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| issue date = 11/21/1991
| issue date = 11/21/1991
| title = Rev 4 to Pump & Valve Inservice Test Program Plan,WPPSS-2.
| title = Rev 4 to Pump & Valve Inservice Test Program Plan,WPPSS-2.
| author name = BAKER J W, RANA R
| author name = Baker J, Rana R
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter: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 Reviewed by c7=IST Program Engineer RRa~Reviewing Engineer Date II-l3-'>i Date Concurrence Concurrence Manager, Plant Technic 1 Manager, Plant Operations
{{#Wiki_filter:HASHINGTON PUBLIC PONER SUPPLY SYSTEM NUCLEAR PLANT NO, 2,
//i5'Date I l I'Ecl(cl (Date Concurrence Approved by Manager, Plant QA Plan anager, HNP-2 l(zo el Date i le(Date Concurrence Authorized Nuclear Inservice Inspector Date n V&
,<<                         PUMP AND VALVE INSERVICE TEST PROGRAM PLAN PZ12100281 5'11203 PDR ADOCK 05000397 P               PDR
RECORD OF PROGRAM'LAN REVISIONS 3b 3a 0 Ho.ll/12/91 10/5/87 12/20/65 6/10/85 11/3/83 8/28/82 4/23/81 i)ATE REVISION REVISION P,EVISIOfl REVISION REVISION REVISION ORIGINAL REV IS IONS 711+Aar CriK'0 APP'0
~in r Records of~v Li st of Effective Pages iv vi Table of Pump Test Program n r i Program Im-plementation 3.2-1 NA Deleted (Relief-1)Rel i ef Request RP-7 3.6-10 3.6.11 Pump Test w CCH-P-1A Fl wP h CCH-P-18 Fl DO-P-1A,18,2 Fl w h FPC-P-1A,18 1 w P h HPCS-P-1 F w HPCS-P-2 1 w h VI 4 Program Ad-Pump Refer-ence List Pump Test Tables Pump Relief 3.4-1 3.5-1 3.5-2 3.5-3 LPCS-P-1 1 w RCIC-P-1 1 wP h ,RHR-P-2A 1 w RHR-P-28 Fl wP h RHR-P-ZC w P SLC-P-1A,18 F w SH-P-1A Fl wP h SN-P-18 F w P Relief Request RP-1 3.6-2 Rel ief R Relief~R De 1 eted (Re 1 i ef~Re P-4 Relief Req Relief Records of T Sample Pump Data Sheets 3.8-2 3.8-3 Valve Test Program Inr u i n 4.1-1 Program Im-plementation 4.2-1


Program Ad-mi 1 in Valve Test T 1 Valve Test Tables Key Valve Test Tables 4.4-1 4.4-2 4.4-3 4.4-4 4.4-5 4.4-7 4.4-8 4.4 9 4.4-10 4.4-11 4.4-12 4.4-13 4.4-14 4.4-15 4.4-16 4.4-17 4.4-18 4.4-19 4.4-20 4.4-21 4.4-22 4.4-23 4.4-24 4.4-25 Valve Test Table Notes 4.4-26 4.4-27 4.4-28 4.4-29 4.4-30 4.4-31 4.4-32 4.4-33 4.4-34 4.4-35 4.4-36 4.4-37 4.4-38 4.4-39 4,4-4 4.4-41 4.4-42 4.4-43 4.4-44 4.4-45 4.4-46 4 4-47 Valve Relief~R 4.Relief Request RV-1 4.5-2 4.5-3 4 V N 4 4 TITL T TL H ET R VI I N Relief e V-4.-Rel i ef~Request RV-3 4.5-6 4-7 Re 1 i ef'equest RV-4 4.5-8 4.5-9 4.5-10 4.5-11 4.5-12 4-1'Deleted<Relief 4 4 Re 1 i ef 4 Relief Re-quest RV-18 4.5-30 Deleted (Relief RV-1 4.Relief Re-quest RV-20 4.5-33 4.5-34 4.5-35 Deleted<Relief V-1 4.Relief Re-V-Relief Re-V-Relief Re-V-4 4,-4 Re 1 i ef R Re 1 i ef V-4.-1 Relief Re-quest RV-25 4.5-41 4, Re 1 i ef Re-quest RV-15 4.5-25 4.5-26 4.Deleted (Relief R RV-1 4.Relief Re-RV-17 4.Rel ief Request RV-9 4.5-18 4, Deleted (Re'lief V-4.Relief Re--11 4.Deleted (Rel i ef V-1 Relief Re--1 4.Relief Re-V-14 c 4 Relief Re-V-4.-4 Relief Re-quest RV-27 4.5-44 4.5-45 Record of 4 Samp1 e Va1 ve Data Sheet 4.6-2 Quali ty Assurance Piping E Inst.i r m
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


