stop watch) is noted. Identification num-bers, range and calibration verification of additional instrumen-tation is recorded.

c) Test Instruct1ons. Directions are sufficiently detailed to assure completeness and uniformity of testing. Instructions include provi-s1ons for returning the system to its normal standby configuration following testing.

d) Acceptance Criteria. The ranges within which test data is consid-ered acceptable has been established by the Supply System and included in the test procedure. In the event that the data falls outside the acceptable ranges, corrective action is governed by approved Administrative Procedures.

e) Reference Values.

Finally it is recognized that the Valve Inservice Test Program sets forth minimum test1ng requirements. Additional testing will be performed as required per INV-3000, after valve maintenance, or as determined neces-sary by the Plant Staff.

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Revision 4 4.3 Pr A ini i n The Valve Inservice Test Program is administered in a manner analogous to the Pump Inservice Test Program.

Page 4.4-1 II The Valve Test Tables are the essence of the. Supply System's Program to meet ASME Section XI, Subsection INV requirements. The Tables include active valves which are required to operate in order to safely shutdown the reactor or mitigate the consequences of an accident and passive valves which require leak rate testing. The Tables reflect the positions taken in support of the relief requests.

Page 4.4-2 Revision 4 To aid in the interpretation of the Tables, brief explanations of the Table headings and abbreviations are provided.

Each piece of equipment in the plant has a uni-que "tag" number which identifies the system to which the equipment belongs, the type of equip-ment (flow control valve FCV, relief valve RV, rupture disc RD, etc.), and a unique serial number.

ASME Code Class per Section III of the ASME Boiler and Pressure Vessel Code. These are roughly equivalent to the safety classes de-fined in Chapter 3 of the FSAR.

i n P D The specific coordinates of each valve are sup-plied to facilitate location of the valves on the flow diagram (PAID - Piping 5 Instrumenta-tion Diagram) provided.

Categories A, 8, C, and D are defined by ASME Section XI, subsection INV. Each valve has specific testing requirements which are deter-mined by the category to which it belongs.

Category A Containment Isolation Valve (CIV) per FSAR (Table 6.2-16).

F -P Passive Category A CIV per FSAR ~

Category A CIV per FSAR and a high-low pressure boundary valve per Technical Specifications.

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Revision 4 NOTE: The designation of Category A valves with a "T" or "F" is intended to be an informa-tional courtesy. A change to the referenced portion of the Technical Specification and FSAR may not necessitate a revision to this Program.

Nominal pipe diameter to which the valve con-nects is given in inches.

The following abbreviations are used to de-scribe valve type:

BF - Butterfly valve RD Rupture disc.

CK Check valve RV Relief Valve DIA Diaphragm valve SC Stopcheck valve GB Globe valve SHEAR Shear Valve GT Gate Valve S/R Safety/Relief Valve PLUG Plug Valve SV Solenoid Valve 3-HAY Three Nay Valve The following abbreviations are used to de-scribe actuator types. Valves may be actuated in more than one way.

AO Air operated EXPL Explosive Charge Actuator 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 va)ves).

SOL Solenoid operated

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Revision 4 (8) N 1/F 1 P i i n This column identifies the,valve's normal posi-tion and failed position.

4 FAI Fail As Is NA Not Applicable FC Failed Close NC Normally Closed FO Failed Open NO Normally Open LC Locked Close NT Normally Throttled (9) ri Fr This column identifies the required testing frequency for exercising the valve in accor-dance with INV-3410 or INV-3520 as applicable.

quarterly To be tested at least once every 92 days.

f Cold shutdown To be tested as often as cold shutdown conditions occur, but not required to be tested twice in the same quarter. Valve testing shall commence within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after cold shutdown is achieved and continue until complete or until the plant is ready to return to power.

Cold Shutdown with Containment Oe-Inerted Same as "C" but the containment must be deinerted.

Refueling To be tested as often as refueling outages occur. At least every 18 months.

Not Applicable No stroke testing is required.

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Revi sion 4 This column lists a code corresponding to the test requirements applicable to that valve.

Test requirements will be as stated, except as modified by referenced notes and requests for rel i ef.

INV-3300 Verify the accuracy of remote posi-tion indicators.

INV-3412 or INV-3520 (for check valves) Full stroke exercise the valve to its required posi-tion.

INV-3413 Measure the stroke time of power op-erated valves.

INV-3415 Operabi 1 i ty verification of val ves with fail-safe actuators.

INV-3420 Valve Leak Rate Test.

INV-3510 Safety and relief valve operability test.

INV-3610 Operability test for explosively actuated, valves.

INV-3620 Rupture discs shall be tested per manufacturer's instructions.

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Revision 4 This column is used to provide reference to ex-planatory notes located at the end of the Valve Test Tables.

This column is used to cross reference documen-tation which requests waiver of certain code requirements. A valve may have more than one associated relief request.

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hlNP-L PUHP AND VALVE IHSERVICE TEST PROGRAH VALVE TEST TABLES Revision 41 Page 4,4-07 4 QQQQQQCIDQQQCQQQQD4 QQQ4 4 crracrr air Ir rr rr 4 4 4 aaaacaaa aaarraarr 4 aaar aaaacaaaa Qaca- acacaca Q 1lacrra aaaaaarrcaa VALVE CODE LOCATION VAI.VE SIZE 1th VAI.VE ACTUATOR --POS I T ION--- EXER. TEST CODE NOTES RELIEF thUNDER CLASS 0th PIIID CATECORY INCHES TYPE TYPE NORIIAL FA1LED FRED. REQUESTS Q cl DQ QQQDQCQ Cc QQQCQ aaacaaaa 4 aa a 4 carr DCCQC DcaccQlra 4 1I a cr a a a 4 rr 4 4 a a 4 4 a I1 c DCQCCCQCC D rr 4 4 Q 4 4 4 rr 4 QCDQQD QCC CAC-FCV-IA HID 2.5 GD HO NC FC GHJKL ~ . ~ Ir 4120 II554 CAC-FCV-18 Hb F 2.5 CD HO WC FC Q GHJKL.. ~ 4120 tl5 5 4 CAC-FCV"2A GIO. F 2~5 GB HO NC FC 0 GHJKL... I ~ 4 ~ 20 N554 CAC"FCV-28 Gb F 2' GB HO NC FC Q GHJKL. ~

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WNP-2 PUNP AND VALVE INSERVICE TEST PROGRAM VALVE TEST TABLES Revision 4 Page 4.4-08 aaaazscacasaccaasasa:s al a asa aaaasaccc saaccaas aaaaassss saaaac sacasaas as acaasa aac asses a c c c c aa aa c aa aaasaascaa csaaascaas VALVE CODE LOCATION VALVE SILE IN VALVE ACTUATOR --POS I T I Otl--- EXER. TEST CODE NOTES RELIEF NUtlDER CLASS Otl Pt ID CATECORY ItlCHES TYPE TYPE NORtlAL FAILED FREO. REQUESTS casasasasaaasca:access a a aa a s caaascaa aacscscc cases aacssssa ccaaaaaasasaa a aa c s saaaaaaaas saasaaaaaas asasaaaacaa CAC-V-2 Gl0 F 4 GT HO tlC "

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IIIIP-2 PUNP AND VALVE INSERVICE TEST PROGRAH VALVE TEST TABLES Revision 41 Page 4.4-09 ascaareec acacccc scarce aarrcacaaa eeceeccc=a==a ~ e ee c ee c D ee D ee c c CCCDD sccDDCCD a a a ee a c ee a a c a c a asreeccrrr VALVE CODE LOCATION VALVE SI IE IN VALVE ACTUATOR --POSITION--- EXE R. TEST CODE NOTES RELIEF NUMBER CLASS ON PhID CATEGORY INCHES TYPE TYPE tfORMAL FA ILE9 FRED. REQUESTS cccseecaarrcssceecacac reer ~ cccccra ee CDC caeear eeeecsacsc ee c a D a ee r Da a c a D sssas ascsacraa careers Daa ac cacaaeea CEP-V-2A J13 30 DF AO NC FC Q GHJKL ~ ~ . 4e20 M543 1 CEP-V-2B 2 J13 M543 1 F 2 GB AO NC FC Q GHJKL ~ ~ ~ 4 '0 CEP-V-3A 2 C14 F 24 BF AO NC FC Q GHJKL ~ ~ ~ 4e20 M543 1 CEP-V-39 2 C14 F 2 CD AO NC FC 0 GHJKL ~ .. 4e20 M543 CEP-V"4A C14 F 24 BF AO t<C FC 0 GHJKL.. 4e20 M543 1 CEP-V"49 2 C14 F 2 GD AO NC FC 0 GHJKL 4e20 M543 1 CIA-RV-5A 3 Hl 1 C ~ 75 RV SA NC tlA tl ... ~ .P..

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CIA-SPV-1A THRU 15A 3 G12 9 ~ 5 SV SOL NC FO C .H.K ~ 1Me8 tl5 5 6 1 CIA-SPV-19 THRU 199 3 912 tl556 B .5 SV SOL NC FO C .HE K .. ltle8 24 1

CIA-V-20 KB tl556 F ~ 75 CD MO NO FAI Q GHJ L... 4e20 CIA-V-21 Kb FC ~ 75 CK SA e

tlO N* R .H ~ .LE ~ ~ 3e 4 tl556 1 CIA-V-30A G9 F .5 CB MO NO FAI Q GHJ.L... 4e20 tl556 I CIA-V-309 F8 MO NO FAI 0 GHJ ~ L ~ ~ ~ 4e20 M556 1 CIA-V-31A G7 FC 5 CK SA NO NA R eH ~ ~ LE ~ 3e 4 M556 1 CIA "V-319 2 F7 FC .5 CK SA NO thA R AH..L~ . ~ 3e 4 M556 I CIA-V-39A J10 9 ~ 5 GD AO NO FC C GHJK . . 11 20 tl556 1 C I A-V-399 E10 B ~ 5 CB AO tlO FC C GHJK.... 11 20

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WNP-2 PUNP ANO VALVE INBERVICE TEBT PROGRAN VALVE TEST TABLEB ReVision 41 Page 4.4-1Q oc acssc c sass o oo cao a c o ca cs o o o s cocaosa o aooocaoo ssaosss ascaaassaacs a c o a ca s s a a a a sa sa sssasa aaoosaa a saassassaaca aasaaaocaca VALVE CODE LOCATION VALVE S I I E I tl VALVE ACTUATOR I OSI TION - EXER. TEST CODE NOTES RELIEF tlUtlBER CLASS ON I sin CATEGORY I tlCHES TYPE ':

TYPE NORtlAL FAILED ,FREQ. REQUESTS sacaooaossaaaoasccocaao oases c o a ss cc c a o acaacasaa o o o o o o cs c casse ococ cao scosaooaaoosaa ~ a a as o cc s o o a a a a a sa acsaoaaa asa ocsasscsaa CIA-V-40 lTYP 71 2 J5-85 AC ~ 5r CK SA NO NA R .H..L... 3~ 7 tl556 1 CIA-V-52A THRU 66A G12 tl556 1 C .5 CK SA NC NA C .H. ~ .... 1H CIA-V-528 THRU 708 3 C12, C .5 CK SA NC tlA C .H. ~ .... 1N tl556 I CIA-V-103A H13 C ~ 5 CK SA NC NA C .H.... ~ ~ ltl tl556 1 CIA-V-1038 D12 C CK SA NC NA C .11. ~ ~ . I tl H556 1 CIA-V-104A H13 tl556 1 8 ~ 5 CB HAN NC NA C .H. ~ ~ ... ltl CIA-V-1048 D12 8 ~ 5 GB HAN tlA C .H. .~ .. Itl tl556 I

, CRD-V-10 2 K6 8 I CB AO NO FC Q GHJK ~ ~ ~ 14 ~ 20 tl52S CRD-V-11 Fb tl528 AO NO FC Q GHJK.. ~ . 14 '0 CRD-V-180 GB AO tlO FC Q GHJK ~ ~ ~ ~ 14r20 t1528 CRD-V-I 8 I F*

tl528 8 CD AO NO FC Q GH JK ~ ~ ~ ~ 14 '0 CSP-V-1 2 D6 F 30 BF AO NC FC Q GHJKL . ~ 4r20 HS43 1 CSP-V-2 D6 30 BF AO NC FC Q CHJKL ~ ~ ~ 4r20 tl543 1 CSP-V-3 2 C5 F 24 BF AO NC FC GHJKL. . 4r20 tl543 1 CSP"V-4 C5 a24 BF AO NC FC Q GHJKL ~ . ~ 4r20 tl543 CSP-V-5 2 C5 F 24 BF AO NC FO Q GHJKL... 4r20 tl543 1 0

CSP-V-6 2 917 F BF AO FO GHJKL... 4r20 H543 CSP-V-7 C5 FC 24 CK AOrSA NC tlA Q GH..L... 6

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WNP-2 PUHP AND VALVE INSERVICE TEST PROGRAH VALVE TEST TASLES Revision 4t Page 4.4-11 sssseessasasasaaaasss Saic je re Das serrea eesD ress a casa ri sisccs s s s D Dace SD SD C DS cssDai a VALVE CODE LOCAT10N VALVE SITE IN VALVE ACTUATOR --POS1T ION- EXERT TEST CODE NOTES REL1EF i

NUtlBER c ee 4 s 4 4 s el 4 4 4 4 4 re 4 4 l1 s 4 CLASS SD ri Otl Ptr ID i a Casa CATEGORY sscerssas INCHES assicaasa TYPE 1 acies TYPE assasaas NORtIAL FAlLED a re 4 ee s a 4 a 4 a a s ee FREON csa cseecaaaaa DCDSSDDSDC REQUESTS asseeaasaaa CSP-V-8 814 FC 24 CK AOesA NC NA GH..L...

tl543 I CSP-V-9 86 F 24 OF AO NC FO Q GHJKL ~ ~ .

M543 1 CSP-V-10 2 D6 FC 24 CK AOrSA tIC NA Q GH. ~ L... 6 M543 1 CSP-V-93 2 F5 F I SV SOL NO FC Q - GHJKL ~ ~ ~ lr M783 CSP-V-96 2 H4 F 1 SV SOL NO FC Q 'HJKL ~ ~ ~ 1 ~ 4 M783 CSP-V-97 2 H4 F SV SOL NO FC Q GHJKL. ~ fr 4 M783 CSP-V-98 F5 F 1 SV SOL NO FC Q GtIJKL ~ .. 1 r 4 tl783 CVB-V-IA B12 AC 24 CK AOrsA NC NA Q GH..... 6 tl543 1 CVB-V-lB 2 812 AC 24 CK AO e SA tlC IIA Q GH ~ ~ ~ r M543 1 CVB-V-lC 2 812 AC 24 CK AOrsA NC NA Q GH... ~ .. 6 6 M543 1 CVB-V-ID 812 AC 24 CK AOrSA NC NA Q GH.... ~ ~ 6 6 tt543 1 CVB-V-IE 2 811 M543 AC 24 CK AOrsA NC NA Q GH. ~ ..r. 6 1

CVB-V-1F 2 Bl 1 AC 24 CK AOeS* NC NA Q GH 6 6 M543 1 CVB-V-1G 811 AC 24 CK AOrsA NC NA Q Gtl......

M543 I CVB-V-lH Bl 1 AC 24 CK AOiSA NC ttA Q GH...... 6 M543 1 CVD-V-IJ 89 tl54 3 I 24 CK, AO,SA tlC tlA Q GH.. ~... 6 CVB-V-IK 2 89'C M543 I 24 CK AOrSA NC NA Q Glt..r... 6 CVD-V-I I. 88 AC CK hOrsh NC NA Q liH...... 6 6

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WNP-2 PUHP AND VALVE INSERVICE TEST PROGRAM VALVE TEST TABLES Revision 41 Page 4.4-12 Dccccscssscssscs ac scscsccc sccscass ccac c s sssss Sc DCDDS sssaasacscsall DSQSD SSCDCCCQQ aacssscass sacscccacc VALVE CODE LOCATION VALVE SIZE IN VALVE ACTUATOR --POSITION--- EXER- TEST CODE NOTES RELIEf NUtrBER CLASS ON earn CATEGORY INCHES TYPE , TYPE, NORtlAL FAILED FREQ.

ccasaacsss REQUESTS DQDQQDQCCCCCQCDDDSCS QCQSQ CDSQQCDD CSCQCQSQ CQ C Q CQDQS QQDCSQSS SSCCSSDDDDCDQ CDCDC ssacscacc DQDSSSDDSQ CVB-V-ltl 2 99 AC 24 CK ADA SA t(C NA Q GH ~ ~ ~ ~ ~ ~

tl543 1 CVB-V-IN 88 AC

=

24 CK AOzSA NC - NA Q GH ~ ~ ~ ~ ~ 6 tl543 1 CVB-V-1P 89 AC 24 CK AOeSA tlC NA Q GH.... ~ . 6 tt543 1 CVB-V-10 97 AC 24 CK AOlSA NC NA Q GH..... 6 tr543 1 CVB-V-lR 97 AC 24 CK AOeSA NC NA Q GH ~ ~ ~ ~ ~ ~ 6 tr543 1 CVB-V-1S 87 AC 2 AO ~ SA NC tlA Q GH. ~ ~ ~ ~ . 6 tl5 4 3 CVB-V-lT 2 87 AC 24 CK AO ~ SA NC NA Q GH ~ ~ ~ ~ ~ ~ 6 tr5 4 3 DO-V-1A J12 1.5 SA tlc NA Q ~ H~ ~ ~ ~ ~ ~

tr5 1 2 DO-V-18 F12 C 1 +5 CK SA NC NA Q AH-.- ~

tl51 2 4 DO-V-10 CB C 1.5 CK SA NC NA Q .H..

t1512 1 DSA-SPV-SA1/2 F10 9 2 3-WAY SOL NC FAI A ~ HJ. . ~ ~ o 12 tl512 2 DSA-SPV-5A1/4 E10 8 2 3-HAY SOL NC FAI A .HJ....o 12 tl512 2 DSA-SPV-5A2/2 F6 8 2 3-MAY SOL NC FAI A .NJORD ~ ~ 12 tr512 2 DSA-SPV-5A2/4 D Eb 9 2 3-ltAY SOL NC FAI A ~ HJ ~ o ~ ~ 12 tl512 2 DSA-SPV-591/2 9 F10 9 2 3-1IAY SOL NC FAI A HJ... 12 t1512 3 DSA-SPV-581/4 Elo 9 2 3-rtAY SOL NC FAI A .HJ.." .. 12 H512 3 DSA-SPV-582/2 Fb 9 2 3-llAY SOL NC FAI A .HJ. ~ ~ ~ . 12 tr51 2 3 DSA-SPV-592/4 Eb 3-MAY SOL NC FAI ~ HJ ~ ~ .~. 12 ll l '0

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WHP-2 PUHP AND VALVE INSERVICE TEST PROGRAH VALVE TEST TABLES Revision 4t Page 4.4-I3 ssasaaaaa scars-saaaaa sasrs sarsa asssss s ssscscssss sssrs Ds asar acssssssarsssa ~ s sc ss s a D a ss s s cs a s ss a sc s a a ss a a a a a ss ss VALVE CODE LOCATION VALVE Sl ZE Itt VALVE ACTUATOR --POSITION"-- EXER. TEST CODE ttOTES RELIEF NUtlDER CLASS Ott PtslD CATEGORY IttcttES TYPE TYPE NORtlAL FAILED FREO. REOUESTS rssasaccssssssssrsssr D Dsssrsrs r s DDss rss ssssarssssssa D r ssssssssr s Dssssass aassssrss DSA-SPV-5Cl/1 E9 3-WAY SOL NC FAI ~ HJ ~ ~ ~ o ~

tl51 2 1 DSA-SPV-5C1/2 F9 M512 1 B 2 3-WAY SOL NC FAI A'HJ.... ~ 12 DW-V-156 2 GB . F -P GT HAN LC NA N .. .L...