TITLE SHEET REVISION TITLE SHEET REVISION 5.0 equality Assurance Pro ram ow Dia rams 6-1 oor rain Radioactive M539*Containment Coolin 8 Pur e M543*ontainment Atmos.Control M554*ontainment Instru.Air M556*52 50 38 34 ontro Service Air M510*lese 1 Misc.S stems M512*Dem nera i ze Water M517*eactor ore Iso.Coolin M519*ig ow ressure Core S ray M520*esi ua ea Removal M521*tan y iq.Control M522*eac or ater Cleanu M523*tan y ervice Water M524*Reactor ose Coolin M525*38 57 44 50/51 20 59 52/51 42 ain Steam Leaka e Cont.M557*eutron Monitoring (Not a Flow Dia ram)M604*Steam an Li uid Sam.M607*mergency i e Water M775*ri.ontainment Nitro en Inertin M783*ost Acci ent Sam lin M896*18 13 17/16/10 ue oo Coolin M526*54 ontro o Drive M528*Main Steam an Reactor Feedwater eactor Recirc.Coolin Equip.Drain Radioactive M529*M530*M537*47*Burns 8 Roe Flow Dia ram Number vii a~Revision 4
n V


==1.0 INTRODUCTION==
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


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.
VI Deleted (Relief
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.
                                                      -1)
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)).
Rel i ef
This Program Plan is comprised of two subprograms
~in r                                    Request RP-7      3.6-10 Records of
-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).
~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
P9~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
~RRelief                                Valve Test
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.
~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
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


P II~Revi sion 4 3.2 Pr Surveillance testing is performed to detect equipment malfunction or de-gradation and to initiate corrective action.Since the safety related pumps are normally in a standby mode, periodic testing of this equipment is especially important.
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.
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.
4.4-23    Request RV-1 4.5-2 4.4-24                4.5-3 4.4-25                      4
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.
TITL                                        T TL                H  ET    R VI I N Relief                                      Relief    Re-e            V-  4.-            quest RV-18          4.5-30 Rel i ef
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.  
~
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).
 
P9~
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).
 
P9~
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.


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 f r 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 orfrom 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.
9~Revision 4 RHR-P-2A, 2B, 2C The Residual Heat Removal pumps are high capacity, low head pumps, which have multiple uses during normal and emergency plant conditions.
Briefly the system: a)In conjunction with other systems, restores and maintains reactor coolant inventory in the event of a LOCA b)Removes decay heat after shutdown c)d)Cools the suppression pool 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).
P9~Revision 4~c~ni Q A N/A NR Quarterly (92 day interval)test Annual test Not applicable.
See Relief Requests Not required IHP-4400 does not require pump speed measurement if pump is directly coupled to a constant speed motor driver.
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IWP Parameter Pump Ident.ASHE Code Class Inlet Pressure, Pi Oischarge Pressure, Po-Oifferential Pressure, P Flowrate, Lubrication Vibration, Pump Level/Speed, Pressure V N Relief Request(s)
IWP Parameter Lubrication Pump     ASHE Code Inlet     Oischarge Oifferential     Flowrate, Vibration,   Pump   Level/     Relief Ident. Class    Pressure, Pressure, Pressure,                              Speed, Pressure   Request(s)
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 9~Revision 4 3.6 if R u Frm r NP ir Relief Requests identify Code requirements which are impractical*for NNP-2 and provide technical justification for the requested exception.
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.
Nhere appropriate, they also propose alternate testing to be performed in lieu of the Code requirements.
n~Revision 4 RELIEF REQUEST RP-1~Pm (s)CCH-P-1A, 18 OO-P-iA, 18, 2 FPC-P-lA, 18 Section XI Code Requirement frwi h li f i HPCS-P-1, 2 LPCS-P-1 RCIC-P-1 RHR-P-2A, 28, 2C SLC-P-1A, 18 SH-P-lA, 18 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.
RELIEF REQUEST RP-1 n~
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.
Revision      4
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.
~Pm   (s)
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.
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)
N'I V'I t~I I!I 4 I'  
~B
'll'~Revision 4 RP-1 (Continued) r in Pr 2.3.4, 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.Vibration testing will be conducted in accordance with all the vibration measurement requirements of ASME/ANSI OMa-1988, Part 6.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.
: 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.
An exception is for DO-P-1A, 18, 2 and FPC-P-lA, 1B.See Item 4 following.
: 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.
The upper limit for vibration velocity for the following pumps shall not exceed: ALERT REQUIRED ACTION FPC-1A;1B 00-P-1A;1B, 2 11"/m.55 in/sec 1.4 in/sec.7 in/sec 1.6 in/sec NR A 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.
: 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.
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 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.
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.n/d M 7 1 1 SER/TER  
N'I V
'I t ~
I I!
I 4
I'
 
RP-1    (Continued)
                                                                            'll'~
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:==
==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.


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
P L'1  
  '1
'll~Revision 4 RELIEF REQUEST RP-2~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.
RELIEF REQUEST RP-2
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/0 M 7 1 1 SER/TER  
                                                                      'll ~
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:==
==Reference:==
2.2.1 This  relief  was  granted as requested.


2.2.1 This relief was granted as requested.
RELIEF REQUEST RP-3 Pg~
N A 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.
Revision     4
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)
~(s)
~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.
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)
(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.
~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.
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  
(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:==
==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.


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-4 DELETED PRIOR TO'ER REVI f H'
 
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.


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.
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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.
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.
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.
I   I f
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.
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.
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  
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:==
==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
  ~ ~
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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FLX  2A+4    +3                                      3 3                                    P-IA V-1060 2  I/2 V-3A                            V"226A                                  V-107D REFERENCES(
EMERGENCY CHILLED IIAI'ER    PIPING ORRDMG M775
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V-7828        V-782A V-8238              FE-358 3
TCV-118 2
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V-8228                  2 I/2 3
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FE-148                      V-478 6                                      20          18 REACTOR VESSEL RO-38              V-38 V-278 V-1728      V-248                          RHR-HX-IB SUPPRESSION                                            IB      20 POOI.
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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.
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g~Revision Relief request denied.SER/TER 2.1.1.1 RELIEF REQUEST RG-1 7 1 Pg~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 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.
                                      'e.12 PCV-388            V-'128                      18 20 FE-I 8                                                    V-1708 IIPCS-P-2       SM-P-I A 18 DCM                                                  PUHP                      SPRAY IIX-182                                              HOUSE A                    POND A DCM IIX-181 V-38 REFERENCES<
i p 1 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.
8  R R DMG SERVICE MATER                                            HS24 Stt 2
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.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.


P II~Revision 4 RP-7 (Continued)
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:
All pumps are tested at essentially full design flow rate.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.
: 1)     Pump  identification  by equipment piece number, manufacturer,      and serial  number.
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~~
: 2)    Inservice test plans. This may be by  reference to the surveillance test procedure  by which the pump is tested.
RP-7(continued)
: 3)    Summaries  of corrective action.
SW-P-5 ACCEPTANCE CRITERIA P,~6-12 Revision 4 230 225 220 215 210~~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
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.