~ 4 M517 DW"V-157 GB F -P 2 GT HAN LC ttA N ~ ~ ~ ~ L~ ~ ~

M'517 EDR-V-19 D9 F 3 GT AO NO FC tl537 EDR-V"20 2 D9 M537 F 3 GT AO NO FC 0 GHJKL ~ ~ ~ 4 '0 FDR-V-3 2 D6 tl539 F 3 BALL AO NO FC 0 GHJKL ~ ~ ~ 4 '0 FDR-V-4 Db F 3 BALL AO NO FC 0 GtlJKL ~ ~ ~ 4I20 M539 FPC-RV-117A Dl I C .75 X 1 RV SA tlC NA N . ~ ~ ~ .P. ~

M526 FPC-RV-117B 3 Cl 1 C .75 X 1 RV SA NC NA N ~ ~ ~ ~ ~ P ~ ~

tl5 2 6 FPC-V 112A D12 C 6 CK SA . NC NA ~ H~ ~ ~ ~ ~ ~

M526 FPC-V-1120 D12 C 6 CK SA NC NA 0 ~ H~ ~ ~ ~ ~ ~

M526 FPC-V-127 3 E9 C 2 CK SA NC 0 H~ ~ ~ ~ ~

FPC-V-140 C9 C 8 CK SA NO NA 0 ~ H~ ~ ~ ~ ~

M526 FPC-V-146A 3 Kll C B CK SA NO NA 0 .H......

tl526 FPC-V-1460 3 K10 C S Ct( SA NO NA 0 olto ~ ~ ~ ~ ~

tl526 FPC-V-149 D9 M526 MO NC FAI 0 GHJ ~ L ~ ~ ~ 4 '0 FPC-V-153 Bl 1 CT MO NC FAI 0 GttJ L 4 ~ 20

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WNP-L PUMP AND VALYE INBERVICE TEBT PROGRAH VALYE TEST TABLES Revision 4) Page 4.4-I4 Q a Q Q Q a Q a a cc a Q Q cc Q a cc s Q s QQQQQ asaasaaQ sassaaaa QQ Qasas asasa sasasssa asssccssaasaas assaa a lc lc Q s Q Q Q a Qsasaasaaa a s Q s Q cc Q s Q a VALVE CODE LOCAT ION VALVE 5 I LE IN VALVE ACTUATOR --POSIT10N--- EXER. TFST CODE NOTES RELIEF NUtlDER a=a=ass=accaaccaaaccrccs CLASS aaaaa OW P&19 aaccaaaaa CATEGORY Qsac Qaaa I NCI IE9 Q QQ TYPE Qs Q TYPE aa aaa f

NORtIAL A ILED Qas ass Qaaaacc FREO.

assccsaccaa r ssssaaa REQUESTS aassaaaasa FPC-V-154 2 911 F GT NO NC FAI GHJ L.r ~ 4120 N526 FPC-V-156 CII F 6 GT ND NC FAI 0 GHJ.L. ~ . 4120 tIS26 FPC-V-172 C9 9 8 GT NO NO FAI 0 GHJ..... 3 20 t)526 FPC-V-173 9 8 GT )IO NO FAl 0 GHJ... ~ 3 20 tl526 FPC-V-175 C9 9 8 GT NO NC FA1 8 GHJ ~ ~ ~ . 3 20 tl5 2 6

~

FPC-V-181A D14 tI526 9 8 NO NO FAI Q GHJ HE

.... 3 20 FPC-V-1819 D14 9 8 GT IIO NO FAI 0 GHJ..... 3 20 II526 FPC-V-184 C9 9 GT NO NO FAl 0 GHJ... ~ ~ 3 20 tl526 HCU-V-114 ITYP 185) D C2 C ~ 75 CK SA NC NA HE ~ ~

HS28 HCU "V-1 15 I TYP 185) C5 C I CK SA tIC NA .H ~ ~ ~ ~ ~ ~ 11 tl5 28 HCU-V-126 I TYP 185) D C4 9 1 GD AO NC FO .H..... ~ 11 t)528 HCU V-127 ITYP 18S) C3 .75 GD AO FO H.....c 11 tl528 HCU-V-138 I TYP 185) C4 C .75 CK SA NO tIA ~ H~ ~ ~ ~ ~ ~

tl5 2 8

'0 HPCS-RV-14 2 Ch FC 1XI RV -

SA NC NA N ~ ~ ~ ~ ~ P ~ ~

N520 HPCS-RV-3S 2 C4 FC IX2 RV SA tlC NA N ~ ~ ~ ~ P ~

tl520 HPCS-V-I Ch 9 14 GT tIO NO FA1 0 GHJ ~ ~ ~ ~ ~

NS20 HPCS-V-2 Cb~ CK SA NA 0 ~ ... ~

NS20 IIPCS-V"4 G7 12 GT HO tlC FA I 0 GH J ~ L~ ~ ~ 4 ~ 20 11 ~

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HHP-2 PUHP AHD YALYE IHSERYICE TEST PROGRAN YALYE TEST TABLES Revision 41 Page 4.4-l5 cccaacaccaa Q acacaa QDCQQ DDQQDDQQ Q Qcaca QIe D Daaacaac QQQcQa Qa c Q a c ee D QQCQ a IIIID ee a Ie Q C Q Ie Q Q C D D Q Q D D eeaeIDCQQQ VALVE CODE LOCAT ION VALVE Sl ZE 1N VALVE ACTUATOR --POSITJON--- EXER TEST CODE NOTES RELIEF NUNBER CLASS ON PtIID CATEGORY. 1NCHES TYPE TYPE NORtlAL FAILED FREQ. REQUESTS aaaaaacaccccacaacaca C II cc a CCCQ C aaaaaaaa Caaaeeaacaaaca QQQ a Q ca Qaa aaacaacaaa HPCS"V-5 II8 TC 12 CK AO ~ SA NC NA GH..L... 40 V M520 HPCS-V-6 C5 C I~5 SC SA I tlAtl NO tlA Q ~ ~ ~ ~ ~ ~ ~

tl520 HPCS-V-7 C5 . C 1.5 CK SA NO tlA Q AH.. ~ ... 17 tI520 HPCS-V-10 2 E3 B 10 GB HO NC FAI Q GHJ.. ~ . ~ 20 H520 HPCS-V-11 2 E3 B 10 CB IIO NC FAI Q CHJ ~ .~. 20 II520 HPCS"V-12 2 95 N520 F 4 GT II0 tIC FAI Q 'HJ.L... 4 '0 HPCS-V-15 2 D7 tl520 F 18 CT tl0 NC FA1 OH'... 4020 HPCS-V-16 Eb C 24 CK SA NC NA 9 .H . ~ ..

II520 HPCS-V-23 E4 F 12 GB NO NC FAl Q GHJ ~ Le 0 ~ 4020 N520 HPCS-V-24 2 95 C 16 CK SA NC NA Q I ~ I ~ ~ ~ ~ ~ ~

II520 HPCS-V-28 3 Cb tl 524 1 C 8 CK SA NC NA 0 .H . ~ ...

HPCS-V-65 H7 F -P I GB IIAN LC NA N ~ ~ ~ ~ L~ ~ ~

t1520 H CS-V-68 tl520 F -P 1 GB tIAII LC NA N ... Le ~ . - 4 HY-V"17A E13 F ~ 75 CT SOL NO FC C GHJK ~ ~ . ~ 1G 4020 tl5 3 0 HY-V"17B 2 E5 F .75 GT SOL NO FC C GHJK. . ~ 1G 4020 HY-V-18A tl530 E13 II530 F .75 'T S0 I. NO FC C GH JK ~ ~ ~ ~ IG 4020 HY-V-189 E5 F .75 GT SOL NO FC C CHJK. ~ . ~ IG 4020 tl530 IIY-V-I'tA E13 leee IA F .75 CT SOL NO FC C CHJK. ~ .. 1C 4020

WWP-2 PUMP AND VALVE INSERVICE TEST PRDGRAH VALVE TEST TABLES RBYision 4t Page 4.4-ih acaaaaacrcacaslcaaalsa caaacaca c a a c Q ls c ss Sl Sl Q Q D ~ l a ss c ss ss c Q aaassslaaaacaaa QcQac sscaaassalsa aaassssassaaa ~ lacaaaaaaa VALVE CODE LOCATION VALVE SI1E IW VALVE ACTUA'TOA --POSITION--- EXEA. TEST CODE NOTES AELIEf tIUtIBER CLASS Otl PhID CATECOAY IWCHLS TYPE TYPE NOAtIAL FAILED FAEQ. AEGUESTS c sl c c a c Q c c Q Q Q c Q Q c Q Q Q c DCQCQ Q ace Q ca C DcllQQ cacccaac C C Sl ll Qaaaaaaa cllsscrslacaacaa llQ Q Q ll QCCQ llllllD Sl ss c c a ss c a ls r ss QCQCQQCsla HY-V-198 2 E5 .75 GT SOL NO fC C CEIJK e ~ 1G 4r20 tl530 HY-V-20A E13 .75 GB SOL NO FC C GHJK ~ ... IC 4e20 II530 HY-V-208 2 E5 ~ 75 CB SOL WO FC C GHJK.... IC 4r20 II530 HY-V-33A 2 E13 .75 GT SOL NO FC C CHJK.... IC 4 '0 HY-V-338 2 E5 F .75 GT SOL NO FC C CHJK.... IG 4e20 M530 HY-V-34A 2 E13 F ~ 75 GT SOL tIO FC C CHJK.... IG 4e20 IIS30 HY-V-348 2 E5 F .75 CT SOL NO FC C GHJK. .. 1C 4e20 tl530 HY-V-35A 2 E13 F .75 , SOL NO FC C GHJK.... IG 4e20 II530 ~

HY-V-358 2 E5 F .75 GT SOL NO FC C CHJK. ~ ~ ~ IG 4e20 II530 HY-V-36A 2 E13 F .75 SOL NO FC C GHJK. ~ ~ . 1G 4e20 tl530 HY-V-368 ~ 75 CB SOL NO FC C . GHJK ~ ~ ~ ~ 1C 4r20 LPCS-FCV-11 2e 813 GB HO NC FAI 6 GHJ ~ L ~ ~ ~ 4 l 20 II520 LPCS-RV-18 F12 FC 1. 5X2 RV SA NC 'tIA N ~ ~ ~ ~ PE 9 II520 LPCS-RV-31 2 C12 FC IXI RV SA NC NA N ~ ~ ~ ~ ~ Po ~ 9 II520 LPCS-V-I 2 Dl I GT HO NO FAI 0 CHJ.L.. ~ 4r20 tl520 LPCS-V-3 813 CK WC NA 0 ~ I 'I ~ ~ ~ ~

tl 520 LPCS-V-5 Gl 1 12 CT II0 NC FA I C CH J ~ L ~ ~ IL 4r20 II520 I.PCS-V-A H9 TC 12 CK AOeSA NC WA I GH..L... 6 4e 9

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blkIP-L PUNP AND VALVE IHSERVICE TEST PROGRAII VALVE TEST TABLES Revision 41 Page 4.4-17 aaacacaacs cjcssjjsssaas DCCSD a c sca accccc C S D jjajr acjsjsjjjsj jsc ~ ja c c a D D D c a cc ss 'cc csasacc aaaaaaaass a a sj Q a D a jjc a cs s cs a a ss cs ss a s VALVE CODE LOCATION VALVE SIZE IN VALVE ACTUATOR --POSITION--- EXER. TEST CODE NOTES RELIEF tiUHBER CLASS ON PhlD CATEGORY INCHES TYPE TYPE NORtIAL FAILED FREQ. REQUESTS D Q c Q c ss a D D D a D a a c ss s ss c c cracQ ~ jcsjaassca caa-r c C asses aaaacsscsc csscsassjrarca ccascc cc caaaaarcac cccaQC c c LPCS-V-12 2 F14 12 GB HO NC FAI GHJ.Lo 4r20 H520 LPCS-V-33 C12 1.5 CK NO tlA Q .H ~ . ~ ~ . ~

H520 LPCS-V-34 C12 . 1.5 SC SArHAtl NO NA Q ~ H~ ~ ~ ~ ~ ~

tl520 LPCS-V-bb H10 F "P HAN LC tlA ~ ~ ~ L~ ~ ~

H520 LPCS-V-67 H10 F -P 1 GB HAN LC NA ~ ~ ~ ~ L~ ~ ~

H520 HS-RV- I A F10 6 X 10 S/R 'AOrSA NC IJA N ~ ~ .. P ~ 7 M529 HS-RV-18 Ell C 6 X 10. 8/R AO r SA tlC tlA N ~ ~ P ~

H529 HS-RV-I C Fb 6 X 10 S/R AOrSA NC NA tl o.. PE 7 t1529 HS-RV-1D E7 6 X 10 S/R AOrSA NC NA N ~ ~ PE ~ 7 tl529 HS"RV"2A F10 C 6 X 10 8/R AOrSA NC NA N .....P.. 7 H529 HS-RV-28 E10 6 X 10 S/R ADA SA tlC NA tl . .. P. ~ 7 H529 HS-RV-2C f7 6 X 10 S/R AOrSA NC NA N ~ ~ ~ P 7 H529 HS-RV-2D E7 6 X 10 S/R AOrSA NC tlA N ~ ~ ~ ~ ~ P ~ 7 ti529 HS-RV-3A F9 6 X 10 S/R ADA SA NC NA N P 7 tl529 HS-RV-38 E9 6 X 10 8/R AO ~ SA NC NA N P 7 H529 HS-RV-3C F7 6 X 10 8/R AOrSA NC tJA N .. ..P.

~ 7 tl5 29 HS"RV-3D EB 6 X 10 8/R AO,SA NC NA R .H...P..

HS-RV-4A 6 X 10 S/R AO,SA NC NA R AH.. ~ P..

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WNP-2 PUHP AND VALVE INSERVICE TEST PROGRAM VALVE TEST TABLES R2Yision 41 Page 4.4-18 aaaoaccsaoacsaaoacassao aaaaaaaa DDDDDDDD aaca Dao DDicoc aoaaaaaa aaaaaassssassaaa Doaaaacsaa aaaaaaaaaa a a a sc c ss a a ss a VALVE CODE LOCATION VALVE SIZE IN VALVE ACTUATOR --PCS I T10N"-- EXERT TEST CODE NOTES RELIEF NUtlBER CLASS ON Phln CATEGORY INCHES TYPE TYPE NORtlAL FA lLED FREQ. REQUESTS cocoa ssassassoacasscsocss D D D CS D D D D aaossocaa cIcc DDDD DaosIL aaoaacace aaacaaaccsaoace oaossa \ LDDaoaaa aasscaacoass DDaaass DDD tIS-RV-48 I E9 BC 6 X 10 S/R AOISA NC NA R .H...P.. 13 tI529 HS-RV-4C I F8 BC 6 X 10 S/R AOeSA NC NA R ~ H~ ~ ~ P.. 13 II529 IIS"RV"40 E8 BC 6 X 10 S/R AOe SA NC NA R .H...P.. 13 N529 HS-RV"58 I E9 BC 6 X 10 S/R AO ~ SA tIC tIA AH.. ~ PE ~ 13 II529 tIS-RV-5C F8 BC 6 X 10 S/R AOeSA NC WA R .H. ~ P..

~

H529 HS-V-lb I 813 F 3 GT IIO NC FA1 0 GHJ.L... 4e20 II529 tlS-V-19 814 F' GT IIO NC FA1 0 GHJ L... 4I20 N529 IIS-V-22A F12 tI529 GB AO NO FC 8 CHJKL ~ ~ ~ 4 '0 IIS-V-228 E12 N529 F 26 GB AO tlO FC 0 GHJKL ~ ~ ~ 4 '0 HS-V-22C F5 26 GB AO NO FC 0 GHJKL.. ~ 4e20 II529 HS-V-22D I E5 F 26 CB AO NO FC 0 CHJKL... 4e20 II529 tlS-V-28A I F13 F 26 GB AO NO FC 0 CHJKL. ~ . 4e20 II529 IIS-V-28B E13 F 26 GB AO NO FC GHJKL... 4e20 II529 IIS-V-28C I F4 F 26 GB AO NO FC 0 GHJKL ~ ~ ~ 4e20 II529 tlS"V"28D E4 F 26 CB AO NO FC 0 GHJKL 4e20 tI529 tlS-V-37 I TYP 18) C6-CII II529 C 10 CK SA NC NA I .H.... 18 tlS"V-38 ITYP 18) 2 t

C6-C II C 10 CK SA NC NA I ~ H~ ~ ~ ~ ~ ~ 18 tl529 tIS-V-67A F13 F I 5 CT tIO NC FAl 0 GHJ LE 4e20 tiN>P

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MHP-2 PUHP AND VAlVE IHBERVICE TEBT PROGRAH VALVE TEST TABLEB Revision 41 Page 4.4-19 ss a ss a a a a a a a ss a ss c a a a ssaaa- assaaaara arras arr ssaassaacss sscslac ssaaaa assr c a a a ss a a ss ss a a a a ccaaa aacaaaaaa aaaaassassaa caaaaassssaa VALVE CODE LOCATION VALVE SIZE IW VALVE ACTUATOR --POS I T I OW--- EXER. TEST CODE NOTES RELIEF tlUtlDER CLASS Otl PtslD CATECORY IWCHES TYPE TYPE WORtlAL FAILED FREO. REQUESTS carra ssaracaaa crass ssaaaa ass ra rca asss:raaaa aarrss acaaa ssa aaaaacacaccaa a ss a a a car acr aa a c r a ss ss a a ss a aaaassrrssaa NS-V"h79 F13 1.5 GT NO tIC FA I 0 GHJ.L... Rs20 tl529 tlS-V-h7C I F4 f 1.5 GT tlO WC FAI 0 GHJ.L... 4s20 N529 NS-V"h7D DR N529 F 1.5 GT NO WC FAI 9 CRT L 4 '0 NS-V-14h 2 87 tl502 I 9 24 GT NO WO FAI C GHJ .... IS 20 NSLC-V-IA 2 87 9 1.5 GT NO WC FAI 6 GH J. .

~ ~ 20 N557 tlSLC-V-19 2 85 9 1.5 GT NO WC FAI Q GHJ..... 20 N557 NSLC-V-IC D7 9 I 5

~ GT NO WC FAI 9 GHJ . ~ s 20 tl557 NSLC-V-ID 9 1.5 CT tlO WC FAI 9 GHJ.... ~ 20 LE NSLC-V-2A I CS 8 I~5 GT NO WC FAI C GHJ . ~ ~ IR 20 N557 NSLC-V-28 I CS N557 9 1.5 GT NO WC FAI C OH'.. ~ IR 20 NSLC-V-2C ES 9 1.5 GT NO WC FAI C GHJ ~... ~ IR 20 t!557 NSLC-V-2D ES 9 1.5 GT NO WC FAI C GHJ. ~ ~ . ~ IR 20 tl557 NSLC-V-3A I C9 F 1.5 GT NO WC FAI C CIIJ-L ~- ~ IR 4 s20 N557 NSLC-V"38 CS F 1.5 GT NO WC FAI C CIIJ.L ~ ~ ~ IR 4s20 tl557 tlSLC-V-3C I ES F 1.5 GT NO WC FAI C GHJ ~ .. IR 4s20 tl557 NSLC-V-3D I ES F ~ I s5 CT NO WC FAI C CHJsL ~ ~ ~ IR 4s20 N557 tlSLC-V-4 2 JR 9 I~5 GT tlO WC FAI C CHJ ~ .~. ~ IR 20 N5 57 tlSI C-V"5 2 .15 9 1-5 I T NO WC FAI C GHJ..... IR 20

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MHP-2 PUHP AHD VALVE IHBERVICE TEST PRDGRAII VALVE TEST TABLES Revision 41 Page.4.4-20 r

Q a Q r c Q Q Q ss ss a c a Q Q Q a Q c ssrraa c D r D ss Q r D arssaaaaa a Q a a a D a ss D D a a D a a a a ss ss a ss a a

- EXER.a DQDaDQQQ QQQQCQCQ QDQCC ss DD D aaassassssssa ssaassssssaaass VALVE CODE LOCAT ION VALVE Sl IE IN VALVE ACTUATOR --POSITION TEST CODE NOTES RELIEF NUtlDER CLASS ON PAID CATEGORY INCHES TYPE TYPE NORtlAL FAILED FRESs REQUESTS QSSQS:ararraSsaaarrrrrs: cac r raarrraa CLLCQQ rrr rara c CLc QQDcassssss rrccrssssaacaass ~ sDQQQ rccasscQDD ssrassssaassass aassaaassaa tlSLC-V-9 H5 1.5 GT HO NC FAI C GHJ. - - IR 20 H557 tlSLC-V-10 . H5 1.5 GT NC FAI C GHJ. ~... 1R 20 tl557 PI-EFC-X18A FC 1 X .5 CK SA NO NA R GH ~.... =

4 ~ 15 Pl-EFC-X188 G9 FC 1 X ~ 5 CK NO NA R GH... ~ ~ ~

tl557 P I-EFC-X18C G9 FC 1 X .5 CK NO NA R GH ~ ~ ~ ~ ~ ~ 4 ~ 15 tl557 PI-EFC-X18D F9 FC 1 X .5 CK SA R GH ~ ~ ~ ~ ~ 4 ~ 1S tl557 Pl-EFC-X29b H7 FC 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~

tl543 1 H7 FC 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4 '5 I'13 PI-EFC-X291'I-EFC-X30a tl543 1 G13 1 X .5 CK SA tl0 NA = R GH. ~ ~ ~ ~ 4s15 tl54 3 1 P I -EF C-X 30 FC 1 X .S CK SA NO NA R GH.. ~ . ~ ~

N543 1 P I-EFC-X371 D6 FC 1 X .5 CK SA NO NA R GH. ~ s... 4s15 tl521 1 Pl-EFC-X378 D6 HS21 1 FC 1 X .5 CK SA tl0 NA R GH. ~ .... 4s15 P I-EFC-X38a 1 C13 FC 1 X 5 CK SA NO tlA R GHs. ~ . ~ 4r1S tl5 2 9 PI-EFC-X38b 1 D13 FC 1 X, ~ 5 CK SA tl0 NA R GH ~ ~ ~ 4s15 N529 P I-EFC-X38c 06 FC 1 X .5 CK SA NO NA R GH .. ~ 4,15 tl519 Pl-EFC-X38d G6 FC 1 X 5 CK SA . NO NA R GH 4s15 tl519 PI-EFC-X38e G6 FC 1 X .5 CK SA NO NA GH ~ ~ ~ ~ ~ ~ 4s15 tl519 PI-EFC-X38f

~ ~~ ~ n 1 X .5 CK SA tlO NA R GH...... 4s15

WHP-2 PUMP AHD VALVE IHSERVICE TEST PROGRAN VALVE TEST TABLES Revision 4t Page 4.4-21 arssaaaaaassaaaaaaaassa rrara aaaaassra aa D Daa arrra a a ss a ass aaa aaaass DQDDD DlsaaQssa DssraD assass VALVE CODE LOCAT I Otf VALVE SIZE IN VALVE ACTUATOR --POSITION--- EXER. TEST CODE NOTES RELIEF tfUtlDER CLASS ON Pf ID CATEGORY INCHES TYPE TYPE NORMAL FAILED FREO. REQUESTS Qasaassssssasasasass ~ e Q s s el aaasassa a ls Q ls sl a ss ll Qsalossaesa DS a Is Q ~e a ee a a ss es D QSQQSQSDQDSDS sssaasl Qs s Q a a a 'D a Da a Q Q D S D D sl DQQQassaseo PI"EFC-X39a C13 FC 1 X .5 CK SA NO NA R G I'I ~ ~ ~ ~ ~ ~ 4o15 M529 PI-EFC-X39b 1 D13 M529 FC 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4 '5 PI-EFC-X39d FC 1 X .5 CK SA NO NA R Glf... ~ ~ ~ 4 ~ 15 MS21 2 P I-EFC "X39e I H13 FC X .S CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4 ~ 15 tl521 2 PI-EFC-X40c 1 F I? FC 1 X .5 CK SA NO tIA CH. ~ ~ e 4rl5 M530 PI-EFC" X40d F12 FC X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4r 15 t'l530 Pl-EFC-X40e C14- FC 1 X .5 CK SA tfO tIA R CH ~ ~ ~ ~ ~ ~ 4 ~ 15 M530 Pl-EFC-X40f'14 11530 FC 1 X .5 CK SA NO NA R CH... ~ ~ . 4o15 Pl-EFC-X41c .5 .... '5 I'4 B4 FC 1 X CK SA NO NA R GH ~ ~ 4 MS30 PI-EFC-X4 I CI C4 FC X .5 CK SA NO NA R GH. ~ . .. 4e 15 M530 PI-EFC-X4fe FC 1 X .5 CK SA NO IIA R 4r 15 M530 P I-EFC-X 4 1 C4 FC 1 X .5 CK SA NO NA R CH. 4r 15 tIS30 P I-EFC-X42a C4 FC 1 X .5 CK SA NO NA R CII ~ ~ ~ ~ ~ 4r15 Pl-EFC-X42b tl529 C4 MS29 FC 1 X ~ 5 CK SA 'O NA GH ~ ~ ~ ~ ~ ~ 4rl5 PI-EFC" X42c Eh FC 1 X .5 CK SA NO NA R CH. ~ . ~ .. 4e15 M543 2 Pl-EFC-X42f'S MS29 FC X .5 CK SA NO NA CH ~ ~ ~ ~ ~ 4e 15 PI-EFC-X44Aa E FC 1 X .5 CK SA NO t(A R Gll . ~ ~ 4e15 tl530 Pl-EFC-X44Ab E2 FC I X .5 CK SA NO tIA R GH..... ~ 4r15 wn I