Pg~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.
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)
V-78 I 8 V-78 I A/3/3 r V-823A~FE-35A TCV-I IA V-1 040 CC-EV-IA PI IA V-710A CCH Pl 34 v-70<A r'-227A V-225A 3 0I-Fx-IA RD-1 A J 3/3 V-IOSD 2 I/2 3 V X-IA P-IA FLX 2A+4+3 V-822A V-1060 2 I/2 3 2 I/2 V-3A V"226A V-107D REFERENCES(ORRDMG M775 EMERGENCY CHILLED IIAI'ER PIPING
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)
*0 0 V-7828 V-782A 2 I/2 g 2 I/2 3 r'V-8238 FE-358 TCV-118 V-IONIC CC-EV-18 Pl 18 V-7108 Pl Cell V-70~8 V-2278 tjI~AD"18 V-2258 FX-18/3/3 V-105C 2 I/2+3 Y-28 FI.X P-18 Inn'LX-28+~
DiPcicntial prcssure dp            PSID        31$          (+2)        (+3)                      (+3)        (4 2)
V-8228 V-106C 2 I/2 3 V-38 CCII SM 3i V-2268 V-107C 2 I/2 REFERENCES'RADNG ll775 EMERGENCY CIIII.I.ED MATER PIPING al ea V-43 V-12/I I/2 V-11 V-10 I/2 00-P-2 00-TK-3C~1 I/2 2 I I I I 00-TK-2 ll PT v-/OIB C3 a I 9 I 00-TK-38 V-48 I I/2~V-5 V-28 V-18 I/2 2 I I I I 00-TK-18 s i L J PT V-/OI A 00-P-IB Ul Il I O 0 O O I 0 I CO C3 C)I 0 I PJ V-4A+I I/2 V-2A V-I A 1/2 00-P-I A XI 0 o a CQ REFERENCES' II R OHGS II512 Stl I tl512 5tl 4 00-TK-3A DIE5EL FUEL OIL 2 I I 00>>TK-IA II LJ (A 0 4l I
(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.
Attachment 9.2 rhea 7.4.5.1.7                                                                    15  of 18


8~V-145A~8 V-1458 (-10 FPC-TK-IA FPC-TK-1S V-.l RSA Y-1468 FE-16 V-130 V" 181A 5T-I A Y-706A (-10 FPC-P-IA Pl~8 I FFUSERS~6 Y-112A Y-116A FPC-IIX-I A Pl V-709A A V-I 18h 6~8 g FUEL PIT (-8 V-175-R0-6 V-142 (-8 V" I 4?Y-140 uI 0 X 0 O I 0 I 0 n I 0 I CD Y" 1818 El FPC P 18 6 g V-1128 Y-1168 Y-124 Y-184 V-7068 Pl V-7098 Pl FPC-IIX-18 V"'I?2 V-158K Xl 0 0 CQ fD REFEREIICES
AHP      0 T
~8 R R OHG M526 Y-1188 6~FUEL POOL COOLIBG V"173 N IH V-68 REACTOR VESSEL 20 V-I 14 CST 10 V-11 V-IO 0 O U)I 0 I SUPPRESSIOH POOL LPCS HPCS V-2 I V-701 PT 24 V-710 FT 5 FE-7 V-709 0 0 UI I O 0 REFERERCES S E R OIIG H520 12 IIPCS-P-I HIGH PRESSURE CORE SPRAY V-24 Zl 00 (0 fD N O
                                                                                                  >'ll'~
Revision R  P    -P-
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IRD MODEL SZO      Q~r)    1D iNQ.                            CAL DUE DAT-CAL DUE DATE IRD MODEL 970 (PROBE) iD NO.
Bearin  4 Probe                    Vibrsaca Velociry (ia/sec)
Locaaoa Reier        Measured          Alert EK    Acdoa HI Value          Vshe              (+ l)        (+ l)
N4          0.130                                          0.700      D.(L11)
E-W        0.150                                          0.700      Q.<~ l.)
: 0. 100                                        0.600
(+ l) For  measured values beyoad tho Alert Value or Acaoa Value reier co    ~aoa        sad L'miuaoas 4.6 or 4.7, resp ecavely.
Attachment 9.3 FROCK) URE WOMBEk                                                              . PAGS 7.4.5.1.7                                                                       46 Of 18


3 2 I/2 (TYP)2 8 V-89 8 V-80 PT V"701 V-29 HPCS-V-28 0/G COOLERS FE-BA n~O~0 m~-FE-88 FLX"3 D/G T FLX-0 V-709 HPCS-P-2 6 8 0 A u)1~0 1 bJ 0 0 V-88 2 V-87 8 PUHP HOUSE A SPRAY PONO A 2 REFERENCES'
l>> D
'OMG H524 Sll 1 V-0C HPCS SERVICE MATER A
                        )
REACTOR VESSEL A0-4 12 V-12 V-60 V-I SUPPRESSION I 0 A LI)I 0 I Pl V-709 2 FE-2 16 Pl V-7OI 24 51'-I POOL LPCS HPCS 0 0 Pfl U)TI'V-3 14 LPCS-P-I REFERENCES<
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BRAOIN 8520 LOM PAESSUAE COAE SPRAY
            *  ~ I 1
!k C y 1~I t r-~L f-a 1 CST V-59 V-23 V-22 PT V-728 V-191 A0-6 (-6 RO-12 (-6 6 W V-101 FE-I V-12 REACTOR VESSEL Sr-I SUPPRESSION POOL ACIC-P-I Pr V-701 V-16 CST V-10 8 g V-11 REACTOR CORE ISOLATION COOL ING REFERENCES<
        ~ 'H A
8 II R OIIG f619 XI 0 e a ((D
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~\I, t AI 18 V-47A 20 V-3A FE-I dh 18-RO-3A 6 V-27A REACTOR VESSEL RIIR-IIX-I A V-24A V-172A 20 18 V-6A V-Rh SUPPRESSION POOL 18 24 V-705A Pl V-701A 2A 18 V-IIOA V-31A RO-SA 24 RI8-P-2A ST-2A RESIDUAL tIEAT REIIOVAL REFEREtlCESs 8&R OMG t1521 SII I
II


REACTOR VESSEL 6 IB I FE-148 20 V-478 18 V-278 RO-38-V-38 V-1728 V-248 RHR-HX-IB SUPPRESSION POOI.V-68 IB 20 24 18 PI 28 V-7018 V-7058 REFEREHCESs 8 C R OMG H521 SH 2 RESIDUAL HEAT REHOVAL g ST-28 24 14 I RO-58 RIN-P-28 IB V-318 V-1108 18 REACTOR VESSEL FE-14C RO-4 V-2'I V-174 Y-4C 24-VENT STRAINER SUPPRESSION POOL V-705C Pl 2C V-701 C 18 V-110C V-31C'4 RO-5C ST-2C 24 XI D e a (0 Q Q 0 REFEREttCESs 8 R R DIIG t621 Stt 2 RtS"P"2C RESIDUAL ttEAT REIIOVAL
P Revision AMPL DATA HEE7 I   '
LPCS-P-1 ACCEPTANCE CRITERIA 3m I
A Ef X0 290 270
              . 630 638l M83        64CO    6420 644l 64K 64M 6500      6520    6540  6560 FLOWRATE  - GPM ALERT RANGE - Area Outside I-2-3-4                  ACTtON RANGE  - Area Outside 5-6-7-8 Attachment 9.4 .
2RGCKURE WMEZ                        REVTSiON 1.4,5.1.7                                                          17  oi 18