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WNP-2 PUHP AND VALVE INSERVICE TEST PROGRAN VALVE TEST TABLES Revision 5 Page 4.4-2?

caccaaasaaacsacaaaccs aacaa ccacsaca acc scca sacaaacca aasaa aaccacsa s c c a ss c as a a a a a ss ~ aaaassa ~a a a a a ss a a a ~s a a a as a ss a c a a sa a a sa a a a sa a VALVE CODE LOCAT ION VALVE SIZE IN VALVE ACTUATOR --POSITION--- EXER. TEST CODE NOTES RELIEF tlUtlBER CLASS ON PhID CATEGORY INCHES TYPE TYPE NORMAL FAILED FRED. REQUESTS Q Q Q U Q U Q 0 c c Q c aa cQQUQQc ca'eas ~ Qc u aa Q Q as ~ accaacscaa Qas aaQQQQ Q aa Q c Q QQQUQQQQ QQQQQQQQQQQQQ ~ o aa a aa aa QQQQQQQQQ QQQQ Qahaaa QQQQQQQQQQ PI-EFC-X44Ac E2 FC 1 X .5 CK SA NO NA R Gll ~ ~ ~ ~ ~ ~ 4o15 tl53 0 Pl-EFC-X44Ad f2 FC 1 X .5 CK SA NO NA R CH. ~

tl530 PI-EFC-X44Ae J6 . FC 1 X .5 CK SA NO NA R CH ~ ~ ~ ~ ~ ~ 4o15 M530 PI-EFC-X44AP E2 FC 1 X ~ 5 CK SA NO . NA R GH ~ ~ ~ ~ ~ ~ 4o15 M530 PI-EFC-X44AQ E2 FC 1 X .5 CK SA NA R GH... ~ ~ ~

M530 PI-EFC-X44AM E2 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~

M530 PI-EFC-X44AJ E2 FC 1 X ~ 5 CK NO NA R o

CH.. ~ . ~

tl530 PI-EFC-X44Ak J6 FC 1 X ~ 5 CK NO NA R GH, ~ .. ~ 4o15 tl5 3 0 PI-EFC-X44Al Hb FC 1 X .5 CK SA NO NA R CH ~ ~ .~. ~

tl530 PI-EFC-X44AA Hb tl530 X .5 CK NO NA R GH ~ ~ ~ ~ ~ 4 '5 PI-EFC-X449a F2 FC X ~ 5 CK SA NO NA R CH......

M530 Pl"EFC-X449b F2 FC 1 X .5 CK SA NO NA R CH ~ ~ ....

tl530 PI-EFC-X449c F2 FC 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~

M530 PI-EFC-X449d 1 F2 FC 1 X 5 CK SA NO GH ~ ~ ~ ~ ~ 4 ~ I tl530 Pl"EFC-X449e Jl I FC 1 X .5 CK SA ttO NA R OH' ~

tl530 PI-EFC-X44DF F2 FC 1 X .5 CK SA NO NA R CH ~ ~ ~ ~ ~ ~ 4a15 M530 Pl-EFC-X4490 1 F8 FC 1 X 5 CK SA NO thA R Gll. 4o15 M530 Pl-EFC-X449h F2 FC 1 X .5 CK SA GH ~ . ~ ... 4o 15

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NHP-2 PUIIP AIID VALVE IHBERVICE TEST PROGRAM VALVE TEST TABLES Revision 4t Page 4,4-23 arcrarrrracrcacaaarrr c r caraasrr ccl carel c coca c aacaas caaaracasa asacasacsacaasc a race sssaaaasa ~ l Is C r Q Q cl la sl Q a a ca c s Q aa a cc VALVE CODE LOCAT I Otl VALVE SIIE Itt VALVE ACTUATOR --POSI T ION--- EXER. TfST CODE NOTES RELIEF tlUtlDER CLASS ON Pkc,ID CATEGORY INCHES TYPE , TYPE NORtlAL FAILED FREO. REQUESTS s Q r c aa r c r c c la a a s s a a s ca aa a r ls r s rscsacara cccclacQC ararccco Qoras asarcac'r Q a la Q Q r s Q Q C al a Q QQCQQ Qcaaacaaa sasaaraarra cslrasasaaaa Pl-EFC-X44DJ F2 FC 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4ll5 tk530 Pl-EFC-X440k Jl H530 1 FC 1 X .5 CK SA'O tIA R GH... ~ ~

PI-EFC-X4481 Hl 1 . FC 1 X .5 CK SA NO NA R GH..-

tk530 P I "EFC-X440n Hl I FC 1 X .5 CK SA NO NA R GH...... 4l 15 PI-EFC-Xhl a F12 FC I X .5 CK NO tIA R CH ~ ~ 4 ~ 15 tk530 PI-EFC" X61b F12 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~

tl530 P I-EFC-Xhl c G5 FC 1 X ~ 5 CK SA tIO tIA R - GH ~ ~ ~ ~ ~ ~ 4 ~ 15 tl529 Pl-EFC-X62b H12 FC 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4 ~ 15 tl529 Pl"EFC-X62c Fh FC I X ~ 5 CK NO NA R Okla ~ ~ ~ ~ ~ 4 ~ 15 tl530 Pl-EFC-X62d Fh FC I X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~

tk530 PI-EFC-X66 C6 FC 1 X .5 CK SA NO tlA R GH ~ ~ ~ ~ ~ 4l15 tl543 Pl-EFC-X67 914 1 X ~ 5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~

tl543 PI-EFC-X69a D4 FC 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4r 15 tl529 PI-EFC-X69b D4 FC 1 X 5 CK SA NO NA R Gkl..

tl529 PI-EFC-X69a G6 FC 1 X .5 CK SA tlO NA R GH ~ ~ ~ ~ ~ ~ 4 ~ 15 tk530 Pl-EFC-X69F H12 H529 FC 1 X .5 CK SA NO 'A R GH... 4al5 Pl-EFC-X70a E4 FC 1 X .5 CK NO NA R Gkl ~ ~ ~ ~ ~ ~

tl529 PI-EFC-X70b FC 1 X ~ 5 CK SA tlO NA R GH..a ~ ~

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WItP-2 PUMP AND VALVE INSERVICE TEST PROGRAM VALVE TEST TABLES Revision 41 Page 4.4-24 Q Q C Q Q CCQDQQ QQ CCQ DSDS cDaccassa QcaDQQQ QQDDQ ~ s c Q c c D D se a a se a ss a a Q a a s a ss ~e a D es a ~ ecaaasaaa Qsasacaseaa a D a ss ss ss se ss a ss VALVE CODE LOCATION VALVE Sl Zf IN VALVE ACTUATOR --POSITION--- EXER ~ TEST CODf NOTES RfLIEF tlUNDER CLASS ON PlrID CATECORY IttCHES TYPE TYPE NORHAL FAILED FREON REQUESTS CQCCSQCQCSCQ Q QC Q sccss Caaaseaaa caasacca c DD sa cassr a QDssess Des CDQQQDDQQQQQQ CQ S Qcaaaaaaa s secseesseaes ss CCQaseDDDQD PI-EFC-X70( f13'529 1 X .5 CK NO ttA GH ~ ~ ~ ~ ~ 4e15 Pl"EFC-X70d 1 E13 FC 1 X .5 CK SA tl0 NA R Gll... ~ ~ . 4r15 tl529 PI-EFC"X70e 1 914 FC 1 X .5 CK SA tt0 NA R GH... ~ ~ . 4e15 N530 PI-EFC-X701' 014 FC 1 X .5 CK SA NO thA R GH... ~ . ~ 4 e 15 N530 P I-EFC-X71 a 1 E4 FC 1 X .5 CK SA NO NA R GH ~ . ~ ~ ~ ~ 4 ~ 15 tl529 P I-EFC-X71b 1 f4 FC 1 X .5 CK SA NO ttA R OH' ~ ~ ~ 4e15 tl 529 P I-EFC-X71( 1 G6 FC 1 X .5 CK SA NO ttA R GH...... 4e 15 tl5 1 9 PI-EFC-X71d 1 G6 FC 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4el5 tl519 Pl-EFC-X71e G6 FC 1 X .5 CK SA NO NA R GH...... 4r 15 tl519 PI-EFC-X711'6 tt519 FC 1 X .5 CK SA NO NA R GH... ~ . ~ 4e 15 PI-EFC-X724 J6 FC X .5 CK SA NO NA R Gll ~ 4 ~ 15 11529 p I-EFc" x72r F12 CK SA NO NA I .H..L ~ ~ 4 ~ 11 tl543 1 PI-EFC-X73a 1 JS FC 1 X .5 CK SA R GH ~ ~ ~ ~ ~ ~ 4 ~ 15 tt520 PI-EFC-X73e F7 CK SA tl0 ttA I ~ H~ ~ L~ ~ ~ 4 e 11 tl543 1 PI-EFC-X74a 012 FC 1 X .5 CK SA tt0 NA 4e15 tl5 3 0 Pl-EFC-X74b 1 115 FC 1 X .5 CK SA tt0 NA GH ~ ~ ~ ~ ~ ~ 4 ~ 1 5 M521 1 PI-EFC-X74e tt 1 I 1 X 5 CK SA NO NA R GH. ~ ~ ~ 4e15 tt530 Pl-EFC-X74r El 1 I 1 X .5 CK 'A NO tlA 4rl5

4 N

II

HHP-2 PUHP AND VALVE INSERVICE TEST PROGRAH VALVE TEST TABLES Revision 4k Page 4.4-25 ccsrliaas s D QDca siisa ascacaar Zi C Qii c aa raass arsrsaaa aarrsararicsaa aarrsccss rraaaaaaaa arias VALVE CDDE LOCATION VALVE SIZE IH VALVE ACTUATOR --POSITION--- EXER. TEST CODE NOTES RELIEF tlUtlDER CLASS OH PAID CATEGORY I tlCHES TYPE - TYPE NORt!AL-FAILED FREG.. REQUESTS s Q c a D Q D s a Q D s c Q c a s iiii aii ar c sarars s i) i) QSQ arear saacrasc aasrcsaasaras seas)i rasa a cs asacaaasaa aaraasasac PI-EFC-X75a G6 1 X .5. CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4)15 tl5 3 0 PI-EFC-X75b G12 FC 1 X .5 CK SA tlO HA R GH 4) 15 PI-EFC-X75c 1 tl530 E12.

tk5 29 FC 1 X .5 CK SA NO HA r

R GH ~ . ~ ~ ~ ~ 4 ~ 15 PI-EFC-X75d E12 FC 1 X .5 Ch SA NO NA R GH... ~ 4)15 tl529 P I "EFC-X75e FS FC 1 X .S CK SA NO tlA R GH.. ... - F 15 tl530 PI-EFC-X75P F5 FC 1 X .5 CK SA ND NA R GH.. ~ ~ ~ ~ ~ r 4) 15 tk530 PI-EFC-X78a E14 FC 1 X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ 4 ~ 15 N543 2 P,I-EFC-X78b r

J10 tk520 FC 1 X .5 CK SA NO NA R Gkl. ~ r ) 4 '5 PI-EFC-X78a F12 FC I X .5 CK SA NO NA R GH 4 ~ 15 tk523 PI-EFC-X78r 1 H12 FC 1 X ~ 5 CK SA NO NA R Gll ~ ~ ~ ~ ~ 4r15 tl530 PI-EFC-X79a F15 tk523 FC X .5 CK SA NO HA R GH ~ ~ ~ ~ ~ . 4 '5 PI-EFC-X79b 1 F15 FC 1 X .5 CK SA NO HA R GH ~ ~ ~ ~ ~ ~ 4 ~ 15 tl523 GOD PI-EFC-X82b 814 FC 1 X .5 CK NO tlA R GH. ~ ~ ~ ~ ~ 4 ~ 15 tk5 4 3 1 Pl-EFC-X84 a 2 Db FC 1 X .5 CK SA NO R 0 ~ ~ ~ ~ ~ ~ ~ ~ 4r 15 N543 1 PI-EFC-X86A 814 FC 1 X .5 CK SA tlA R GH. ~ . ~ . ~ F 15 tl543 1 PI-EFC-X868 814 tl543 1 FC 1 X .5 Ch SA NO HA R GH ~ ~ ~ ~ ) ~ 4 '5 PI-EFC-X87A Dbr FC X .5 CK SA t<0 NA R GH ~ ~ ~ ~ ~ ~ 'le 15 tk543 1 PI-EFC-X878 2 Db FC 1 X .5 CK SA NO NA R . ~ ~ . ~ 4r 1S

~ I i ~

l' WNP-2 PUHP ANIL VALVE INSERVICE TEST PROGRAH VALVE TEST TABLES Revision 4t Page 4.4-26 a c a a a a a ls Q a a is a a ls a c c a a a QQD aacaaaaa caca aa aaaa- aa Q a a a c ss a a c a ~ s ss sl a a a sl ls ss a VALVE CODE LOCATION VALVE SIZE IN VALVE ACTUATOR --POSITION--- EXER. TEST CODE NOTES RELIEF tlUtlBER CLASS ON PhlD CATEGORY ItlCHES TYPE " TYPE NORHAL FAILED FREQ. REQUESTS slaaaaa aaslacaaacaaaa Daa ls s:aaaaaaa slaaac sl ac a ca aacaQ acQCQQQQ aaaaaaassalsaaa D a sl a D acaaaaaaa a ss a sl c a a a a a a aaaa Qaa PI-EFC-X106 H12 FC X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~ 4r 15 tt529 PI-EFC-XI07 H12 FC I X .5 CK SA NO NA R GH ~ ~ ~ ~ ~ ~

H529 PI-EFC-X 108 C12 . FC X .5 CK NO NA R tt529 P I "EFC" X109 HS FC 1 X .5 CK SA tl0 NA R GH. ~ ~ ~

tl529 PI-EFC-Xl 10 H5 FC 1 X .5 CK SA NO NA R GH. ~

tl529 P I "EFC-X111 H5 FC 1 X .5 CK SA NO NA R GH.... ~ .

tt529 PI-EFC-X112 HS FC 1 X .5 CK SA NO NA R GH...

H529 PI EFC-X113 H5 FC I X .5 CK SA NO NA R GH . ~ ~ ..

tl529 PI "EFC-X114 H12 1 X ~ 5 CK NO NA R CH ~ ~ ~ ~ ~ ~ 4r 1S tl529 LE P I "EFC-X 115 H12 FC 1 X .5 CK SA NO NA R CH ~ ~ ~ ~ ~ ~ 4r15 H529 PI-EFC-X119 C6 FC 1 X .5 CK SA NO NA R Gll ~ ~ ~ ~ ~ ~

tl543 PI-V"X42d F5 F -P ttAtt LC tlA N ~ ~ ~ ~ L~ ~ ~

H521 pI-v-x540r F -P HAth LC NA N ~ ~ ~ ~ L~ ~ ~

tl521 pI-v-x61r G5 tl LC tlA N L~

PI-V-X62f'13 AN ~ ~ ~ ~ ~ ~

H521 012 HAN N ~ ~ ~ ~ L~ ~ ~ 4 tl52 1 P I-V-X69c F13 F -P HAtl LC N ~ ~ ~ ~ L~ ~ ~

tl521 PI-VX-216 F6 F "P CD HAN LC N .. ~ ~ . ~

tt521 P I-VX-218 H13 LC ....L...

ttSP 1

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'I IF

HHP-2 PUIIP AHD YALYE IHSERYICE TEST PROGRAN YALYE TEST TABLES Revision 4t Page 4,4-27 s caaasccasaaaascacaa sar>ac aaaaacssa a sa a c s c a a aaaacacac asses caacaassc caacaaacaaccc ca ac aaaaccaa ~ aacasaacca ss a c a a a ss aa c a VALVE CODE LOCATION VALVE Sl ZE 1N VALVE ACTUATOR --POSITiON--- EXER. TEST CODE NOTES RELiEF tlUHDER CLASS ON PtrlD CATEGORY 1NCHES TYPE TYPE NORIIAL FA1LED FRED. REQUESTS

~ > as s c s> a a a c c s> ss >s c a c a a c a ss >s a ss ss c c c sa c >> a c accasaasc c c aa>s a c c a sa a> c a c a c a a> csscaaccaaccac a a a s sl c c s a s a a> sa ss a c a a a cccccaccas P 1-VX-219 I lb F -P GD ttAN LC NA ~ ~ ~ ~ L~ ~ ~

tl521 1 PI-VX-22D Dll F-P 1 GD HAN LC NA tt ... L... 4 N521 2 Pl-VX-221 2 F12 ~ F -P I CD NAN LC tIA N ~ ~ . L~ ~ 4 N521 2 PI-VX-250 F13 F 1 SV SOL NO FC 0 GHJKL.. 1 ~ 4 11543 1 PI-VX-251 2. F13 F 1 SV SOL NO FC 0 GHJKL. ~ ~ 1 ~ 4 N543 1 Pl-VX"253 2 F13 F 1 SV SOL NO FC 0 GHJKL. ~ . 1 ~

tl543 -1 Pl-VX-256 2 F7 F 1 SV SOL NO FC Q CHJKL ~ . 1 ~ 4 tl543 P 1-VX-257 F7 F 1 SV SOL NO FC 0 CHJKL ~ >. 1> 4 N543 I P 1-VX-259 F7 F 1 SV SOL NO FC 0 GHJKL. ~ . 1> 4 tl543 1 P 1-VX-262 2 G13 F 1 SV SOL tIO FC 0 CHJK....

tl5 4 3 2 Pi-VX-263 C13 F 1 SV SOL NO FC 0 CHJK.... Ir 4 tt543 2 PI-VX~264 2 F13 F 1 SV SOL NO FC Q CHJK.... 1 ~ 4 tl543 2 P 1-VX-265 C14 F 1 SV SOL NO FC Q Gtt JK ~ ~ ~ ~ I~ 4 N543 2 P 1-VX-266 G7 F I SV SOL NO FC 0 CHJK.>..

tl543 2 Pl-VX-268 2 F7 F 1 SV SOL NO FC 0 GHJK.... lr 4 N543 2 Pl-VX-269 2 C5 tt543 2 F I SV SOL tIO FC 0 Gtt JK ... Ir 4 PSR-V-X73-1 2 J14 F 1 GT SOL NC FC 0 GIIJKL ~ ~ ~ I> 4>23 N896 PSR-V-X73-2 J12 1 GT SOL ttC FC 0 GHJKL... I> 4

t V

1

IINP-2 PUHP AND VALVE IHBERVICE TEBT PROGRAH VALVE TEBT TABLEB Revision 41 Page 4.4-28 sassssrasaasssaascsa asaass Draacaaca crcaaasscs ssarsaacsa sasasacaa aaa acaa D ra D r D s a s D r D as Q c as ss asaQQD Dca ssaasasacaas ssaasssasca VALVE CODE LOCAT 10tI VALVE S12E IN VALVE ACTUATOR --POS I T lON--- EXER. TEST CODE NOTES RELIEF tIUtIDER CLASS Otl P& ID CATEGaORY INCHES TYPE TYPE NORtIAL FAlLED FREQ. REQUESTS 4 C 4 4 c 4 4 ae 4 r c Q 4 c Q Q Q Q s 4 DQQseQ ~ aa s Q s s 4 sa CQ ca QQQQ sccsasas asseaa asaacaQQD D aa c D s c se s c a c s D S D Q Q aa c a as aa sa c a sa sa DQQQD444QQ QSQSQSSSSQ

'3 a

PSR-V-X77AI E14 GT SOL NC FC Q GHJKL ~ ~ ~ 1 ~ 4 M896 PSR-V-X77A2 E12 F 1 GT SOL tIC FC Q GHJKL...

M896 PSR-V-X77A3 1 F14. F 1 GT SOL NC FC Q GHJKL...

M896 PSR-V-X77A4 F12 F 1 GT SOL NC FC Q GHJKL...

M896 PSR-V-XSO-1 K14 GT SOL NC FC Q GHJKL. ~ . le 4e23 M896 PSR-V-XSO-2 K12 F GT SOL NC FC Q GHJKL ~ ~ ie 4 M896 PSR-V-X82-I B12 GT SOL NC FC Q GHJKL ~ ..

M896 PSR-V-X82-2 Bll F 1 GT SOL NC FC Q GHJKL ~ ~ ~ le 4 tIS96 PSR V-XS2-7 G12 F I GT SOL tIC FC Q GHJKL...

M896 PSR-V-X82-8 Gl 1 F 1 GT SOL NC FC Q GHJKL. ~ ~ le 4 M896 PSR-V-X83-I J13 F I GT SOL NC FC Q GHJhL ~ . le 4e23 MS96 PSR-V-X83-2 J12 F 1 GT SOL NC FC Q GHJKL. ~ ~

tI8 9 6 PSR"V-X84-1 F SOL NC FC Q GHJKL ~ ~ 1 ~ 4 '3 PSR-V-X84-2 illI GT SOL NC FC 0 GHJKL ~ ~ .

tl896 PSR-V-XSS-1 D13 1 GT .SOL NC FC Q GHJKL. ~ ~ I ~ 4e23 M896 PSR-V XSS-2 Dl I GT SOL NC FC 0 GHJhL... 1, 4 tl896 RCC-RV-34A H5 .75 X I RV SA NC NA N ~ ~ ~ ~ ~ P ~

tl525 RCC-RV-340 F5 ~ 75 X I AV NC NA N ~ ~ ~ ~ eP ~ ~

M.'I? 5

WHP-2 PUMP AND VALVE IHSERVICE TEST PROGRAM VALVE TEST TA8LES Revision 41 Page 4.4-29 saascasscaaccaasaaa- aaaaa acs:ssaassss acssscQ a aasscaaaa caQQC saaaasaa caaaa ssasssssaaaa ssaasss sass sass aaasa VALVE CODE LOC*T 10tl VALVE Sj jE ltI VALVE ACTUATOR --POSITlON--- EXER. TEST CODE tIOTES REL jEF NUtIDER CLASS OW PIID CATEGORY INCHES TYPE TYPE NORtIAL FA ILED FREON REOUESTS csassacaacscsacacss caaass c s ac sr = sr caasa QQ Cs SSQ C Qcaaaaas asac a aa ss ss scca QQ CQCQQQ ccaaa casa QQ a Q RCC-V-5 DIO 10 GT MO NO FA I OH'E ~ ID 4s20 M525 RCC-V-21 D10 F 10 ~

GT MO NO FAI C GHJL... ID 4r20 M525 RCC-V-40 2 D10 F 10 GT MO tIO FAl C GHJ.LE ~ lD 4r20 M525 RCC-V-104 2 E10 F 10 GT MO NO FAl C GHJL... ID 4r20 M525 RCC-V-129 3 ES M525 B 8 GT MO NO FAl 0 GHJ ~ .... 20 RCC-V-130 3 Eb, B 8 CT MO NO FAl 0 GHJ. 20 M525 RCC-V-131 3 Eb B 8 GT MO NO FAI 0 GHJ ~ ~ ~ ~ 20 tl525 RCC-V-133A H5 ~ C 6 CK SA NO NA 0 .H... ~

M525 RCC-V-1338 F5 C CK SA NO NA 0 .H...

tl525 RCIC-RD-1 Dl I D 10 RD SA . NC NA N .. ~... ~ W 2s 10 tl519 RCl C-RD-2 C12 D 10 RD SA NC NA W 2s10 tl519 RCIC-RV-17 C13 C lxl RV SA NC NA tl ~ .. .P..

~ 2 tl519 RCIC"RV-19 09 C 2X3 RV SA WC NA N ~ ~ ~ ~ P ~ ~ 2 tl519 Rcjc-V-l Ell 8 3 GT MO NO FAl 0 GHJ ~ .... 2 '0 M519 Rcjc-V"8 Fb F GT MO NO FAl 0 GHJ L. .~ 4 4r20 tl5 1 9 RC 1 C-V-10 2 814, tl519 D 8 GT tIO NO FAl 0 GHJ. ~ ... 2 20 RCI C-V" I I C 8 CK SA NC WA 0 .Ms' ~ 2 tl519 RC I C-V-13 H7 s

T 6 GT MO tIC FAI C GHJ ~ L.. IK 4s20 r

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IINP-2 PUHP AND VALVE INSERVlCE TEST PROGRAN VALVE TEST TABLES Revision 41 Page 4.4-30 rs:aacaaaacaaatrracrc car araacaaa ca Crace rs DCQCD(s QQCa IS Q aD acacaaDacraaa C IS ta D rc rca Q Q r ss ~ I a a IIs( a a a s( aaaaaaacaa VALVE CODE LOCATION VALVE SILE IN VALVE ACTUATOA IT IOtl---

PCS EXER TEST CODE NOTES RELIEF tlUtlDEA CLASS Otl PI(ID CATEGORY INCHES TYPE TYPE NOAtlAL FAILED 'REQ ~ AEQUESTS ctraccacacsstrcatrcrc CCC caccssraa Dr Ctr C C a QC C Caa ~ I Is c Is r s( Is c ~ stra (siss(carat ccrc aas(aaarca Qc ccQacac cssaaaaass(sa RCI C-V-19 E7 GD tIO NC FAI 0 GHJ.L . ~ ~ 4(20 N519 RCI C-V"21 2 ED C 2 CK SA NC NA Q .H..... ~ 2 tl519 RCI C-V-22 2 J8 . 8 6 GD HO NC FAI Q CHJ ~ ~ ~ ~ ~ 2 20 ACI C-V-28 2 D8 FC 1.5 CK SA NC NA 0 HE L .. " 4 HS19 RCIC-V-30 C7 C 8 CK SA NC NA ~ H~ ~ ~ ~ ~ 2 tl519 RCIC-V-31 2 C7 f 8 GT tlO NC FAI Q GHJ.L ~ .. 4(20 II519 RCIC-V-40 08 FC 10 CK SA NC NA Q .H. L H519 RCIC-V-45 2 F11 8 GD HO NC FAI Q CHJ ~ ~ ~ ~ 2' 20 t151 9 RCI C-V-46 2 F11 8 CD II0 NC FAI 0 GHJ ~ ~ ~ ~ ~ 2 20 tI519 RCI C"V-59 J9 8 6 GT HO NC FAI Q GHJ.( . ~ 2 20 II519 RCIC-V-63 I H3 F 10 CT tI0 NO FAI Q GHJ.L. 4(20 II519 RC I C-V-64 I Ch F -P ~ 10 GT HD LC NA N ~ ~ . ~L o tl519 RCIC V-65 Hb C 6 CK AO ~ SA "

NC NA I GH ~ ~ ~ ~ ~ ~ 2 '

tl519 RCIC-V-66 I J4 TC 6 CK AOISA NC tIA I GH. ~ L ~ ~ 6 9 tl5 1 9 RC I C-V-68 E7 N519 10 GT IIO tlO F*1 0 CHJ ~ L ~ ~ ~ 4 '0 RCIC-V-69 2 D7 F 1.5 CT tl0 NO FAI Q CHJ.LE ~ 4(20 H519 RC I C-V-76 H3 F I CO tlO NC FAI 0 GHJ(L ~ . 4 4(20 NS19 ACIC-V-86 2 A13 C 2 CK SA NC tlA 0 H ~ ~ ~ . 2

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WNP-L PUHP ANIj VALVE INBERVICE TEST PROGRAH VALVE TEST TABLEB Revision 41 Page 4.4-31 SSDDCDSCSCSDSCCSDC CCC S CC CSDSS CDSSCSSC S S ~I IIC SCSDISCSS SD C S C SS SSS CS S SC SC DS C VALVE CODE LacATION VALVE SIIE IN VALVE ACTUATOR --POSITIOtl--- EXER. TEST caoE NaTES RELIEF NUHDER CLASS ON Phla CATEGORY I NCllES TYPE TYPE NORHAL FAILED FREQ. REQUESTS DDRCDDDDDDDCSDDDRSDU DDDCU DDDDIIDCD CDCIIDDCR U D S U D S D rl UDUDD RDDDDDDD DDDDDUURRDIIDD CURDS UDDDDUDSD DSDIIDSDDDD DDDDDDDUDII RCIC-V-110 E7 GT Ha Na FAI Q GHJ ~ ~ ~ ~ ~ 4 20 H519 RCIC-V-111 2 CK SA NC tlA Q ~ H~ ~ ~ ~ ~ ~ 2 ~ 4A tl519 RC I C-V-1 12 2 f7 C CK BA NC NA Q AH ~ ~ ~ ~ ~ 2r4A tlS I 9 RCIC-V-1 13 2 E6 8 GT tto Na FAI Q GHJ.... ~ 20 tl519 RCI C-V-184 HS F -P 1 GS tlAtl LC NA N ...L tl519 RCI C-V-204 814 tl519 C 8 CK SA NC NA Q .H ~ .....

RCIC-V-740 2 H5 F -P 1 GD tlAN LC NA N ~ ~ ~ ~ L~ ~ ~ 4 tl519 RC I C-V-742 1 Jh F -P .75 GD HAN LC NA N ~ ~ ~ L~ ~ ~

tl519 Rjtt-V-IOA 1 G12 FC 24 CK SA Na NA C GH..L... 1F 4 tl529 RFll-V-108 1 G5 FC 24 CK SA t<a NA C GH ~ .are 1F 4 tl529 RFW"V-32A 1 G13 FC 24 CK AO ~ SA Na NA GH ~ ~ L~ ~ ~ 1Frh 4 tt529 RFN-V-328 GS FC 24 CK AO ~ SA Na tlA C GH ~ ~ L~ ~ ~ 1F ah H529 RFtl"V-bSA 1 G13 GT tl 0 FAI C GHJ L ~ 1F 4r20 tl52'9 RFH"V-658 1 G4 F 24 GT Ha tla FAI C GHJ.L. ~ . 1F 4I20 H52'9 RHR-FCV-64A 2 C12 H521 F 3 GD FAI Q GHJ ~ L ~ ~ ~ 4 '0 RHR"FCV"648 Ch F 3 l'ID tla Na FAI Q GHJ ~ L.. 4I20 11521 2 RHR-FCV-64C Eh H521 2 F GD Ha Na FA I 0 GHJ ~ L ~ ~ ~ 4 '0 RHR-RV-lA 2 H13 FC .75X1.5 RV SA NC NA N .....P.. 9

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llHP-2 PUNP AHIj VALVE IHSERVICE TEST PROGRAH VALVE TEST TABLES Revision 41 Page 4.4-32 asaaaaaaasaaaaasasssa saaaaa asassaaaa aaaaaaass- aasaslc saaacsasaD DaasaaaasccaccsD assaa Dsssaaaalc asaaaaasaaasca aaaaaaaaaasaa VALVE CODE LOCAT I ON VALVE SIZE IN VALVE ACTUATOA --POSITION--- EXER TEST CODE NOTES RELIEF NUMBER CLASS OW Pt ID CATEGOAY INCHES TYPE TYPE NOAtIAL FAILED FAEQ. AEQUESTS Aacaaaaasasaassla aaaa Daaas sasasaas saaaacssa as'Daalaal DICDCIS a aa CI aa s 0 a aa ~ I 0 0 D 0 s Ic a 0 D s 0 0 0 Ia 0 s la 0 D 0 a A IC 0 0 s Dsssallasas ADDSDDDasD RHR-AV 18 H5 FC .75X1.5 RV SA tIC NA N ~ ... ~ P..

M521 2 RHR-RV-5 CB FC IX2 RV SA NC NA N .....P.. 9 tl521 1 RHR-RV-25A 2 D10. FC 1X2 RV SA NC NA tk ~ ~ . ~ ~ P tl5 2 1 1 RHR-RV-259 C10 FC IX2 RV SA . NC NA N .....P.. 9 M521 2 RHR-RV-25C EB FC IX2 RV SA NC NA N . ..P.. 9 tl5 2 1 2 RHR-RV-30 C4 FC-P I X2 RV SA NC NA N ... L... 4 M521 2 RHR-RV-3b 2 F12 FC-P b X 8 AV SA NC NA N ~ ~ ~ ~ L~ ~ ~

tl521 1 RHR-RV-BBA 2 C7 FC .75 X 1 AV SA NC NA N M521 I RHR-RV"888 BB tl521 2

~ 75 X I RV SA NC NA N .... ~ P.. 9 RHR-RV-BBC 2 DB FC .75 X I RV SA NC NA N ~ ~ ~ ~ ~ P ~ ~

tl521 2 CAJOLE RHR-V-3A 2 HID 8 18 GT MO tIO FAI 0 GHJ ~ ~ ~ ~ ~ 20 M521 RHR-V-38 J9 8 18 GT MO NO FAI Q GHJ..... 20 M521 2 RHR-V"4A Bb F 24 GT MO NO fAI Q GHJ L 4I20 M521 1 RHR"V-49 912 F 24 GT MO NO FAI 0 GHJ.L ~ .. 4I20 tl521 2 RHR-V-4C 2 811 tl521 2 F 24 CT MO NO fAI Q GHJ ~ L ~ ~ ~ 4 '0 AHR-V-bA 2 98 8 18 CT MO NC FAI Q CH J ~ ~ ~ ~ ~ 20 M521 I AHA-V-b9 97 18 CT MO NC FAI 0 . .

~ 20 tl521 I AIIA-V-8 Eb II I ~ I 20 GT MO NC FAI C GHJ L .. IC 4I20

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MHP-2 PUHP AHD VALVE IHBERVICE TEST PROGRAM VALVE TEST TABLES Revision 41 Page 4.4-33 QDQccccrc QcarrrQClQC arras sauaraaa cesar aa aaaacaaa csaQc aaarracas a Q c D rr D D c a D a c a alaaDQ aascarraaa Dcsassrrsaa Da ar a a rs a r a rs VALVE CODE I.OCAT Intl VALVE S I ZE I tl VALVE ACTUATOR -"POSITION--- EXER. TEST CODE tlOTES RELIEF tlUtlDER CLASS Otl Vain CATEGORY I NCIlES TYPE TYPE NORIIAL FAILED FREQr REQUESTS s Qaacaacra scrrDrr DD caa D asaaaaaa DQDQDDDQ rasascsc Caaa- sacass Qsaaaaasacc a asses rS c a Ds s a a a D D a rr D c a D D a Drsaraaacrass RHR-V-9 D5 20 GT NC FAI C CHJ.L... IC 4r20 N521 I RHR-V-IIA El I tl521 I F "P 4 GT HO LC NA N ....L... 4 RIIR "V-I I B 2 Cl I F -P 4 GT NO LC NA N .. .L.

~

tl52 I RHR-V-16A F 16 GT NO NC FAI Q GHJ.L..r 4r20 tl52 I I RHR"V-16B DIO F 16 GT tlO NC FAI Q GHJ ~ L ~ ~ ~ 4r20 tl521 2 RHR-V-17A Hh F 16 HO NC FAI 0 GHJrL.r. 4r20 II521 RHR-V-17D Dll F 16 CT tlo NC FAI Q CHJ.LE ~ 4r20 tl521 2 RHR-V-21 E7 F ls GD IIO tlC FA I . 0 GH J L. . ~ 4r20 N521 2 RHR-V-23 K13 T 6 CB HO NC FAI C CHJ.LE ~ ~ IC 4r20 H521 2 RHR-V-24A EI 0 F 18 GD HO NC FAI 0 GHJ L ~ 4r20 t1521 I RHR-V-24B C10 IS CB HO NC FAi 0 CHJ L.. ~ 4r20 H521 2 RHR-V-27A D7 tl521 I F 6 GT HO NC . FAI Q CHJ LE ~ ~ 4 '0 RHR-V-278 DIO F 6 CT tin NC FAI Q CHJ ~ L ~ ~ ~ 4 ~ 20 tl521 2 RHR-V-31A D14 CK NC NA 0 .H. ~ . ~

tl521 I RHR"V-31B la CK SA NC NA Q .H H521 2 RIIR-V-3 I C D5 tl521 2 C IS CK SA NC NA 0 .H...r..

RHR"V-40

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C4 4 CD tI0 FAI CHJ..... 20 D NC 0 tl521 2 RHR-V-41A G5 TC 14 CK AOrSA tlC tlA I CH ~ .LE ~ ~ 4o 9 tt'tD I I I

MNP-2 PUMP AND VALVE INSERVICE TEST PROGRAM VALVE TEST TABLES Revision 4t Page 4.4-34 44S4CQCSQCCSSCQQSCCQ CCCDS ~a 4 4 4 D aa ai 4 ~ I 4 ra 5 4 4 aa 4 csaascscc scssD Q444a 4 4 aa aacscsscsscasaa SSQSS 4 s 4 4 4 4 Q af s QCCCQQCSQS CCQSCDSDCS VALVE CODE LOCATION VALVE S I LE IN VALVE ACTUATOR -"POSITION--- EXER. TEST CODE NOTES RELIEF tlUtlDER 4 ar 4 aa 4 4 4 Q 4 ra o ar 4 aa Q 4 4 4 CLASS aaosoa Otl CQC PIII 9 DQCQ CATEGORY cacccaac 1NCHES cc 4 5 Q TYPE ccccar TYPE Qoracccss NORtlAL F A saacaaaQsc IarQQ LED FRED.

CCCCC acsarsaaca ccs csaass REQUESTS QQcscD44raa

'Q 4;

r ~

RHR-V-4 I D I G13 TC 14 CK AOrSA NC NA I GH..LE 4r 9 t1521 2 r RHR-V-4 I C I E13 TC 14 CK AOrSA NC tlA I 'H..LE ~ 6 4r 9 tl521 2 RHR-V-42A G7 . T 14 GT IIO NC FAI C GHJ.L... IL 4r20 tl521 I fI r~

RHR-V-428 I G12 T 14 GT IIO NC FAI C GH Jr L ~ . ~ IL 4r20 r .

tl521 2 2,

RHR-V-42C I El I T 14 GT HO NC FAI C GHJ.L .. IL 4r20 H521 2 RHR"V-46A 2 C10 C CK SA NC NA 0 .H. ~ ... ~

H521 I r.'.

RHR-V-460 C6 C 6 CK SA NC NA 0 .H.....r 2 pr II521 2 RHR-V-46C 2 ES C 6 CK SA NC tlA 0 AH. ~ ~ r ~ ~ Ir tl521 RHR-V-47A J13 B 18 GT tlO NO FAI 0 GHJ ~ ~ 20 tl521 I RHR-V-47B 2 J3 B 18 GT NO NO FAI 0 CHJ ~ ~ ~ ~ 20 tl521 2 rI RHR-V 48A 2 Jl I D 18 GD NO NO FAI 0 GHJ ~ . ~ .. 20 rr tl521 RHR-V-488 2 JB D 18 GD Ilo NO FAI GllJ ~ ~ ~ ~ ~ 20 tl521 2 ~"

~ t RHR-V"49 G4 D 4 GT HO NC FAI 0 GIIJ ~ ~ . ~ ~ 20 tl521 2 RHR-V"50A F5 TC 12 CK AOrSA tlC NA I GH ~ L N521 RIIR-V-508 I F13 TC 12 CK AO ~ SA NC tlA I CH. ~ L ~ ~ 6 4r tl5 2 1 2 RHR-V-53A I Eb T 12 GT IIO NC FAI C GHJ L.. IC 4r20 tl52 I I RHR-V-538 I

""""r-El 1

""-T"-"-" 12 GT NO "NC -"-"

FAI

- - C GHJ.Lr ~ . IC 4r20 RI IR- V 6 0 A II I I D .75 SV 8 A I. NC FC Gl I JK....I

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'0 r, HNP-2 PUllP AND VALVE INSERVICE TEST PROGRAH VALVE TEST TABLES R&Yi.sion 41 Page 4.4-35 s cseaaaaaaarrcaasscaaca Scars QacsaDDQ acacssacc s a s ss s Q s c c s a ss a c a a c c a ss a ss a se a a SDSQQ DcQs es D s c s acaaasaaaa csssaseaccaa VALVE CODE LOCATION VALVE SIZE 1N VALVE ACTUATOR --POSIT1ON--- EXERT TEST CODE NOTES RELIEF NUtIBER CLASS Otl PhID CATEGORY 1NCHES TYPE TYPE NORIIAL FAILED FRED ~ REQUESTS QQUUUUQDescQQQSQDQQQD Qcrra s ee r r r c r c aseaaeerra rase rara CDQQD aaeeccscss D c Q r es a se D a a Q D es SQacD cassseaesaca aaacaassaaa aaacsrsQDS RHR-V-608 2 II8 .75 SV SOL NC FC 0 GHJK. ~ ~ ~ ee H521 2 RHR-V-68A 3 D13 D lh GT HO NO . FA1 0 GHJ ~....

20 t1524 I RHR-V-68B 3 014. B 16 GT IIO NO FAI 0 GHJ..... 20 tl5 2 4 2 RHR-V-73A H14 2 GB IIO NC FAI 0 GHJ ~ L ~ ~ ~ 4 ~ 20 e.

H521 I i"

R I IR-V-7 3 B H5 II521 2 F 2 GB HO tIC FAI 0 GHJ ~ L ~ ~ ~ 4 '0 ge e

RHR-V-75A 2 Gl I tl521 1 B ~ 75 SV SOI NC f C 0 GHJK. ~ ~ 1 r,

RHR-V-75B 2 G9 B .75 SV SOL tIC FC Q GHJK ~ ~ ~ ~ 1 II521 2

HR-V-8 2 D14 C 1.5 CK SA tIC NA 0 .H...... 17

= II521 1 I

RHR-V-848 2 B3 C I~5 CK SA NC NA 0 HE .. ~ 17 II521 2 ee RHR-V"84C C6 C 1.5 CK SA NC NA ~ H~ ~ ~ ~ ~ ~ 17 tl5 2 1 2 RHR-V-85A 2 DI4 C I~5 SC SAetlAN NC NA 0 .H II521 I RHR-V-85B D3 C I~5 SC SAVHAN NC tIA 0 H~ . ~

tl521 2

~ RHR-V-85C Ch C 1 ~ 5 SC SAeHAN NC tIA 0 AH. ~ ~ ~ ~

tl521 2 RHR-V-89 JIO C 14 CK ADA SA NC NA 0 GH ~ ~ ~ ~ ~ ~

tl521 2 R I IR-V-1 I 5 14 GT tIO NC FAI 0 GHJ.. .. 20 11521 2 RHR-V-116 J9 0 14 GB HO NC FA1 0 GHJ. ~ ~ ~ ~

II521 2 V t" ~

RHR-V-120 2

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Cl I F -P 3 GT II AN LC NA . ~ ~ L.. ~ 4 vr, tl521 I RHR-V-121 2 Cll F -P 3 GT HAN LC NA N ....L.. ~ 4 ~ ~,

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I tlWP-2 PUIIP AND VALVE IHSERVICE TEST PROGRAH VALVE TEST TABLES Revision 41 Page 4.4-36 1

I} 'I ts Q Q Q a C S S D D C Q D Q D Q D Q C D II aaaaa IeassDSDD cDsaasas aaaasacll ~ I S S Ila IlD a s s s Q c c D Q el c D s Q Dallaa QDDDSQSCD a D D S IIS D D a D DQDDCSSQSQ P4 I

VALVE CODE LOCATION VALVE Sl IE IN VALVE ACTUATOR --POSITION--- EXER. TEST CODE NOTES RELIEF ~S IIUIIBER CLASS Otl PIIID CATEGORY INCHES TYPE TYPE tIORHAL FAILED FREQ. REQUESTS ~ I aellerallusaaaraauaallaa cucra C IIQQSQS Dauaa D Dllulsaura CCQQD QCSCSDDD le D D D D C S D Q S Q C Q SSSDD IIDDDDDD ~ ISDQCQQSQS DCQSQCQSSD (t RHR"V-123A I E5 T GT tlO LC FAI C GHJ LE ~ 4I20 p'N H521 I RHR-V-1238 I E13 GT HO LC FAI C CHJ LE ~ IP 4I20 II521 ts RHR-V-124A 814 . F -P 1.5 HO LC NA ~ ~ ~ ~ L~ ~ ~

II521 1 3

RHR-V-1248 2 C12 F -P 1.5 GB II0 LC NA N ~ ~ ~ ~ L~ ~ ~

H521 RHR-V-125A 2 D4 F -P GB LC NA ....L. ~ ~ Ie

~

t}521 2 RHR-V-1258 D3 F -P tl0 LC NA N ~ ~ ~ ~ L~ ~ ~ se tt tl521 2

\i RHR-V-13IIA 2 F14 F 2 GB HO FAI Q GHJ ~ L ~ ~ ~ 4I20 tl521 I

'I RHR-V-1348 F5 F 2 ~ GB tIO NC FAI Q CHJ.L ~ .. 4 20 tl521 2 RHR-V-209 D5 TC ~ 75 CK NC NA R .H. L. ~ ~ ~ 4IS H5I21 I-.