DEIIIN kATER SUPPLY V-9 V-17 SLC-Tk-2 REACTOR VESSEL Pl V-701 V-4A V-16 I I/2 I I/2 V-3A V-33A V-31 SLC-P-IA 3 SUPPRESSION POOL 1 I/2 3 V-2A V-48 V-38 V-338 I/2 SLC-P-18 REFERENCESI BCRDMG HS22 STANDBY LIOUID CONTROL 3 V-28 0 I 4) 16 20 20.18 V-2A 2A V-IA 20 RIIR-HX-I A RHR-V-68A RHR-V<<IAA FE-6A y 706A PI HPCS-P-2 SM-P-I A 20 18 20~PUHP HOUSE A SPRAY POND A 12 PUHP HOUSE MALL DCM HX-I A2 DCM HX-IA I 20 20 FE-IA PCV-38A V-12A SM-P-I B SM-P-I B 20 V-170A REFERENCES'&RDMG H524 SH I RO-2A SERVICE MATER PUHP HOUSE B SPRAY POND B 4 I I I~.1'gg j t f, 0 l V-28 V-18 SM-P-18 20 Rt(R-tlX-18 i8 RIN-V-148 V-7068 Pt PUttP HOUSE 8 SPRA Y POND 8 20.12'e PCV-388 V-'128 PUIIP tlOUSE MALL 18 FE-I 8 IIPCS-P-2 SM-P-I A V-1708 18 DCM IIX-182 DCM IIX-181 V-38 SERVICE MATER PUHP HOUSE A SPRAY POND A REFERENCES<
P V
8 R R DMG HS24 Stt 2 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:
I j    'll                  4
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.
~ II 14 I
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AMP 0 TA H T P Revision 4 PUMP OPERABILITY DATA SHEET FOR LPCS-P-1 Test Parameters Driver Lubrication Suction Pressure before pump start per LPCS-Pf-1 Pump Lubrication Suction Pressure at test flow per LPCS-Pf-1 Discharge Prcssure pcr TDAS lSS or (LPCS-PI-3)
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.
DiPcicntial prcssure dp (Discharge Pressura4uction Prcssure)Howrate per TDAS 164 (or LPCS-HAOO)
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.
Fluid Temperamre CMS-TR-5 FP"0 hfotor Voltage Per E.FI-SM7 NA PSIG iVA PSIG PSIG PSID GPM Refer Value SAT 16.6 SAT 16.0 NA 31$6350 N*NA Action Lo(+1)NA 7.7 NA (+2)l 6350 NA hlett Lo(+1)NA NA NA NA NA (+3)Nh NA NA Measured Value A!crt K(+1)NA NA iVA (+3)NA iVA Amion K(+1)UNSAT UNSAT iVA (4 2)6541 iVA ViA Motor Current Per LPCS-AM-1 AMP NA iVA NA iNA NA Outboard Motor Bearin Tcmperamre Per W12S Outboard Motor Bearing Temperature per W129 Inboard Motor Bearing Temperature per W130'F NA NA ViA Nh Nh NA NA NA Nh iVA iVA Nk (+1)For measured values beyond the Alert Value or Action Value refer to Precaution and Limitations 4.6 or 4.7, respectively.
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.
(+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.Attachment 9.2 7.4.5.1.7 rhea 15 of 18 AHP 0 T>'ll'~Revision R P-P-P~~pU NS C>>: 'I I C r'~s[~I l l p~I I I s IRD MODEL SZO Q~r)1D iNQ.IRD MODEL 970 (PROBE)iD NO.CAL DUE DAT-CAL DUE DATE Bearin 4 Probe Locaaoa Vibrsaca Velociry (ia/sec)N4 E-W Reier Value 0.130 0.150 0.100 Measured Vshe Alert EK (+l)Acdoa HI (+l)0.700 0.700 0.600 D.(L11)Q.<~l.)(+l)For measured values beyoad tho Alert Value or Acaoa Value reier co~aoa sad L'miuaoas 4.6 or 4.7, resp ecavely.Attachment 9.3 FROCK)URE WOMB Ek 7.4.5.1.7.PAGS 46 Of 18 l>>D)I*~I 1~'H A II t II AMPL DATA HEE7 P Revision I'LPCS-P-1 ACCEPTANCE CRITERIA 3m I X0 290 A Ef 270.630 638l M83 64CO 6420 644l 64K 64M 6500 6520 6540 6560 FLOWRATE-GPM ALERT RANGE-Area Outside I-2-3-4 ACTtON RANGE-Area Outside 5-6-7-8 Attachment 9.4.2RGCKURE WMEZ 1.4,5.1.7 REVTSiON 17 oi 18 P V I j'll~II 4 14 I 4 I V~1 C I Ji I'I'w'(4 4 I I r,~~v t'i I l 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 Supply System is confident that the HNP-2 Valve Inservice Test Pro-gram complies with the intent of all applicable Codes, Regulations(1),
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".
and Generic Letters(2) and contributes to ensuring the safety of the general public.
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.
(1) 10CFR 50.55 a(g)(2)
The Code recognized that certain of its requirements may be impractical for a specific plant and contains provisions.
(2) Generic Letter 89-04
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  
~'~F~I F F 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.
ll f I 2': 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.
v I Pg~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.  
        ~
'I h r a~A tt I l 4~, l N I I 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 CK Check valve DIA Diaphragm valve GB Globe valve GT Gate Valve PLUG Plug Valve 3-HAY Three Nay Valve RD Rupture disc.RV Relief Valve SC Stopcheck valve SHEAR Shear Valve S/R Safety/Relief Valve SV Solenoid 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 4 1I I'N v 4 b Pg~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 hours 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
F ~
-Same as"C" but the containment must be deinerted.
F I
Refueling-To be tested as often as refueling outages occur.At least every 18 months.Not Applicable
F
-No stroke testing is required.
 