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RRC-V-13A C13 FC s75 CK SA tIO NA C ~ tl ~ .L ~ ~ ~ 1 J II530 S',t RRC-V-138 813 FC .75 CK NO NA C .H. ~ L.s. 1J II530 RRC-V-IAA C14 e75 GT tIO FAI C CHJ ~ L.. IJ 4e20 lt II530 I":I RRC-V-I68 814 F .75 GT HO tlO FAI C GHJ.L ~ ~ ~ 1J 4e20 \

tl530 r..

s RRC-V-19 Fl 1 F ~ 75 SV SOL NC FC Q CHJKL ~ I le 4 H530 RRC-V-20 F12 75 SV SOL NC FC 0 CHJKL ~ ~ ~ le 4 tl53 0 RWCU-V-I F15 GT tI0 tI0 FA I C GHJ ~ L... IN 4e20 tl523 RHCU-V-4 E15 F h CT II0 NO FAI C GHJ.L... 1N 4e20 tl523 RIICU-V-40 I Hl I

~ ~ ~ I GT tl0 NO FAI C GHJ.L... IN 4e20 I

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HIIP-2 PUIIP AND VALVE IHSERVICE TEST PROGRAN VALVE TEST TABLES Revision 41 Page 4.4-37 4 4 aa a a 4 a sa 4 4 sa 4 ca 4 4 4 4 4 a 4 4 c la aa 4 4 4 4 4 4 ca 4 aaaccaass 44444444 ssaccsaaa saaaasaaaaassass 4 a s ca 4 a ca = cs aaascaaa 4 saacaaaaaaa VALVE CODE LOCATION VALVE S I LE IN VALVE ACTUATOR I

--POD IT ON--- EXER. TEST CODE NOTES RELIEF NUIIBER CLASS ON PhID CATEGORY INCHES TYPE TYPE NORtlAL FAlLED FRED. REQUESTS 4 4 sa 4 a 4 a 4 a a 4 4 a 4 Is a sa aa 4 a- ss aa 4 4 4 4 4 c 4 4 4 sa 4 araacaaa Caasaaaa 4 Q 4 4 ca ~ saaaaasaua Qaaascaaasaaaasa aacsaa Qaaaaaaca caaaaaaacc aacaaaaccaaa BA-V-109 Jb F -P GT tlAN LC NA tl ~ ~ ~ ~ L~ ~ ~

tl510 SLC-RV-29A E6 C I X 2 RV SA NC tlA tl .....P tl522 SLC-RV-298 2 D6 C I X 2 RV SA tlC NA N .....P ~ .

tl522 SLC-V-IA 2 E4 tl5 2 2 8 4 GD HO NC FAI 0 OH'.. 20 SLC-V-18 D4 8 4 GB tlO NC FAI 0 GHJ..... 20 tl522 SLC-V-4A I FS FD I 5

~ SHEAR EXPL NC NA N ....L.V. 4 t1522 SLC-V-48 I DS tIS22 FD I~5 SHEAR EXPL NC NA N ... L.V.

SLC-V-6 I Fl I C 1.5 CK SA NC NA R .H...... 2 tI522 SLC-V-7 I F13 FC I~5 CK SA tlC tlA R ~ HI ~ LI ~ I 2a 4 H522 SLC-V-33A F7 I 5

~ CK BA NC tlA 0 ~ H~ ~ ~ ~ ~ ~

tI522 SLC-V-338 D7 C I~5 CK SA NC NA 0 ~ H~ ~ ~ ~ ~ ~

H522 SW-RV-IA C14 N524 I C I RV 'A NC tlA N ~ ~ P Sff-RV-18 FI 4 C RV SA NC NA tl ~ ~ P ~ ~

tl524 2 Sff-TCV-IIA G5 8 2' GB HO NT FO 0 .II.K . ~ ~ 22 II775 SW-TCV-118 Cb 8 2' GD HO NT FO 0 IH ~ K ~ ~ 22 ll7 7 5 Sff-TCV-15A J10 8 2~5 GD HO tlT FO 0 .H.K--- ~

tl7 7 5 Sff-TCV-15D El 0 8 2.5 GD HD NT FO 0 .H.K.... 22 tl775 SW-V-IA H5 20 CK SA NC tJA 0 AH.... ~ .

IINP-2 PUIIP AND VALVE IHSERVICE TEST PROGRAM VALVE TEST TABLES Revision 44 Page 4.4-38 a c a ca ca ca ac cc cs s a c s sa a s sa s sa aa caracas saaacssassa asssascasa aaaaassa a s c s aa ss a ca aa s ac r sa s s c a as s a c s c s s a arras aacsasaasa aaassssaassssas ssasaasaas VALVE CODE LOCATION VALVE SIZE IN VALVE ACTUATOR --POSITION--- EXER. TEST CODE NOTES RELIEF NUtlBER CLASS ON ParD CATE CORY INCHES TYPE TYPE NORtlAL FAILED FREG. REQUESTS cccscscaapcarcscsssscas acres saa caaaa caacaaa- apc c a acsaa scsssaas rcrsasaascsss asasaa sc ss c a ca c s c aa sssaaacaaac ccasaaaaass Sll-V-I 8 3 C5 20 CK SA NC NA 0 ~ H~ ~ ~ ~ ~ ~

tl524 2 SW-V-2A 3 H6 9 20 BF NO NC FAI 0 GHJ .cc. 20 N524 I SW-V-28 G6 . B 20 BF NO NC FAI 0 CHJ.. 20 N524 2 SW-V-4A 3 E9 9 8 CT tlO NO FAI 0 GHJ..... 20 tl524 1 SW-V-4B G9 9 8 GT NO NO FAI G GHJ. ~ .. 20 N524 2 3 F7 9 8 GT tlO NO FAI G GHJ... ~ 20 tl524 1 SW-V-12A G3 9 18 GT NO tIC FAI 0 GHJ. ~ ~ . 20 N524 1 SW-V-128 G3 18 GT NO NC - FAI 0 GHJ.... 20 tl5 2 4 2 SW-V-24A G9 9 2 CT NO NO FAI 0 CHJ . ~ c. 20 N524 1 SW-V-249 f10 tl524 2 9 2 CT NO NO F*l 0 GHJ .... 20

-SW-V-24C K10 9 2 GT NO NO FAI 0 GHJ..... 20 N524 2 SW-V-29 C6 9 8 tlD NC FAI 0 CHJ ~ ~ ~ ~ ~ 20 11524 1 BW-V-34 Cl 1 B 1 ~ 5 GB SOL NO FO 0 GHJK.... 1 N524 2 SW-V-44 E9 9 2 GT NQ NO FAI 0 GHJ. ... 20 N524 1 SW-V-54 F7 B 2 GT tlO NO FAI G GHJ..... 20 N524 SW-V-75A A13 2 NO tIC FAI 0 GHJ ~ ~ ~ ~ ~ 20 tl5 2 4 I SW-V-759 Bl 4 r-9 2 GD NO

"--"-"--"-"" tIC FAI 0 GHJ...

~ 20 N524 2 SW-V-187A G14 9 6 CT NO NO FAI 0 GHJ..c.. 3 20

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WHP-2 PUIIP AND VALVE INSERVICE TEST PROGRAH VALVE TEST TABLES Revision 41 Page 4.4-39 ~

a as as sa sa ~s ss Qa a a a ss ~ S SS Q S Sj ja Sj Sa ssaaaacg aagg- ~ saaasaaaa aaaaggaagggaa S D a sj D Q a a Q aaaaaaaaag DQDDQSSDCD 'caassaaaaa VALVE CODE LOCATION VALVE SI2E 1N VALVE ACTUATOR --POSIT10N-- EXERT TEST CODE NOTES RELIEF IIUIIBER CLASS ON PI(ID CATEGORY 1 tICHES TYPE TYPE NORNAL FAILED FREOr REQUESTS 4 ss Da a a ss a a g a sa ss a a ss a a c Q Q Q QCD DCQD a a DCDCCQDC jr ass ja jr asDsr csssca jsaasajjagc asscasasaacgaa js casaca QDDCQDQQD js gccaaaasa aaaaaaaaca SH-V-1878 C13 GT tlO tIO FA1 8 GHJ- ~ ~ - ~ 3 20 44 tl524 2 4 (4(

SII-V-188A 3 H13 8 6 GT IIO NO FAI OH'... 20 N521 I SW-V-188B D12 B 6 GT IIO tlO FAI 0 GHJ.... 20 SII-V-223A 3 tl524 2 K5 C 3 CK SA NC tIA 0. H~ ..... ------------I N775 Sll"V-2238 3 E5 C 3 CK SA NC NA 0 ~ H ~ ~ ~ ...

N775 4 r,s SH-V-226A F7 C CK SA NC NA ~ H~ ~ ~ ~ ~ ~

N775 SII-V-2268 3 Bh C 3 CK S* NC NA 0 .H... .. ~

M775 SII-V-'t3 IA 'I 3 K4 C I CK SA NO NA 0 ~ H~ ~ ~ ~ ~ ~ s II524 I SII-V-9318 J4 C 1 CK SA NO NA 0 AH ... ~ j II524 2 TIP-V-I GH12 F .375 BALL SO NC FC 8 CHJKL ~ ~ ~ I~ 4 II604 T1P"V-2 CH12 F .375 BALL SO NC FC 0 CHJKL ~ ~ ~ I ~ 4 tlb04 *s T1P-V-3 2 GH12 F .375 BALL SO NC FC CHJKL.. ~ Ir 4 II604 4 T1P-V-4 2 GH12 F ~ 375 BALL SO tlC FC 0 CHJKL ~ 1 ~ 4 4(

s j N604 T1P-V-5 2 CH12 F .375 BALL SO NC FC 8 GH JKL ~ ~ ~ Ir 4 tlb04 TIP-V-6 GI I 1 2 FC I CK SA NO tIA 1 .H..L .. ~ 4r 11 tlb04 T IP-V-7 CHI 2 FD .375 SHEAR EXPL NO FO N .. ...V.

~ 4 II604 TIP-V-8 CH12 FD .375 SHEAR EXPL NO FO N ~ ~ ~ ~ ~ ~ V~

tlb04 TIP-V"V GI I I 2 FD .375 SHEAR EXPL NO FO .. ~ . ~ ~ V.

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WHP-2 PUHP AND VALVE INBERVICE TEST PRtjGRAH VALVE TEST TABLES Revision 41 Page 4.4-4Q gauaaaaaaassacaaaaaass a g ss ss a a ss ss a a a - ss r r caaacaaa arear araaacga sggrgagaggaaa aaraaagga aassacacaar a r ss a a a a ss a a VAI.VE CODE LOCATION VALVE ss SITE IN VALVE ACTUATOR

~

POSIT ION" EXER. TEST CODE NOTES RELIEF tlUtlDER CLASS ON PtsID INCHES TYPE TYPE NORtlAL FAILED REQUESTS sscssaaraaccrggagaaarss ~ 'ag ~ scggoccc CATEGORY gcassrgcr cg c aaa cager arssssgaaa ssssaaaccass-agg FREQ ss ac

~

r cccgrara a ss ss ss ss ss a ss a ss racgcgarga TIP-V-10 2 GH12 FD .3l5 SHEAR EXPl NO FO N ~ ~ ~ ~ ~ V~

t1604 TIP-V-11 2 GH12 FD .375 SHEAR EXPL NO FO N ... ~ ~ .V.

N604 TIP-V-15 2 G HI? F 1 SV SOL NO FC Q GHJHL... ls 4 tt 604 TOTAL COUNT 597

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Page 4.4-41 Revision 4

1. V lv x r i i T r INV-3411 states that category A and B valves shall be exercised at least once every 3 months, except as provided by INV-3412(a). INV-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 plant operations shall be specifically identified by the Owner and shall be full-stroke exercised during cold shutdowns.

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 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) 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. All of these valves wi 11 be tested during each refueling outage. The valves are identified by unique valve numbers and Code identification as to Code Class and Valve Category. See RV-25.

RHR-V-8 1, A Isolation valves in RHR shutdown cooling suction RHR-V-9 1, A line from recirculation loop A RHR-V-23 1, A RHR supply to vessel head spray RHR-V-53A, 8 1, A Loop A, B outboard isolation valve for shutdown cooling return g~tfi~~~ Valves are interlocked with reactor coolant system pressure such that valves automatically close to protect the RHR pump suction line from elevated reactor coolant system pressures. Opening circuit is disabled by the same pressure interlocks. Overpressurization of the suction line may cause the loss of shutdown RHR cooling capability. Interlocks cannot be bypassed with normal control circuits.

Q~E f' RCC-V-5 2, A Isolation valves for reactor closed cooling RCC-V-21 2, A water lines RCC-V-40 2, A RCC-V-104 2, A gg~ifi~i~nClosure of any isolation valve will interrupt cooling water flow to the Reactor Recirculation (RRC) Pump seals, to the RRC pump motor coolers and to the Orywell Air Coolers possibly causing failure of this equip-ment.

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Revision 4 Qg~~I. ~Fn ~in RFH-V-10A, 8 1, A-C Reactor feedwater inboard check valves RFH-V-32A, 8 1, A-C Reactor feedwater outboard check valves RFH-V-65A, 8, 1, A Reactor feedwater .stop valves

1) Closure of either Category A valve (RFH-V-65A, 658) would result in a loss 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.

G) V v Gmh.~ Em~i HY-V-17A, 8 2, 8 Valves provide hydraulic control fluid to the HY-V-18A, 8 2, 8 reactor recirculation flow control valve HY-V-19A, 8 2, 8 hydraulic operators. Recirculation .flow HY-V-20A, 8 2, 8 control valves are RRC-V-60A and RCC-V-608.

HY-V-33A, 8 2, 8 HY-V-34A, 8 2, 8 HY-V-35A, 8 2, 8 i~--E HY-V-36A, the reactor 8 2, ii 8

fii lyi i.:,.

recirculation flow control valve, i y .p causing undesirable Iii g:f reactivity changes in the core.

e- E CIA-V-39A, 8 3, 8 These valves cross connect the normal nitrogen supply for the Main Steam Isolation Valves and Main Steam Relief Valves (including the 7 AOS Valves) accumulators to the backup nitrogen sup-ply for the 7 AOS valves.

i ply to the AOS valve accumulators. This is unsafe to do while the plant is operating.

CI BL RRC-V-13A, 8 2, A-C Inboard and outboard isolation valves for the RRC-V-16A, 8 2, A recirculation pumps seal purge line.

Y 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.

Category A-C valves (RRC-V-13A, 8) are held open by purge water flow and can-not be closed during power operations.

Revision 4 RCIC-V-13 1, A RCIC pump discharge isolation, and containment isolation, and reactor coolant pressure isolation valve.

possibility of an t\1d intersystem LOCA.

i 1pp i h L) CadeMi. ~F LPCS-V-5 1, A LPCS discharge isolation to the reactor vessel.

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RHR-V-42A,B,C 1, A RHR discharge isolation to the reactor vessel.

~i~ ifi~jgn The risk of injuring plant personnel, overpressurizlng the associated pump and piping, or causing an intersystem LOCA makes the opening of these valves imprudent during power operations.

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CIA-SPV-18-198 3, B Emergency nitrogen supply isolation valve, CIA-SPV-1A-15A 3, 8 CIA-V-52A-66A 3, C Emergency nitrogen supply check mode.

CIA-V-52B-70B 3, C CIA-V-103A F 8 3, C Remote Emergency nitrogen supply check valve.

CIA-V-104A 5 B 3, C Remote Emergency nitrogen supply isolation valve.

t This would inhibit the system from performing its designed safety function in case of an emergency.

RHCU-V-1 1, A Containment Iso., RHCU Pump Suction Iso.

J~ RNCU-V-4 RHCU-V-40 1, A 1, A Containment Containment Iso.,

Iso.,

RHCU Pump RHCU Pump Suction Iso.

Discharge Iso.

d overheating of the pumps, significantly increasing the potential for equipment damage.

GL~ F RHR-V-123A 1, A CIV, HI-LO Pressure Iso.

RHR-V-1238 1, A CIV, HI-LO Pressure Iso.

Justifi~iog This valve is normally closed during power operations and functions as a Reactor Coolant Pressure Boundary/Containment Isolation Valve.

Opening this valve for the sole purpose of verifying its ability to close in accordance with INV-3410 requirements is not prudent, as it presents an unnecessary challenge to the containment and increases the potential for an intersystem LOCA.

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Page 4.4-44 Revision 4

~F~in HSLC-V-2A 1, 8 Prevent Radioactive Material Release HSLC-V-3A 1, A CIV, Prevent Radioactive Material Release HSLC-V-28 1, 8 Prevent Radioactive Material Release MSLC-V-38 1, A CIV, Prevent Radioactive Material Release HSLC-V-2C 1, 8 Prevent Radioactive Material Release MSLC-V-3C 1, A CIV, Prevent Radioactive Material Release HSLC-V-20 1, 8 Prevent Radioactive Material Release HSLC-V-30 1, A CIV, Prevent Radioactive Material Release HSLC-V-4 2, 8 Prevent Radioactive Material Release MSLC-V-5 2, 8 Prevent Radioactive Material Release HSLC-V-9 2, 8 Prevent Radioactive Material Release HSLC-V-10 2, 8 Prevent Radioactive Material Release tl tl 1 t't t tl operation sub]ects the valves to operation with 1005 psi across the seat.

Hhile the valves and operators are designed for the 1005 psi differential, this results in excessive wear and tear on the valves that may affect their performance when required to operate to allow the HSLC System to,operate or maintain isolation if inboard HSIV fails to close.

The valves perform two functions: (1) isolation during normal plant operation and in case of failure of the inboard HSIV to close adequately for the HSLC system to oper'ate and (2) open to allow the inboard HSLC to operate. Since the valves are normally in the closed position during plant operation and will be required to open or- close with only 35 psi across them in case of an. acci- i.....

dent, taking a risk of shutting the plant down if they don't seal after a test and subjecting the valve to severe duty compared to what it operates against is not considered prudent.

QQSfP ~ QlfK~n HS-V-146 2, 8 Isolation Valve, Main Steam Supply to Auxiliary Equipment ifi This valve is normally open at power. Closing this valve at power would isolate steam from the following equipment.

1) Reactor Feed Hater Pumps and result in loss of RPV level and a reactor scram,

2) Hain Steam Bypass Valves and result in a Technical Specification violation,

3) Main Steam Air E]ectors and result in loss of Main Condenser vacuum.

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Revision 4

2. Only those valves which are shutting down a

~~ to perform a specific function in 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 at the Owner's discretion.

RCIC-V-1, 10, 11, 21, 22, 30, 45, 46, 59, 65, 86, 111, 112, 204 RCIC-RV-17, 19 RCIC-RD-1, 2 RCIC-V-30 will be partial-stroke exercised quarterly and full-stroke exercised during refueling outages. A relief request is not required for these valves since they are not required to be included in the IST program.

3. These valves are not ASME Class 3. They have been assigned Washington State Special Numbers and are considered as SA105 material welded to an ASHE code system pressure boundary. The vendor's hydrostatic test was not maintained for sufficient time to meet ASNE requirements, This does not affect the valves ability to perform its safety function.

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-111 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. Deleted

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R bivalve.

The valve actuator was installed to facilitate stroke testing of the It is not intended for use'in normal system operations and is therefore, exempt from IWV-3413 (stroke-time measurement) and IWV-3415 (operation of fail-safe actuators) requirements.

RCIC-V-65, 66 HPCS-V-5 LPCS-V-6 RHR-V-41C, 50A, 50B, 89 RFW-V-32A, 32B CVB V lA, B, C, D, E, F, G, H, J, K, L, M, N, P, Q, R, S, T CSP-V-7, 8, 10 These valves are categorized BC. The only required safety function of these valves is its self-actuating overpressure relief function (Category C). The valve operator's safety function is passive <Category B). No stroke testing is required by the code for passive Category B valves, therefore these valves will be tested in accordance with the. code as Category C safety/relief valves <i.e., operability tests every 5 years).

MS-RV-1A, 1B, 1C, 1D MS-RV-2A, 2B, 2C, ZD MS-RV-3A, 3B, 3C These valves are operated by, a programmer with a geared nylon whee.l,- The ~

programmer is activated by a pressure switch which trips on low header pressure. The nylon wheel rotates one position to deenergize a solenoid and open a valve. If the low pressure condition persists, in 30 seconds, the nylon gear rotates and another solenoid is deenergized to open another nitrogen bottle isolation valve. The geared nylon wheel is equipped with a window through which a number 1 thru 20 may be seen. Each number corresponds to the number of solenoids deenergized in its rotational sequence which corresponds directly with the number of valves that are open.