~1I 1~~~1 1~~1'"l'1~
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:
9~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.
: 1)  Valve Operability Tests
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.
: 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.
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.
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,
P II'~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.
: 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.
A valve may have more than one associated relief request.
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.
0 6 hlNP-L PUHP AND VALVE IHSERVICE TEST PROGRAH-VALVE TEST TABLES Revision 41 Page 4,4-07 4 QQQQQQCIDQQQCQQQQD4 VALVE thUNDER Q cl DQ QQQDQCQ Cc CAC-FCV-IA QQQ4 4 CODE CLASS QQQCQ crracrr air LOCATION 0th PIIID aaacaaaa HID II 554 Ir rr rr 4 4 4 VAI.VE CATECORY 4 aa a aaaacaaa SIZE 1th INCHES 4 carr 2.5 VAI.VE TYPE DCCQC GD aaarraarr 4 ACTUATOR TYPE DcaccQlra HO acacaca Q--POS I T ION---NORIIAL FA1LED 4 1I a cr a a a 4 rr 4 4 a a NC FC EXER.TEST CODE FRED.4 4 a I1 c DCQCCCQCC GHJKL~.~aaar aaaacaaaa Qaca-1lacrra NOTES D rr 4 4 Q 4 4 4 rr 4 aaaaaarrcaa RELIEF REQUESTS QCDQQD QCC Ir 4120 CAC-FCV-18 CAC-FCV"2A Hb F 2.5 CD HO WC FC Q GHJKL..~tl5 5 4 GIO.F 2~5 GB HO NC FC 0 GHJKL...N554 4120 I~4~20 CAC"FCV-28 Gb F tl554 2'GB HO NC FC Q GHJKL.~CAC-FCV-3A DIO F 2'GB HO NC FC Q GHJKL~.~tl5 5 4 I~4~20 CAC-FCV-38 Db F 2~5 GB HO NC FC Q tI554 GHJKL~~I r 4120 CAC-FCV-4A FIO F 2.5 GB HO NC FC Q GHJKL.~tl554 1~4120 CAC-FCV-48 2 Eb tl554 F 2.5 CD HO thC FC 8 GHJKL..1~4'0 CAC-f CV-5A F14.8 1 CD HO NC FC Q tl5 5 4 GH JK~~~~20 CAC-FCV-58 CAC-RD-IA F2 8 I CD HO NC FC 0 GHJK~~re 20 tl554 D12 D 2 RD SA NC NA N.......Ih 10 H554 CAC-RD-18 D3 N554 D RD SA thC NA th~~~~~r II 10 CAC-RV-b3A E12 C I X 2 RV SA NC NA N.r~P~r tl554 CAC-RV-b38 E4 C N554 I X 2 RV SA NC IIA N~~r.PE CAC-RV-b5A D13 C 1.5 X 3 RV SA NC NA N~~~~~P~~tl554 CAC-RV-b5D CAC-V-IA C 1.5 X 3 RV SA thC NA N~~~P tl55 4 r F15 8 2-D I A HO tlC FC 0 CHJK~~~~M554 20 CAC-V-18 FI T I~'I'D1 A HD NC FC CHJK.~.~20 h g t Cl 4 I''i WNP-2 PUNP AND VALVE INSERVICE TEST PROGRAM-VALVE TEST TABLES Revision 4 Page 4.4-08 aaaazscacasaccaasasa:s VALVE NUtlDER casasasasaaasca:access CAC-V-2 al a a s a CODE CLASS a a aa aaaasaccc LOCATION Otl Pt ID a s Gl0 H554 saaccaas aaaaassss saaaac sacasaas VALVE SILE IN VALVE ACTUATOR CATECORY ItlCHES TYPE TYPE caaascaa aacscscc cases aacssssa F 4 GT HO as acaasa aac--POS I T I Otl---NORtlAL FAILED ccaaaaaasasaa tlC" FA I asses EXER.FREO.a aa c s a c c c c aa aa c aa aaasaascaa saaaaaaaas GHJ.L...saasaaaaaas TEST CODE NOTES csaaascaas RELIEF REQUESTS asasaaaacaa 4r20 CAC-V-2A 2 F12 D 4 tl554 DIA HO NC FC 6 CHJK....20 CAC-V-28 F5 DI A HO=NC FC 6 GtlJKr r r 20 CAC-V-4 Elo F tt 554 GT tlo NC FAI 6 CHJ~L~~~4'0 CAC-V-6 HIO F GT IIO tlC FAI 6 CHJ.L~.