It is the owner's position that this is not a "Valve Position Indicator" as used in IWV-3300. At best it is an indicator of whether or not specific solenoids are energized or not.

CIA-SPV-lA through 15A CIA-SPV-1B through 19B Containment isolation valves <relief valves) tested per IWV-3510 are not required to be additionally tested per IWV-3420. Reference IWV-3512.

These valves are not listed under Relief Request RV-4.

HPCS-RV-14, 35 LPCS-RV-18, 31 RHR-RV-lA, 1B., 5, 25A, 25B, 25C, 88A, 888, 88C

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These rupture discs are of is required per IHV-3620.

a nontestable design.

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Revision 4 Therefore; no testing CAC-RD-1A, 1B CCH-RD-1A, 18 RCIC-RD-1,2

11. The following HCU valves (typical of 185 valves) perform a function important to safety. These valves are non-ASME and as such are not required to be included in the IST program by the subject SER or by GL 89-04. However, because of their safety significance and because ISTC of the OM Code will require these valves to be added to the IST program in the future, the subject HCU valves are being added to the IST program at this time. These valves will be tested per HNP-2 Technical Specifica-tions referenced against each valve. This alternate testing complies with position 7 of GL 89-04.

V~lv ~@&Per i 1 HCU-114 Check vlv to scram hdr 4.1.3.2 (a, b, 5 c)

HCU-115 Charging wtr ck vlv 4.1.3.5.b.2 HCU-126 Drive water AOV 4.1.3.2(a, b, 5 c)

HCU-127 Hithdraw AOV 4.1.3.2 (a, b, & c)

HCU-138 Cooling wtr ck ylv 4.1.3.1.2.a

Reference:

SER Appendix.B, item 15

12. The following emergency diesel generator air start system valves perform a function important to safety. These valves are non-ASME and as such are not required to meet the requirements of ASME Section XI. These valves will be tested annually during DG Air Starter Motor Test. Note that two valves will be tested at a time but a failure of a single valve would be detected.

V lv DSA-SPV-5A 1/2

-5A 1/4

-5A 2/2

-5A 2/4

-5B 1/2

-5B 1/4

-5B 2/2

-5B 2/4

-5C 1/1

-5C 1/2

Reference:

SER Appendix B, item 14

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R 4.5 R li f fr i WV ~ir o~n~

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.

RELIEF REQUEST NO. RV-1 P Il ~

Revision 4 m

Various Rapid acting valves. (Applies to Open Position, Closed Position or Both Positions.)

Corrective action based on an increase in stroke time (INV-3417(a)).

fr li Some valves (generally solenoid valves) are very rapid acting. Since stroke times are to be measured to the nearest second, a 50'4 increase in stroke time cannot be consistently measured with present methodology.

P rf A limiting stroke time of two seconds .will be assigned to these valves. ,

Valves exceeding this limit will be corrected in accordance with INV-3417(b);

li f The corrective action based on an increase ln stroke time (per INV-3417(a)) is in this case, an i'mpractical requirement due to the rapid-acting nature of these valves. Measured stroke times in excess of the two second limit will identify valves with operability problems in a consistent and timely manner.

Hence, the proposed testing will provide adequate assurance of material quality and public safety. This alternate testing compline with Position 6 of GL 89-04 and with OM-10.

SER/TER

Reference:

3.1.1.1 Relief request is granted as requested.

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Revision 4 TABLE RV-11 V

CAC-FCV-1A Hydrogen Recombiner Flow Control 5 Isolation CAC-FCV-1B Recombiner Flow Control 5

'ydrogen Isolation CAC-FCV-2A Hydrogen Recombiner Flow Control 5 Isolation CAC-FCV-2B Hydrogen Recombiner Flow Control 5 Isolation CAC-FCV-3A Hydrogen Recombiner Flow Control &

Isolation CAC-FCV-3B Hydrogen Recombiner Flow Control 5 Isolation CAC-FCV-4A Hydrogen Recombiner Flow Control 5 Isolation CAC-FCV-4B Hydrogen Recombiner Flow Control 5 Isolation CSP-V-93 2 Containment Isolation CSP-V-96 2 Containment Isolation CSP-V-97 2 g* Containment Isolation CSP-V-98 2 Containment Isolation

1. For information only. Not part of relief request.

It TABLE RV-1 (CONTINUED)

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i sion 4 P I-VX-251 Radiation monitor RAD-RE-12B inlet valve P I-VX-250 Radiation monitor RAD-RE-12B outlet valve PI-VX-253 Radiation monitor RAD-RE-12B outlet valve P I-VX-256 Radiation monitor RAD-RE-12A inlet valve P I-VX-257 Radiation monitor RAD-RE-12A inlet valve P I-VX-259 Radiation monitor RAD-RE-12A outlet valve P I-VX-262 Hydrogen-oxygen monitor sample iso. valve P I-VX-263 Hydrogen-oxygen monitor sample iso. valve P I-VX-264 Hydrogen-oxygen monitor sample iso. valve P I-VX-265 Hydrogen-oxygen monitor sample iso. valve P I-VX-266 Hydrogen-oxygen monitor sample iso. valve PI-VX-268 Hydrogen-oxygen monitor sample iso. valve P I-VX-269 Hydrogen-oxygen monitor sample iso. valve PSR-V-X73-1, 2 A Containment Isolation PSR-V-X77A1, 2 A Containment Isolation PSR-V-X77A3, 4 A Containment Isolation PSR-V-X80-1, 2 A Containment Isolation PSR-V-X82-1, 2 A Containment Isolation PSR-V-X82-7, 8"'2= " 'A Containment Isolation PSR-V-X83-1,2 A Containment Isolation PSR-V-X84-1, 2 A Containment Isolation PSR-V-X88-1, 2 A Containment Isolation RHR-V-60A Loop A sample (inboard)

RHR-V-60B Loop B sample (inboard)

RHR-V-75A Loop A sample (outboard)

RHR-V-75B Loop 8 sample (outboard)

RRC-V-19 Reactor recirculation sampling Iso valve.

RRC-V-20 Reactor recirculation sampling Iso valve.

SH-V-34 Cooling Hater Isolation TIP-V-1 Containment Isolation Tjp-V-2 Containment Isolation TIP-V-3 Containment Isolation TIP-V-4 Containment Isolation TIP-V-5 Containment Isolation TIP-V-15 Containment Isolation

RELIEF REQUEST NO. ~V-System Standby Liquid Control (SLC)

Valve(s) SLC-V-6, SLC-V-7 ASHE Code Class: 1 Category'. B-C (SLC-V-6)

Classification A-C (SLC-V-7)

Function Standby Liquid Control discharge to reactor vessel.

Code Testing 1. Quarterly exercising (INV-3521)

Requirement 2. Cold shutdown exercising (INV-3522)

Basis for 1. Valves have no operator with which they may be stroked.

Rel i ef 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 D 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 for SLC-V-7 will be verified in conjunction with 10CFRSO Appendix J (Type C) testing.

The proposed testing complies fully with the intent of the Code (INV-3522).

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

N A / 0 1 1 SER/TER

Reference:

3.4.1.1 Relief granted as requested'

N System RELIEF REQUEST NO. ~V-Containment Instrument Air P II ~

Rev) s)on 4 Valve(s)

ASME Valves affected by this rel)ef request are )dentif)ed )n Classification Table RV-3.

Function Code Testing quarterly testing (INV-3412)

Requ)rement Basis,.for The CIA-V-40 series check valves are located )ns)de Relief the conta)nment and are )naccess)ble during power operations. There is no way to remotely isolate the valves and observe the pressure decay of .the accumulators.

2. There ) s no local or remote position indication for these check valves.

Alternate Testing 1. During refueling outages, pressure decay tests w)11 to be Performed be performed for the Automatic Depressurization System accumulators associated with'the Hain Steam Safety/

Relief Valves in order to verify closure ability of CIA-V-40 series check valves and opening of CIA-V-31A and 318. Each accumulator will be tested at least every two years.

2. Closure ab)lity of CIA-V-Zl, 31A, and 318 w)ll be verif)ed by normal 10CFR50, Append)x J (Type C) testing.

The proposed test)ng qualitatively verifies valve closure on the most practi-cal regular basis. Th/s sat)sf)es the )ntent of the Code (INV-3412). Valve opening )s verified when the accumulators are pressur)zed )n preparat)on for the pressure decay test.

The valves in Table RV-3 are in the pneumatic supply to the auto-depres-surization System valves, a safety related system. However, the proposed alternate testing together with the redundancy of the pneumatic supplies and

)ndividual accumulators, of the ADS valves themselves and of the high pressure injections systems assures an acceptable level of quality and public safety.

A / M 7 1 1 SER/TER

Reference:

3.9.1.1., 3.9.1.2 Relief granted as requested.

R TABLE RV-3 CIA-V-31A A-C Instrument air supply to ADS valves B 'IA-V-31 A-C (outside containment)

CIA-V-40 H, N, 2 A-C Instrument air to ADS Accumulators P, R, S, U, and (inside containment)

V CIA-V-21 A-C Instrument air supply to containment (outboard check valve).

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Revision 4 REQUEST FOR RELIEF NO. gV-4 System, Valves, Category A, Containment Isolation Valves.

and ASME Classification Function Containment Isolation Code Testing Leak Test Requirements (INV-3420)

Requirement Basis for The purpose of leak rate testing is, ultimately, to Relief the ~v ~

assure that the limits of 10CFR100 are not exceeded.

leakage from the containment is the critical parameter in leak rate testing, not individual valve leak Hence rates. Appendix J Leak Test requirements specifically address leakage requirements for valves functi,oning as con-tainment isolation valves. Exceptions to the applicability of Appendix J Leak Test requirements are detailed in the NNP-2 Technical Specifications and FSAR.

Alternate Testing 1, These valves wi 11 be leak tested according to 10CFR50, to be Performed Appendix J as detailed in the WNP-2 Technical Speci-fications and FSAR in .lieu of INV-3420. Exceptions and deviations from Appendix 3 Type C test require-ments are noted in Table RV-4.

2. NNP-2 wi 1 1 specify a perm) ssible leakage imi t based 1

on valve type, size and equipment history for those valves being Type C leak tested.

3. Valves exceeding their leakage limits will be repaired or replaced.

The Appendix J limit of 060 La will be met (060 La is equivalent to 67,920 SCCM).

1 / fe These valves are all category A valves and whether active or passive perform a common safety function of containment isolation. The Appendix J and Technical Specification requirements recognize this safety function and provides leak test requirements based on this safety function. The proposed alternate test-ing provides adequate assurance of quality and public safety.

NR A / R 0 M 7 1 SER/TER

Reference:

3.1.2 1, 3.1.3.1

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The relief request was granted provided that NNP-2 complies with the require-ments of paragraphs INV-3426 and -3427(a), Analysis of Leakage Rates and Corrective Action, as described in GL 89-04 Position 10.

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TABLE RV-41 V v II 5!Itlh

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Revision 4 CAC-FCV-1A 2 A DW-V-156 2 A CAC-FCV-18 2 A DW-V-157 2 A CAC-FCV-2A 2 A EDR-V-19 2 A CAC-FCV-28 2 A EDR-V-20 2 A CAC-FCV-3A 2 A FDR-V-3 2 A CAC-FCV-38 2 A FDR-V-4 2 A CAC-FCV-4A 2 A FPC-V-149 2 A CAC-FCV-48 2 A FPC-V-153 2 A CAC-V-2 2 A FPC-V-154 2 A CAC-V-4 2 A FPC-V-156 2 A CAC-V-6 2 A HPCS-V-4 1 A CAC-V-8 2 A HPCS-V-5 1 AC CAC-V-11 2 A HPCS-V-12 2 CAC-V-13 2 A HPCS-V-15 2 CAC-V-15 2 ~

A HPCS-V-23 2 CAC-V-17 2 A HPCS-V-65 2 CAS-V-730 2 A HPCS-V-68 2 CAS-VX-82e 2 A HY-V-1/A 2 CEP-V-1A 2 A HY-V-178 2 CEP-V-18 2 A HY-V-18A 2 CEP,. V-2A 2 A HY-V-188 2 CEP-V-28 2 A HY-V-19A 2 CEP-V-3A 2 A HY-V-198 2 CEP-V-38 2 A HY-V-20A 2 CEP-V-4A 2 A HY-V-208 2 CEP-V-48 2 A HY-V-33A 2 CIA-V-20 2 A HY-V-338 2 CIA-V-21 2 AC HY-V-34A 2 CIA-V-30A 2 A HY-V-348 2 CIA-V-308 2 A HY-V-35A 2 CIA-V-31A 2 AC HY-V-358 2 CIA-V-31 8 2 AC HY-V-36A 2 CSP-V-1 2 A HY-V-368 2 CSP-V-2 2 A LPCS-FCV-11 2 CSP-V-3 2 A LPCS-V-1 2 CSP-V-4 2 A LPCS-V-5 1 CSP-V-5 2 A LPCS-V-6 1 AC CSP-V-6 2 A ~

LPCS-V-12 2 CSP-V-7 2 AC LPCS-V-66 2 CSP-V-8 2 AC LPCS-V-67 2 CSP-V-9 2 A MS-V-16 1 CSP-V-10 2 AC MS-V-19 1 CSP-V-93 2.' A MS-V-22A 1 CSP-V-96 2 A MS-V-228 1 CSP-V-97 A MS-V-22C 1 CSP-V-98 2 A MS-V-22D 1 For information only not part of relief request.

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Revision 4 TABLE RV-4 (CONTINUED)

Elks V lv Nm MS-V-28A A. 1 A P I-EFC-X44Ac AC HS-V-288 A 1 A PI-EFC-X44Ad 1 AC MS-V-28C A 1 A P I-EFC-X44Ae 1 AC HS-V-28D A 1 A PI-EFC-X44Af 1 AC HS-V-67A A 1 A PI-EFC-X44Ag 1 AC MS-V-678 A 1 A . PI-EFC-X44Ajl 1 AC HS-V-67C A A P I-EFC-X44A] 1 AC MS-V-67D A 1 A PI-EFC-X44Ak 1 AC HSLC-V-3A A 1 A P I-EFC-X44A1 1 AC HSLC-V-38 A 1 A P I-E FC-X44Am 1 AC MSLC-V-3C A 1 A PI-EFC-X448a 1 AC MSLC-V-3D A 1 A PI-EFC-X448b 8 1 AC PI-EFC-X18A 8 1 AC PI-EFC-X448c 8 1 AC PI-EFC-X188 8 1 AC PI-EFC-X448d 1 AC PI-EFC-X18C 8 1 AC PI-EFC-X448e 1 AC PI-EFC-X18D 8 1 AC PI-EFC-X448f 1 AC P I-E FC-X29b 8 2 I AC PI-EFC-X448g 8 1 AC PI-EFC-X29f 8 2 AC PI-EFC-X448I1 8 1 AC PI-EFC-X30a 8 2 AC PI-EFC-X448] 8 1 AC PI-EFC-X30f 8 2 AC P I-EFC-X448IQ 8 1 AC PI-EFC-X37e 8 1 AC P I-EFC-X4481 8 1 AC PI-EFC-X37f 8 1 AC P I-EFC-X448m 8 1 AC PI-EFC-X38a 8 1 AC PI-EFC-X61a 1 AC PI-EFC-X38b 8 1 AC PI-EFC-X61 b 1 AC PI-EFC-X38c 8 1 AC PI-EFC-X61c 1 AC P I-EFC-X38d 8 1 AC PI-EFC-X62b 2 AC PI-EFC-X38e 8 1 AC PI-EFC-X62c 1 AC P I-EFC-X38f 8 1 AC P I-EFC-X62d 1 AC PI-EFC-X39a 8 1 AC P I-EFC-X66 2 AC P I-EFC-X39b 8 1 AC PI-EFC-X67 2 AC P I-EFC-X39d 8 1 AC PI-EFC-X69a 1 AC P I-EFC-X39e 8 1 AC PI-EFC-X69b 1 AC P I-EFC-X40c 8 1 AC PI-EFC-X69e 1 AC PI-EFC-X40d 8 1 AC P I-EFC-X69f 1 AC PI-EFC-X40e 8 2 AC PI-EFC-X70a ~

1 AC P I-EFC-X40f 8 2 AC PI-EFC-X70b 1 AC PI-EFC-X41c 8 1 AC P I-EFC-X70c 1 AC P I-EFC-X41d 8 1 AC PI-EFC-Xjod 1 AC P I-EFC-X41e 8 2 AC PI-EFC-X70e 1 AC P I-EFC-X41 f 8 2 AC P I-EFC-X70f 1 AC P I-E FC-X42a 8 1 AC PI-EFC-X7la 1 AC P I-E FC-X42b 8 1 AC P I-EFC-Xj b 1 1 AC P I-EFC-X42c 8 2 AC PI-EFC-X71 c 1 AC P I-EFC-X42f 8 2 AC P I-EFC-X71 d 1 AC PI-EFC-X44Aa 8 1 AC PI-EFC-X71 e 1 AC PI-EFC-X44Ab 8 1 AC PI-EFC-X71 f 1 AC

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Rev) sion 4 TABLE RV-4 (CONTINUED)

V v Gln.z PI-EFC-X72a AC P I-VX-221 2 A PI-EFC-Xjzf AC P I-VX-250 2 A P I-EFC-X73a AC P I-VX-251 2 A PI-EFC-X73e AC PI-VX-253 2 A PI-EFC-X74a AC PI-VX-256 2 A PI-EFC-X74b AC P I-VX-257 2 A PI-EFC-X74e AC PI-VX-259 2 A PI-EFC-X74f AC PI-VX-262 2 A PI-EFC-X75a AC PI-VX-263 2 A PI-EFC-X75b AC PI-VX-264 2 A PI-EFC-X75c AC PI-VX-265 2 A PI-EFC-X75d AC PI-VX-266 2 A PI-EFC-X75e AC PI-VX-268 2 A PI-EFC-X75f AC PI-VX-269 .2 A PI-EFC-X78a AC PSR-V-X73-1 2 A PI-EFC-X78b AC PSR-V-X73-2 2 A P I-EFC-X78c AC PSR-V-X77A1 1 A P I-EFC-X78f AC PSR-V-X77A2 1 A P I-EFC-X79a AC PSR-V-X77A3 1 A P I-EFC-X79b AC PSR-V-X77A4 A P I-EFC-X82b. AC PSR-V-X80-1 2 A PI-EFC-X84a AC PSR-V-X80-2 2 A P I-EFC-X86A AC PSR-V-X82-1 2 A PI-EFC-X86B AC PSR-V-X82-2 2 A P I-EFC-X87A AC PSR-V-X82-7 2 A P I-EFC-X878 AC PSR-V-X82-8 A P I-E FC-X106 AC PSR-V-X83-1 A P I-EFC-X107 AC PSR-V-X83-2 A PI-EFC-X108 AC PSR-'-X84-1 A PI-EFC-X109 AC PSR-V-X84-2 A P I-EFC-X110 AC PSR-V-X88-1 A P I-EFC-X111 AC PSR-V-X88-2 A PI-EFC-X112 AC RCC-V-5 A PI-EFC-X113 AC RCC-V-21 A PI-EFC-X1,14 AC RCC-V-40 A PI-EFC-X115 AC RCC-V-104 A P I-EFC-X119 ,AC RCIC-V-8 A Pr-V-X42d A RCIC-V-1 3 A P I-V-X54Bf A RCIC-V-1 9 A P I-V-X61 f A RCIC-V-28 AC P I-V-X62 f A RCIC-V-31 C A P I-V-X69c A RCIC-V-40 ~

AC P I-VX-216 A RCIC-V-63 A P I-VX-218 A RCIC-V-64 A PI-VX-219 A RCIC-V-66 AC P I-VX-220 A RCIC-V-68 A

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Rev ) s1on 4 TABLE RV-4 (CONTINUED) g 'ELK kU Gl ~ Gaia~~~

RCIC-V-69 2 A RHR-V-123A A RCIC-V-76 1 A RHR-V-1238 1 A RCIC-V-184 2 A RHR-V-124A 2 A RCIC-V-740 2 A RHR-V-1248 2 A RCIC-V-742 1 A RHR-V-125A 2 A RFW-V-10A 1 AC RHR-V-1258 2 A RFW-V-108 1 AC RHR-V-134A 2 A RFW-V-32A 1 AC RHR-V-1348 2 A RFW-V-328 1 AC RHR-V-209 1 AC RFW-V-65A 1 A RRC-V-13A 2 AC RFW-V-658 1 A RRC-V-138 2 AC RHR-FCV-64A 2 A RRC-V-16A 2 A RHR-FCV-648 2 A RRC-V-168 2 A RHR-FCV-64C 2 A RRC-V-19 . 1 A RHR-RV-30 2 AC RRC-Y-20 1 A RHR-RV-36 2 AC RWCU-V-1 1 A RHR-V-4A 2 A RWCU-V-4 A RHR-V-48 2 A RWCU;V-40 1 A RHR-V-4C 2. A SA-V-109 2 A RHR-V-8 1 A SLC-V-4A AD RHR-V-9 .1 A SLC-V-48 1 AD RHR-V-11A 2 A SLC-V-7 1 AC RHR-V-118 2 A TIP-V-1 2 A RHR-V-16A 2 A TIP-V-2 2 A RHR-V-168 2 A TIP-V-3 2. A RHR-V-17A 2 A TIP-V-4 2 A RHR-V-178 2 A TIP-V-5 2 A RHR-V-21 2 A TIP-V-6 2 AC RHR-V-23 1 A TIP-V-7 2 AD RHR-V-24A 2 A TIP-V-8 2 AD RHR-V-248 2 A TIP-V-9 2 AD RHR-V-27A 2 A TIP-V-10 2 AD RHR-V-278 2 A TIP-V-11 2 AD RHR-V-41A AC TIP-Y-15 2 A RHR-V-418 1 AC RHR-V-41C 1 AC RHR-V-42A 1 A RHR-V-428 1 A RHR-V-42C 1 A RHR-V-50A 1 AC RHR-V-508 1 AC RHR-V-53A 1 A RHR-V-538 1 A RHR-V-73A 2 A RHR-V-738 2 A RHR-V-I20 2 A RHR-V-121 2 A

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Revision 4 N TAB RV 4 The following notes identify exceptions to Appendix J (Type C) Leak Test requirements detailed in the HNP-2 FSAR 'and Technical Specification where the, associated basis is documented.

A. Main steam isolation valves and associated leakage control system valves are type C tested at least once per 18 months. Maximum allowable leakage rate for these valves is specified in Technical Specification 3.6.1.2.c and the leakage from these valves is not included in the cumulative type 8 and C leakage rate.

B. These valves are not subject to a type C leak rate test or included in a type A test (FSAR Table 6.2-16, notes 27, 28 and 29). These valves include:

1) excess flow check valves located in instrumentation lines used to follow the course of an accident,

2) post LOCA hydrogen monitor isolation valves,

3) transversing incore probe explosi'vely actuated shear valves, and

4) isolation valves in the hydraulic control lines of the reactor recirculation line isolation .valves.

C. These valves are pressurized with fluid from a seal system and are hydraulically leak tested at 38.2 psig. Maximum allowable leakage rate for these valves is specified in Technical Specification 3.6.1.2.d. The leakage from these valves is not included in the cumulative type 8 and C leakage rate (Appendix J section III.C.3 and Technical Specification 4.6.1.2.g).

D. These valves are not subject to type C leak rate test and are tested per Technical Specification 4.4.3.2.2. These valves are reactor coolant pressure boundary pressure isolation valves and are hydraulically leak tested at 950 (+ or 10) psig at least once every 18 months in lieu of type C test. Maximum allowable leakage rate for these valves is specified in Technical Specification 3.4.3.2.e which is much more restrictive than that allowed by the Code. Testing of these valves meets all the requirements of INV-3420 except that corrective action is based on Technical Specification requirements and not per IHV-3427(b),

E. Not subject to type C leak rate test, but tested as part of type A test.

Page 4 5-14 Revision 4 REQUEST FOR RELIEF NO. ~V-Incorporated in Relief Request RV-4 as of Revision 3b.

Revision 4 RELIEF REQUEST NO. ~RV-System Primary Containment Cooling and Purge Valves CVB-V-1A, B, C, 0, E, F, G, H, J, K, L, M, N, P, Q, R, S, T ASME Code Class: 2 Category: A-C Classification Function To .break vacuum on the drywell to suppression chamber down-comers and imi 1 fr h wn Code Testing IWV-3420, Valve Leak Rate Test Requirement Basis for These check valves cannot be tested individual.ly, there-Re 1 i ef fore, 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 drywell to the suppression pool chamber does not exceed Technical 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 These valves will be leak tested according to WNP-2 to be Performed Technical Specifications, at least once per 18 months by conducting a drywell-to-suppression chamber bypass leak test. These valves are verified closed by redundent posi-tion indicators, tested in the open direction using a torque wrench, and each valve seat is visually inspected.

Corrective actions will be as specified in the Technical Specification.

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.

0 d M SER/TER

Reference:

3.10.1.1 Relief granted as requested.

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RELIEF REQUEST NO. 3V-7 9 ~

Revision 4 System Containment Instrument Air Valves CIA-V-40M, N, P, R, S, U, V ASHE Code Class: 2 Category: A-C Classification Function 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 l. IWV-3424, Seat Leakage Measurement.

Requirement Basis for 1. These check valves can only be tested by the method Relief specified in IWV-3424(b) with much more difficulty than using the pressure decay method described below.

The test methods for measuring seat leakage past a valve as specified in the Code imposes an undue burden on the Owner without commensurate compensating benefits.

Alternate Testing 1. These check valves will be leak tested during a pres-sure decay test on the accumulators. This test method will provide accurate measurements of leakage rates and is accepted by OM-10 (ASME/ANSI OMa-1988, Part 10).

li f The pressure decay method of measuring leakage rates is recognized as an accurate "method of measuring leakage rates. The proposed alternate testing provides adequate assurance of material quality and public safety.

A n / M SER/TER

Reference:

3.9.1.3 Relief granted as requested.

lg H 4

Revision 4 RELIEF REQUEST NO. ~RV-System Residual Heat Removal Valves RHR-V-209 ASME Code Class: 1 Category: A-C Classification Function Containment isolation and Reactor Coolant System Pressure Boundary and r u li f i in w n v v Code Testing l. INV-3521, that each category C valve be exercised at Requirement least once every 3 months.

Basis for 1. This check valve is located inside the containment and Relief 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval (per NNP-2 Technical Specifica-tion). Additionally, containment will not be de-inerted during all cold shutdowns.

Al ternate Testing 1. Thi s check valve wi 1 1 be exerci sed at refuel ing out-to be Performed ages. fi Furthermore, thi s check val ve i s veri ed to shut by being leak tested at least once every 18 months per Technical Specification 4.4.3.2.2.

This valve is normally closed and is verified to be adequately seated by leak tests at least once every 18 months. This valve performs the passive safety functions of containment isolation and reactor coolant system pressure isola-tion. 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 inherent potential for violations of the NNP-2 Technical Specification.

This will provide adequate assurance of material quality and public safety.

N A / D M 7 SER/TER

Reference:

3.3.1.1 Relief granted as requested.

P9~

Revision RELIEF REQUEST NO. ~

System RCIC, HPCS, LPCS, and RHR.

Qm. Gaimarz ~F 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 A-C RHR Loop A, 8 discharge to the recircu-lating pump discharge Code Testing l. INV-3521, that check valves be 'exercised at least Requirement once every 3 months, except as provided by INV-3522.

Basis for 1. The Velan operation and maintenance manual for the Relief testable check valves used in the RCIC, LPCS, HPCS, and RHR systems specifies that the valves are not to be operated with greater than 5 psi differential pressure across the disc. To achieve this condition during shutdown with any substantial vessel level will require that the manual .isolation valve downstream be operated and pressure equalized across the disc prior to valve stroking. It ts not possible to perform this task with the containment inerted.

Alternate Testing 1. These check valves will be exercised with the reactor to be Performed at cold shutdown and the containment.deinerted.

Cold shutdown testing shall commence immediately (within 48 hours) following establishment of cold shutdown de-inerted conditions. Testing shall conti nue only as long as the plant is scheduled to be in cold shutdown with the containment de-intered.

Cold shutdown testing will be conducted in a manner which wi 11 not impede plant startup. Cold shutdown valves are tested in groups by several different procedures. The decision whether to start cold shutdown testing on any particular procedure will depend on the estimated length of the cold shutdown de-inerted period, system outages/conditions, time interval from the last cold shutdown testing, or other particular conditions. All cold shutdown valves will

I 4

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Revision 4 be tested during each refueling outage. Testing is not required if the time period since the previous test is less than three months.

For extended outages, cold- shutdown testing does not need to start within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months as long as all valves are tested before startup.

This alternate testing meets the intent of OM-10 which will be required in the future.

j / f j These valves are normally closed and while in the closed position function as

1) containment isolation valves and 2) high-low pressure interface valves be-abilityty tween the reactor coolant and portions of the Emergency Core Cooling System.

These valves must open to facilitate operation of part of the Emergency Core Cooling System. The valves will normally only be operatedquality in the event of an emergency during normal power operations. Lengthening the interval between tests as recommended will not preclude the timely evaluation of valve oper-and thus provides adequate assurance of material . and public safety.

1 1 SER/TER

Reference:

3.1.4.1 Relief granted as. requested ~

IO

4 RELIEf REQUEST NO. Q~

DELETEO PRIOR TO SER REVIEW

RELIEF REOUEST NO. ~V-11 Pg~

Revision 4 System Process Instrumentation Valves PI-EFC-X72f, X73e and TIP-V-6 ASME Code Class: 1 Category: AC Classification 2 (TIP-V-6)

Function Containment Isolation.

Code Testing INV-3521. Check valves shall be exercised at least once Requirement every 3 months.

Basis for These containment isolation valves are located inside the Re 1 i ef containment and can only be observed/tested during cold shutdown conditions when the containment is de-inerted.

Alternate Testing These valves will be tested at cold shutdown conditions to be Performed with the containment de-inerted.

Cold shutdown testing shall commence immediately (within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) following establishment of cold shutdown de-inerted conditions. Testing shall continue only as long as the plant is scheduled to be in cold shutdown with the contain-ment de-intered. Cold shutdown testing will be conducted in a manner which. will not impede plant startup; Col,d shutdown valves are tested in groups by several different procedures. The decision whether to start cold shutdown testing on any particular procedure will depend on the estimated length of the cold shutdown de-inerted period, system outages/conditions, time interval from the last cold shutdown testing, or other particular conditions. All cold shutdown valves will be tested during each refueling outage. Testing is not required if the time period since the previous test is less than three months. For extended outages, cold shutdown testing does not need to start within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months as long as all valves are tested before startup.

.This alternate testing meets the intent of OM-10 which will be required in the tuture.

Lengthening the time interval between tests as recommended will not preclude the timely evaluation of valve operability and thus provides adequate assur-ance of material quality and public safety.

N A n / M 7 1 1 SER/TER

Reference:

3.11.1.1.

Relief granted as required.

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Revision 4 RELIEf REQUEST NO. ~V~

DELETED Design change deleted valves DO-V-40A, 40B.

II RELIEF REQUEST NO. QV ~1 Pg~

Revision 4 System Main Steam Val ves HS-RV-30, 4A, 4B, 4C, 4D, 5B, 5C ASHE Code Class: 1 Category: BC Classification Function These valves form the Auto-Oepressurization System and, as such, function to relieve reactor vessel pressure to the extent that the low pressure coolant injection system could be brought on line and perform its safety function.

Code Testing l. INV-3411, Test Frequency Requirement 2. INV-3413, Stroke Time of Power Operated Valves Basis for l. Valve exercise on a quarterly basis during power oper-Relief ations could cause power transients resulting in a reactor shutdown. Valve testing at cold shutdown con-ditions is not desirable because of the increased po-tential for damaging the valve seat. It is not desir-able to test more frequently than refueling outages to reduce the number of challenges to the valves.

2. These valves are not equipped with position indicators based directly on the valve obturator,or valve actua- ,

tor position. Thermocouples are installed in the ex-haust piping to provide indication as to whether or not the valve is properly seated. Acoustic monitors are also installed on the exhaust piping to provide in-direct valve position indication. This, indication lags actual valve position and is not accurate at reduced pressures'lternate Testing The valves will be exercised at least once every 18 months to be Performed in accordance with NNP-2 Technical Specification. The valves will be verified fully open and closed based on available instrumentation and appropriate system response.

1 m The proposed alternate testing adequately evaluates the operational readiness of these valves commensurate with their safety function. This wi 11 help re-duce the number of challenges and failures of safety relief valves and still provide timely information regarding operability and degradation. This will provide adequate assurance of material quality and public-safety.

M 1 1 SER/TER

Reference:

3.6.1.1 Relief granted as requested.

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Revision 4 RELIEF REQUEST NO. RV-14 System Control Rod Drive Valves CRD-V-10 and 180, CRD-V-ll and 181 ASME Code Class: 2 Category: B Classification Function These valves are the vent and drain valves on the scram discharge volumes.

Code Testing INV-3413. Measure the stroke-time of power operated valves.

Requirement Basis for CRD-V-10 and 180, as well as CRD-V-ll and 181 are located Relief in series, share the same position indication, and the same actuating source (air). Valve indication indicates shut when ~i only

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when valve closes. Valve indication indicates open valves are open. These valves are always operated in pairs and cannot be operated individually with-out modifying the valve control system.

Alternate Testing The combined stroke-time of both valves will be measured to be Performed in lieu of individual valve stroke-times. Valve closure will be verified by local observation.

li / f Valve operability is adequately evaluated by the proposed alternate testing.

This provides adequate assurance of material quality and public safety.

NR n D SER/TER

Reference:

3.7.1.1 Relief granted as requested.

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QV-l'j 9~

Revision 4 RELIEF REQUEST NO.

System Various Valves All excess flow check valves in the program ASHE Classification Function Containment Isolation Code Testing l. IHV-3521, Test Frequency Requirement Basis for 1. These are instrumentation line excess flow check Relief valves that are tested per HNP-2 Technical Specifica-tion at least once every 18 months. Quarterly testing or cold shutdown testing requires more frequent tests which would be a hardship on WNP-2 with little compen-sating benefits.

Alternate Testing l. These valves shall be exercised at least once every to be Performed 18 months per WNP-2 Technical Specifications. It will be verified that the valve checks flow at greater than 10 psid differential pressure in hydraulic service and 15 psid differential pressure in pneumatic service.

Testing the excess flow check valves as specified by HNP-2 Technical Specifi-cations will provide timely identification of valve failure and/or degrada-tion. This provides adequate assurance of material quality and public safety.

D 1 1 SER/TER

Reference:

3.1.5.1 Relief granted as required.

l e 4'

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Revision 4,

TABLE RV-151 MXW!CX MZa~~r P I-EFC-X18A 1 AC PI-EFC-X44Bb AC PI-EFC-X18B 1 AC PI-EFC-X448c AC PI-EFC-Xl SC 1 AC PI-EFC-X44Bd AC PI-EFC-X180 1 AC PI-EFC-X44Be AC P I-EFC-X29b 1 AC P I-EFC-X44Bf AC P I-EFC-X29f 2 AC P I-EFC-X44Bg AC PI-EFC-X30a 2 AC PI-EFC-X44Bh AC PI-EFC-X30f 2 AC PI-EFC-X44B] AC PI-EFC-X37e AC PI-EFC-X448k AC PI-EFC-'X37f AC PI-EFC-X44B1 AC P I-EFC-X38a AC PI-EFC-X44Bm AC PI-EFC-X38b AC PI-EFC-X61a AC PI-EFC-X38c AC P I-EFC-X61b AC PI-EFC-X38d AC PI-EFC-X61 c AC P I-EFC-X38e AC PI-EFC-X62b AC P I-EFC-X38f AC PI-EFC-X62c AC PI-EFC-X39a AC PI-EFC-X62d AC PI-EFC-X39b AC PI-EFC-X66 AC PI-EFC-X39d AC PI-EFC-X67 AC P I-EFC-X39e AC P I-EFC-X69a AC PI-EFC-X40c AC PI-EFC-X69b AC PI-EFC-X40d AC PI-EFC-X69e AC PI-EFC-X40e AC PI-EFC-X69f AC P I-EFC-X40f AC PI-EFC-X70a AC P I-EFC-X41 c AC PI-EFC-X70b AC PI-EFC-X41d AC PI-EFC-X70c AC PI-EFC-X41e AC P I-EFC-X70d AC PI-EFC-X41f AC P I-EFC-X70e AC P I-EFC-X42a AC P I-EFC-X70f AC P I-EFC-X42b AC P I-EFC-X7 1 a AC PI-EFC-X42c AC PI-EFC-X71b AC P I-EFC-X42f AC PI-EFC-X71c AC P I-E FC-X44Aa AC PI-EFC-Xjl d AC PI-EFC-X44Ab AC P I-EFC-X71e AC P I-EFC-X44Ac AC PI-EFC-X71 f AC PI-EFC-X44Ad AC PI-EFC-X72a AC P I-EFC-X44Ae AC PI-EFC-X73a AC P I-EFC-X44Af AC PI-EFC-X74a AC PI-EFC-X44Ag AC P I-EFC-X74b AC P I-EFC-X44Ah AC PI-EFC-X74e AC PI-EFC-X44A j AC P I-E FC-X74f AC P I-EFC-X44Ak AC PI-EFC-X75a AC PI-EFC-X44A1 AC PI-EFC-X75b AC PI-EFC-X44Am AC P I-EFC-X75c AC PI-EFC-X44Ba AC PI-EFC-X75d AC For information only not part of relief request.

N a

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Revi s ton 4 TASLE RV-15 (CONTINUED)

CL Cat.l~KI5 PI-EFC-X75e 1 AC P I-EFC-X7 5P 1 AC P I-EFC-X78a 2 AC PI-EFC-X78b 1 AC PI-EFC-X78c 1 AC P I-EFC-X78f 1 AC PI-EFC-X79a 1 AC PI-EFC-X79b 1 AC PI-EFC-X82b 2 AC P I-EFC-X84a 2 AC P I-EFC-X86A 2 AC PI-EFC-X868 2 AC PI-EFC-X87A 2 AC PI-EFC-X878 2 AC P I-EFC-X106 1 AC PI-EFC-X107 1 AC PI-EFC-X108 1 AC P I-EFC-X109 1 AC P I-E FC-X110 1 AC P I-EFC-X111 1' AC I-E FC-X112 1 AC PI-EFC-X113 1 AC PI-EFC-X114 AC PI-EFC-X115 1 AC PI-EFC-X119 2 AC

RELIEF REQUEST HO. f~

Il ~

Revision 4 DELETED SER/TER

Reference:

3.2.1.1 Re1ief request denied for RCIC-V-111 and 112.

I

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Revision RELIEF RE/VEST NO. g~

System HPCS, LPCS, and RHR Valves HPCS-V-7, LPCS-V-33, and RHR-V-84A, 84B, 84C ASHE Code Class: 2 Category: C Classification Function Open: To permit the water leg pump to it fill the system with water and maintain pressurized.

Close: To prevent overpressurization of the waterleg pump and associated piping.

Code Testing INV-3521, Test Frequency Requirement Basis for These valves cannot be verified to be closed without either Re 1 i ef installing a test connection or dismantling the valve and inspecting the internals (which requires grinding out the seal weld). The associated stop-check valve is located in series with the check valve and performs the same function as the check valve. Closure of the stop-check.is verified quarterly. The overpressure protection function is pro-vided by the two valves and in addition a low pressure re-lief valve is installed should both the the check and stop-check valves fail or leak excessively.

Alternate Testing These check valves will be tested in the open position quar-to be Performed terly per INV-3522. The stop-check and check valve will be tested in combination and verified closed (one or both) during the quarterly surveillance test. In addition, the stop-check valve will be shut manually to ensure no binding exists. tf excessive leakage ts noted, both valves shall be repaired or replaced.

li /

The proposed alternate testing verifies valve operability in the open posi-tion, but not the closed. However, the stop-check valve located in series with the check valve is verified to open and close quarterly. The required testing would be a hardship on WNP-2 with little compensating benefits. The alternate testing wi 11 provide adequate assurance of material quality and public safety.

N A / 0 'vl 1 1 SER/TER

Reference:

3.1.6.1 Relief requested granted, provided if excessive leakage is noted, both valves shall be repaired or replaced.

Revision 4 RELIEF REQUEST NO. EVE System Main Steam Valves MS-V-37A, 8, C, 0, E, F, G, H, J, K, L, M, N, P, R, S, U, V MS-V-38A, B, C, 0, E, F, G, H, J, K, L, M, N, P, R, S, U, V ASME Code Class: 2 Category: . BC Classification Function Open: To break vacuum in the downcomers of the main steam relief valves.

Close: To direct steam to the quenchers in the wetwell.

Code Testing INV-3521, Test Frequency Requirement Basis for Testing requires personnel access to the containment. This Rel i ef requires that the reactor be shutdown and the containment be de-inerted.

Alternate Testing These valves will be exercised when'he reactor is shutdown to be Performed and the containment de-inerted. The valves will be man-ually operated and visually verified to open and reseat.

Cold shutdown testing shall commence immediately (within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) following establishment of cold shutdown de-inerted conditions. Testing shall continue only as long as the plant is scheduled to be in cold shutdown with the contain-ment de-intered. Cold shutdown testing will be conducted in a manner which will not impede plant startup. Cold shutdown valves are tested in groups by several different procedures. The decision whether to start cold shutdown testing on any particular procedure will depend on the estimated length of the cold shutdown de-inerted period, system outages/conditions, time interval from the last cold shutdown testing, or other particular conditions. All cold shutdown valves wi 11 be tested during each refueling outage. Testing is not required if the time period since the previous test is less than three months. For extended outages, cold shutdown testing does not need to start within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months as long as all valves are tested before startup.

This alternate testing meets the intent of OM-10 which will be required in the future.

Pg~

II i /

The proposed alternate testing will provide accurate and timely information regarding valve operabi 1 i ty and wi1 provide adequate assurance of material 1

quality and public safety.

SER/TER

Reference:

3.6.2.1 Relief granted as requested.

RELIEF REQUEST NO. /VV ')

P II ~

Revision 4 OELETED SER/TER

Reference:

3.8.1,1 Relief request denied for HY valves.

P j'l

page~M3 Revision 4 RELIEF REQUEST NO. Q~

System Various Valves ASME Ail power operated valves except rapid action valves covered Classification by Relief Request RV-1.

Function System control valves and Containment isolation valves.

Code Testing IWV-3417(a) which requires comparison of measured stroke Requirement time with "the previous test".

Basis for WNP-2 Administrataive Procedures require specific accept-Rel ief ance criteria to be included in Technical Specificaton sur-veillance procedures, of which valve stroke timing proce-dures are a,part. Since recorded times may vary slightly result of plant conditions or test personnel, the re-as a quirement to compare the results with ~ previous value implies that acceptance criteria may have to be changed each time the surveillance is performed. This is admini-stratively unweildly and unnecessary.

Alternate Testing WNP-2 valve stroke acceptance criteria are founded on em-pirically obtained baseline values unless constrained by the FSAR, Technical Specifications or other commitments.

The acceptance range for valves with stroke times no greater than 10 seconds is the baseline time z 50K; for valves with stroke times greater than 10 seconds, the baseline time z 25'/. This approach allows stability of acceptance criteria and ensures that the valves remain wi thin a reasonable range around an established baseline.

WNP-2 Administrative procedures require engineering evaluation if stroke times fall outside the established acceptance ranges.

The proposed method of establishing acceptance criterion is consistant with the intent of the code in that stroke times are evaluated against an estab-lished baseline value. The proposed acceptance criteria method adequately ensures quality of testing and public safety.

NR n / M 7 1 1 SER/TER

Reference:

3 ~ 1.1.2 Relief granted as requested.

TABLE RV-201 Pg~

Revision 4 V lv N r gl gglIUIIIII ~l.~ ~~r CAC-FCV-1A 2 A FDR-V-3 A CAC-FCV-18 2 A FDR-V-4 A CAC-FCV-2A 2 A FPC-V-149 A CAC-FCV-28 2 A FPC-V-153 A CAC-FCV-3A 2 A FPC-V-154 A CAC-FCV-38 2 A FPC-V-156 A CAC-FCV-4A 2 A FPC-V-172 8 CAC-FCV-48 2 A FPC-V-173 8 CAC-FCV-5A 2 8 FPC-V-175 8 CAC-FCV-58 2 8 FPC-V-181A 8 CAC-V-1A 2 8 FPC-V-1818 8 CAC-V-18 2 8 FPC-V-184 8 CAC-V-2 2 A HPCS-V-1 8 CAC-V-2A 2 8 HPCS-V-4 A CAC-V-28 2 ,

8 HPCS-V-10 8 CAC-V-4 2 A HPCS-V-ll A CAC-V-6 2 A HPCS-V-12 A CAC-V-8 2 A HPCS-V-15 A CAC-V-11 2 A HPCS-V-23 A CAC-V-13 2 A HY-V-17A A CAC-V-15 2 A HY-V-178 A CAC-V-17 2 A HY-V-18A A CEP-V-1A 2 A HY-V-188 A CEP-V-18 2 A HY-V-19A A CEP-V-2A 2 A HY-V-198 A CEP-V-28 2 A HY-V-20A A CEP-V-3A 2 A HY-V-208 A CEP-V-38 2 A HY-V-33A A CEP.-V-4A 2 A HY-V-338 CEP-V-48 2 A HY-V-34A CIA-V-20 2 A HY-V-348 CIA-V-30A 2 A HY-V-35A CIA-V-308 2 A HY-V-358 CIA-V-39A 3 B HY-V-36A CIA-V-398 3 HY-V-368 CRD-V-10 2 8 LPCS-FCV-11 CRD-V-11 2 8 LPCS-V-1 CRD-V-180 2 8 LPCS-V-5 CRO-V-181 2 8 LPCS-V-12 CSP-V-1 2 A MS-V-16 CSP-V-2 2 A MS-V-19 CSP-V-3 2 A MS-V-22A CSP-V-4 2 A MS-V-228 CSP-V-5 2 A MS-V-22C CSP-V-6 2 A MS-V-220 CSP-V-9 2 A MS-V-28A EDR-V-19 2 A MS-V-288 EDR-V-20 2 A For information only not part of relief request.

I

'9

~ I I

,4

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Revision 4 TABLE RV-20 (CONTINUED)

~~~Vltt Cl ~l~garz ~~~VI MS-V-28C 1 A RHR-FCV-64A 2 A MS-V-28D 1 A RHR-FCV-648 2 A MS-V-67A 1 A RHR-FCV-64C 2 A MS-V-678 1 A RHR-V-3A 2 8 MS-V-67C 1 A RHR-V-38 2. 8 MS-V-67D 1 A RHR-V-4A 2 A MS-V-146 2 8 I RHR-V-48 2 A MSLC-V-1A 2 8 RHR-V-4C 2 A MSLC-V-18 2 8 RHR-Y-6A 2 8 MSLC-V-1C 2 8 RHR-V-68 2 8 MSLC-V-1D 2 8 RHR-V-8 1 A MSLC-V-2A 1 8 RHR-V-9 1 A MSLC-V-28 1 8 RHR-V-16A 2 A MSLC-V-2C 8 RHR-V-168 2 A MSLC-V-2D 1 8 RHR-V-17A 2 A MSLC-V-3A 1 A RHR-V-178 2 A MSLC-V-38 1 A RHR-V-21 2 A MSLC-V-3C 1 A RHR-V-23 1 A MSLC-V-3D 1 A RHR-V-24A 2 A MSLC-V-4 2 8 RHR-V-248 2 A MSLC-V-5 2 '8 RHR-V-27A 2 A MSLC-V-9 2 8 RHR-V-278 2 A

+t'ai MSLC-V-10 2 8 RHR-V-40 2 8 RCC-V-5 2 A RHR-V-42A 1 A RCC-V-21 2 A RHR-V-428 1 A RCC-V-40 2 A RHR-V-42C 1 A RCC-V-104 2 A RHR-V-47A 2 8 RCC-V-129 3 8 RHR-V-478 2 8 RCC-V-130 3 8 RHR-V-48A 2 8 RCC-V-131 3 8 RHR-8-488 2 8 RCIC-V-1 2 8 RHR-V-49 2 8 RCIC-V-8 1 A RHR-V-53A 1 A RCIC-V-10 2 8 RHR-V-538 1 A RCIC-V-13 1 A RHR-V-68A 3 8 RCI C-V-1 9 2 A RHR-V-688 3 8 RCIC-V-22 2 8 RHR-V-73A 2 A RCI C-V-31 2 A RHR-V-738 2 A RCI C-V-45 2 8 RHR-V-115 2 8 RCIC-V-46 2 8 RHR-V-116 2 8 RCI C-V-59 2 8 RHR-V-123A A RCIC-V-63 1 A RHR-V-1238 1 A RCIC-V-68 2 A RHR-V-134A 2 A RCIC-V-69 . 2 A RHR-V-1348 2 A RCIC-V-76 1 A RRC-V-16A 2 A RCIC-V-110 2 8 RRC-V-168 2 A RCIC-V-11 3 2 8 RWCU-V-1 1 A RFW-V-65A 1 A RWCU-V-4 1 A RFW-V-658 1 A . RWCU-V-40 1 A

'1 t

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R TABLE RV-20 (CONTINUED)

V v SLC-V-1A 2 8 SLC-V-18 2 8 SW-V-2A 3 8 SH-V-ZB 3 8 SH-V-4A 3 8 SH-V-48 3 8 SW-V-4C 3 8 SH-V-12A 3 8 SH-V-128 3 8' SH-V-24A 3 SH-V-248 3 8 SH-V-24C 3 8 SH-V-29 3 8 SH-V-44 3 8 SH-V-54 3 8 SH-V-75A 3 8 SH-V-758 3 8 SH-V-187A 3 8 SH-V-1878 3 8 SH-V-188A 3 8 SH-V-1888 3 8

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Revision 4 RELTEF REQUEST NO. ~V- 1 DELETED Design changes deleted valves SW-V-214, 215, 216, and 217,

f I

9'~

Revision 4 RELIEF REQUEST NO. ~V- P.

System Emergency Chilled Water Valves SW-TCV-11A, 118, 15A, 158 ASME Classification Code Class 3, Category B Function These are the temperature control valves for cooling water flow to the chiller heat exchangers, Code Testing IWV-3413, measure the stroke time of power operated Requirement valves.

Basis for These are hydraulically operated globe valves used Relief for control of chillwater temperature. They do not have 'a manual control switch or any remote position indicators.

Alternate Valve exercising per INV-3412 will provide adequate Testing to be assurance of valve operability. Verification of Performed valve position is based on observing the appropriate system response or locally observing stem position.

1 /

Valve operability is adequately demonstrated by the tests associated with INV-3410 with the exception of IWV-3413 noted above. This testing provides ade-quate assurance of material quality and public safety.

A n / D SER/TER

Reference:

3.1.3.1.1 Interim relief granted until May 13, 1992 or next refueling outage (R7) whichever is longer.

During this interim period, NNP-2 should evaluate alternatives and identify a method for adequately assessing the operational readiness of these valves.

Ilvv Pg~

Revision 4 RELIEF REQUEST NO. ]LVV System Post Accident Sampling Valves PSR-V-X73-1 PSR-V-X80-1 PSR-V-X83-1

PSR-V-X77A1 PSR-V-X82-1 PSR-V-X84-1

PSR-V-X77A3 PSR-V-X82-7 PSR-V-X88-1 ASME Classification Code Class: 2 Category: A

Code Class: 1 Function Closed Position - Containment Isolation Code Testing Requirement INV-3413, Power Operated Valves (stroke times)

Basis for These nine PSR solenoid valves are the inboard Relief Containment Isolation Valve for nine different pene-trations and are operated from a single keylock con-trol switch. It is impractical to measure the indi-vidual valve stroke times. To do so would require repetitive cycling of the control switch causing

~

unnecessary wear on the valves and control switch with little compensating benefit.

Alternate The stroke time of the slowest valve will be measured Testing to by terminating the stroke time measurement when the be Performed last of the nine indicating lights becomes illumin-ated. If the stroke time of the slowest valve is in the acceptance range, then the stroke times of all valves will be considered acceptable.

The proposed alternate testing will verify that the valves respond in a timely manner and provide information for monitoring signs of material degradation.

This provides adequate assurance of material quality and public safety.

A / M 1 1 SER/TER

Reference:

3.1.4.1.1 Relief granted as requested.

E RELIEF REQUEST NO. f~V-9~

Revision 4 System Containment Instrument Air Valves CIA-SPV-1A through 15A CIA-SPV-1B through 198 ASME Classification Code Class: 3 Category: B Function Emergency Nitrogen Bottle Isolation Valve Code Testing Requirement IWV-3413, Power Operated Valves <stroke times)

Basis for These valves have neither a manual control switch Relief nor suitable valve position, indicators. The proposed alternate testing will confirm valve operability and detect any defective valves.

Alternate The valves will be tested per IWV-3410 with the Testing to exception of IWV-3413. Verification that the valve be Performed opens and closes is based on observation of appropriate system responses.

li /

Valve operabi 1 i ty i s adequately evaluated by the tests associated wi th IWV-3410 with the exception of IWV-3413 noted above. This testing provides adequate assurance of material quality and public safety.

SER/TER

Reference:

3.9.2.1 Interim relief granted unti 1 Hay 13, 1 992 or the next refueling outage (R7) whichever is longer.

During this interim period, HNP-2 should e'valuate alternatives and identify a method for adequately assessing the operational readiness of these valves.

I

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Revision RELIEF REQUEST NO. RVV,'j System Al 1 Valves All valves tested at cold shutdown.

ASME Classification Various Function Various See Note 1 to valve test tables.

Code Testing IHV-3412 Exercise valves during cold shutdowns, Requirement IHV-3522 if valve is not full stroke exercised each 3 months during plant operation.

Basis for It is a hardship to test all cold shutdown valves at Relief each cold shutdown. Additionally, requiring all cold shutdown testing each outage would mean a significant delay in plant startup for cold shutdowns of short duration.

The industry has recognizd that cold shutdown test-ing, as specified in 1980H80 of Section XI, is excessive. The 1989 edition of Section XI references ASME/ANSI OM, Part 10 for valve testing. Part 10 does not require all cold shutdown valves to be tested each cold shutdown.

. The NRC has also recognized that testing all cold shutdown valves at each cold shutdown is a signifi-cant burden. Many SERs contain an appendix which states (similar to OM-10) that cold shutdown testing needs to continue only until the plant is ready to start up.

Alternate Cold shutdown testing shall commence immediately Testing to (within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) following establishment of cold be Performed shutdown conditions. Testing shall continue only as long as the plant is scheduled to be in cold shutdown. Cold shutdown testing will be conducted in a manner which will not impede plant startup. Cold shutdown valves are tested in groups by several different procedures. The decision whether to start cold shutdown testing on any particular procedure will depend on the estimated length of the cold

Relief Request No. ~i (Continued)

II ~

Revision 4 shutdown period; system outages/conditions; time interval from the last cold shutdown testing; or other particular conditions. All cold shutdown valves will be tested during each refueling outage.

Testing is not required if the time period since the previous test is less than three months. For extended outages, cold shutdown testing does not need to start within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months as long as all valves are tested before startup.

The alternate testing is in accordance with OM-10 which wi 11 be required in the future.

li /

The effect of granting this relief wi 11 have no adverse impact on plant safety. The alternate testing as described herein is currently being followed at NNP-2. The Industry and NRC have, by the actions previously described, considered this method of cold shutdown testing appropriate.

e / M 7 SER/TER

Reference:

3.1.7;1 Relief granted only for valves that can be tested during any cold shutdown.

Pa~

Revision 4 RELIEF REQUEST NO. I'LL~

System Standby Liquid Control (SLC)

Valves SLC-V-33A, 338 ASHE Code Class 2 Category: C Classification Function SLC-P-1A and 1B discharge check valves Code Testing 1. Quarterly exercising (INV-3521)

Requirement

2. Cold shutdown exercising (INV-3522)

Basis for There are no test connections to allow back flow testing Relief of these check valves. The only way to determine if the check valves are closed would be to remove the relief valve on the pump associated with the check valve to be back flow tested and either running the other SLC pump or pressurizing the discharge piping with the head of the SLC test tank, Removing the relief valves is a time consuming job and it can only be performed with the SLC system inoperable. Back flow testing of these valves should be performed when the. relief valves are re'moved for testing during refueling outages.

The postulated failure mode is that a relief valve on an idle pump sticks open and the check valve does not isolate the running pump thus causing failure of both trains because of a common discharge line. The relief valves on each pump are tested when the pump is run for its quarterly test. Therefore, assurance that the system will perform as designed is verified quarterly.

Alternate Testing During each refueling outage verify closure of these to be Performed valves by back flow testing.

1 /

The SLC System will be required to perform its safety function only under very infrequent circumstances (ATNS). The proposed testing provides adequate assurances of quality and public safety.

Pending

F

'I I

RELIEF REQUEST NO. fQf~

P II ~

Revision 4 System RCIC, HPCS, LPCS and RHR RCIC-V-65, 66 1 A-C RCIC discharge to the reactor vessel head LPCS-Y-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 A-C RHR Loop A, 8 discharge to the recircu-lating pump discharge Code Testing 1. Quarterly exercising (INV-3521)

Requirement 2; Cold shutdown exercising (INV-3522)

Basis for These valves (except RCIC-V-65) function as Reactor Relief Coolant System Pressure Isolation valves. This requires the check valve disc to properly seat and achieve a relatively leak-tight seal. Technical Specification requires seat leakage testing of these valves each refueling outage (not to exceed 18 months). Seat leakage must be less than 1 gpm at a differential pressure of 950 psig. Seat leakage as a method of showing valve closure testing is labor and dose intensive and as such impractical to perform during each cold shutdown and should be tested during refueling outages only.

2. In two instances a valve was found to be not fully closed due to binding in the position indication linkage. These valves were designed with an open/closed position indication system, but have proven unreliable and are scheduled for removal of position indication system to increase the reliability of these valves SOER 86-03 issue.

(Position indication mechanisms have been removed from RHR-V-41A and B.) The position indication mechanism in the closed position does not indicate closure of disc, but closed indication merely reflects that the disc is not full open.

3. Other than the above two instances, these check valves have exhibited excellent leak-tight integrity during the last eight years since commercial operation.

l E

'I g J

Relief Request No. 9V ~ (Continued)

Pg~

Revision 4 4, Due to lack of re'liable position indications, the other positive means of verifying these valves fully open is by passing the required accident condition flow through these valves. This is an acceptable full-stroke per.position of Attachment of Generic 1 1 Letter 89-04.

5. Hith flow rates on the order of 7500 gpm (ECCS),

vessel level rises at a rate of 38 inches per minute Operating ranges for RPV level provides a narrow band in which to work, making any such injection an challenge to plant technical specifi-cation limits and can result in flooding of main steam lines. Full flow testing of these valves should be performed only during refueling outages, when such testing can occur during refueling cavity flood-up.

6. Because of the differences in water chemistry, frequent injections of Suppression Pool water into the RPV is undesirable and will lead to additional crud accumulations in the crevices of piping nozzles, etc., and thus result in higher dose rates in the containment.

7. Six of the nine valves have been inspected internally and have exhibited no signs of wear which could affect the ability of the valves to stroke full open or closed. These check valves do not exhibit any signs of back-seat tapping or hinge pin wear, nor have they shown any indication that internal fastener retention methods are inadequate.

8. During normal plant operation, these valves are

. normally closed and do not open.

Alternate Testing During each refueling outage (not to exceed 18 months) to be Performed

l. Closure ability of these valves (except RCIC-V-65 which does not have a closed safety function) shall be demonstrated by leakage test as required by Technical Specifications.

z. Opening ability of these valves shall be demonstrated by passing the maximum required accident condi'tion flow through these valves.

Relief Request No. 3V~ (Continued)

P g~

Revision 4 Im 1 n in All these valves were verified full open and closed during R-6 Refueling outage (1991) and shall be tested again during R-7 Refueling outage (1992).

This relief request supersedes the testing requirements specified in Relief Request RV-9.

1 f These valves are normally closed and while in the closed position function as

1) containment isolation valves and 2) high-low pressure interface valves between the reactor coolant and portions of the Emergency Core Cooling System. These valves must open to facilitate operation of part of the Emergency Core Cooling System. The valves will normally only be operated in the event of an emergency during normal power operations. Lengthening the interval between tests as recommended will not preclude the timely evaluation of valve operability and thus provides adequate assurance of material quality and public safety.

Pending

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R f I rv Records and reports pertaining to Valve Inservice Testing will be maintained according to Article INV-6000 of the Code.

i 1

P 4

0TA T Pa~

ReVI S jOn 4 VALVE STROKE DATA SKEET Stopwatch Ident iNO Calibration Due Date OPENING TME IN SECONDS CLOSING TME IN SECONDS VALVEID VALUE ALERT LO ALERT HI ACTION HI (+ 1)

~TLO MEASURE VALUE ALERT HI ACTION HI (+ I)

(+ 1) (+ 1) (+ I) (+ 1)

LPCS-V-I V".14 91.60 152.67 183.21 120.50 9037 150.62 180.75 LPCS-FCV- 17.09 12.82 2136 U>.64 16.62 12A 20.78 24.93, ll

( " LPCS-V-12 11.74'A NA 936, 4.68 LPCS-V-3 NA NA NA NOT iNA NA NA OPEN LPCS-V-33 NA NA NOT NA NA iNA iNOT OPEN CLOSED LPCS-V-34 NA NOT NA NA NA NOT OPEN CLOSED

(+1) For measured values beyond the Alert Value or Action Value refer to Precaution and Limitations 4.6 or 4.7, respectively.

(+2) A limiting stroke time is specified in the references.

Attachment 9.1 PROCEDURE UMBEL REVISION PAGE 7.4.5.1.7 '34 of 18

TWO YIIAR VP) VI.~111 ~ I(.ATIANDATA csl-lI..IST VfRl'IED OPLtH VL'RIPIED CI.OSL'D VALVE % PULL LOCAL IHDICATIOH REMOTE REMOI E LOCAL INDICATION COHDITIOH OPEN INDICATION LOCATION IN DICATIOH VALVE VALVE INSPECTED OF Vr I OPERATION (+2)

NUMBER INITIALS AS FULL SAT UHSAT SAT UNSAT IHITIALS (+I) AS ruLL raaua asau FOUND CI.OSr:

STEP I STCP 2 STEP 3 STEP 5 STEI' STEP 4 STEP 4 STEP 4 STCP 2 STEP 3 STEP 5 STEP 6 STEP 8 STEP 7 LPCS-V-I I I )3/P60 I LPCS-FC V-I I I I I3/PGO I LPCS-V-12 I I I3/P60)

(+3)

(+ I) Ifthc valva In it~ Aa Found condition ls not fully <<loscd, aubnut an httVR (fur changing limit switch scuings and obtaining stroke time mc ~ surcnscnts). For thrunlc valves, verify that tha valve casusat bc lbnhcr rsloscd front ha cosurul switch.

(+2) Iftha valvo I ~ less thao 904 Full Open as calculstcJ below, writs ~ I'QR and mask I'OC Insmcdiata Disposttion Yca. Calculate % Fsili Opcnln acconlanccwids obtained values ~ rut the fallowing cxamplcst 5 PULL OPliN ~ I(Aa Pound Open) - (Pull Closed)I/(gall Opsn) - (Pull Close J)) x l00

~ nsi to i.steato 5 5 at Full Ctuscd ~xse ~ALsSS 0 at Full Close J 9$ Ã at Full Opcu 6.0 st Full Open 90'I As Fuood Open 5.$ Aa Found Open X FUI.L OPQN (90 5)/(95.5) x l00 ~ 9d.c 4 X I'UI.LOPQtt ($ .$ -0)/(6.0-0) x III ~ 9I.7X iloh7~l1 ~AISttkiiSv~il II a 0 at I'ull Close J ittst~n~ns ~nt ~ I so JS't Pull Closad I 2 5 at Irull Otscsl 27$ at Full Open I l.5 Aa Iruuud t)pcu 23S'a FounJ Open A I UI.L Of'QN <<(I I.S.O)/(I'2.$ .0) x l00 ~ 9'2.04 St FULL OPQN (23$ .65)/(27$ .45fx l00 ~ 82.6 A (I3) I pCS.V I'2 4 cunsldcrcd Full Open lflt passes at least 63S0 Gl'ht when it is fully opcnc J clccnically. LPCS.V l2 ~ tsould in ticstc apprualnutcly 20 9'ncslly when fully open clcctricalty.

~

LI'CSV l2 4 sluottlcJ at 20% tu prcvcnt caccssivc vibration dosing srsoka timing. Is i ~ ssot ucccssary'to manually open I IIV.I2 tu 100 4 whcu chcckiug twu year Vl'I fur vcsiticd <span psutiou of Qsi ~ anacluo su, AIIIICIIIIICIII9.5

Pg~l R

5.0 Quality Assurance Program The NNP-2 Pump and Valve Inservice Test Program activities will be con-ducted in accordance with Topical Report HPPSS-QA-004, the Supply System's Operational Quality Assurance Program description.

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R R

6.0 Piping and Instrument Diagrams The Piping and Instrument Diagrams used to generate this Program are listed below. 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.

'~

PT Control & Emergency Chilled r i Diesel Oil & Pri. Containment RIL RRII Demineralized Post Accident r lin Reactor Core li High/Low Pressure r

Residual Heat v M 1 Standby Liq.

r 1 Reactor Water Standby Service W r Reactor Closed lin Fuel Pool 6~1 Control Rod Dr v Main Steam and r w Reactor Recirc.

1 Equip. Drain R i iv H Floor Drain R i iv M Containment lin P r M 4 Containment A m . n 1 H 4 Containment In tr . Air Ma in S team Le n Neutron ni rin M 4

ML17286B179

Text

1.0 INTRODUCTION

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