~4a20 CAC-V-8 D10 tl554 F GT NQ NC FAI 6 CHJ.L..~4r20 CAC-V-11 2 06 M554 F 4 GT HO NC FAI 6 CHJ~L~~~4r20 CAC-V-13 2 Eb F HO NC'AI 6 GHJ~L~~~4~20 CAC-V-15 2 Hb F N554 4 GT NC FAI 6 CHJ~L~~~4'0 CAC-V-17 Db F tt554 4 GT ttn NC FAI 6 GHJ.L...4r20 CAS-V-730 2, K9 tt51 0 F-P 1 CD HAN LC NA N~~~L~~~CAS-VX-82e tt5 1 0 F-P CD ttAN LC NA~~~~L~~~CCH-RD-IA G8 D 3 N775 RD SA NC NA N.....It 10 CCH-RD-18 3 C7 D tt775 RD SA tlC NA N~~~~~~~It 10 CCH-RV-2A 3 F7 C.75 X 1 RV'tt775 SA NC NA N~~~~~P~ccH-Rv-2n B7 C tt775.75 X 1 RV tlc NA~~~~~P~CEP-V-IA 2 J13 tl543 I DF AO NC FC 6 CtlJKL 4r20 CEP-V-ln a Cn Ao FC 6 GtlJKL...4'0
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.
'I~,'C~~l h l II L I'V IIIIP-2 PUNP AND VALVE INSERVICE TEST PROGRAH-VALVE TEST TABLES Revision 41 Page 4.4-09 eeceeccc=a==a
Subarticle INV-3420 of the Code specifies that valve leak rate tests are required for category A valves.
-ascaareec VALVE NUMBER cccseecaarrcssceecacac CEP-V-2A~e ee CODE CLASS reer~acacccc LOCATION ON PhID cccccra J13 M543 1 c ee c D ee D ee c VALVE CATEGORY ee c scarce SI IE IN INCHES CDC 30 CCCDD VALVE TYPE caeear DF sccDDCCD ACTUATOR TYPE eeeecsacsc AO a a a ee a c ee a a c a c a--POSITION---
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.
tfORMAL FA ILE 9 ee c a D a ee r D a a c a D NC FC EXE R.FRED.sssas Q ascsacraa GHJKL~~.careers Daa asreeccrrr TEST CODE NOTES aarrcacaaa RELIEF REQUESTS ac cacaaeea 4e20 CEP-V-2B CEP-V-3A 2 J13 F 2 GB AO NC FC Q GHJKL~~~4'0 M543 1 2 C14 F 24 BF AO NC FC Q GHJKL~~~4e20 M543 1 CEP-V-39 2 C14 M543 F 2 CD AO NC FC 0 GHJKL~..4e20 CEP-V"4A CEP-V"49 CIA-RV-5A C14 F 24 BF AO t<C FC 0 GHJKL..M543 1 2 C14 F 2 GD AO NC FC 0 GHJKL M543 1 3 Hl 1 C~75 RV SA NC tlA tl...~.P..4e20 4e20 Cl*-RV-5B 3 911 C.75 RV SA tlC NA N~~~~PE M556 1 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 B.5 SV SOL NC FO C.HE K..ltle8 tl556 1 24 CIA-V-20 KB F tl556~75 CD MO NO FAI Q GHJ L...4e20 CIA-V-21 e Kb FC~75 CK SA tlO N*R.H~.LE~~3e 4 tl556 1 CIA-V-30A G9 F.5 CB MO tl556 I NO FAI Q GHJ.L...4e20 CIA-V-309 F8 M556 1 MO NO FAI 0 GHJ~L~~~4e20 CIA-V-31A G7 FC M556 1'5 CK SA NO NA R eH~~LE~3e 4 CIA"V-319 CIA-V-39A C I A-V-399 2 F7 FC.5 CK SA NO thA R AH..L~.~M556 I J10 9~5 GD AO NO FC C GHJK..11 tl556 1 E10 B~5 CB AO tlO FC C GHJK....11 3e 4 20 20 I I P t WNP-2 PUNP ANO VALVE INBERVICE TEBT PROGRAN-VALVE TEST TABLEB ReVision 41 Page 4.4-1Q oc acssc c sass o oo VALVE tlUtlBER sacaooaossaaaoasccocaao CIA-V-40 lTYP 71 cao a CODE CLASS oases 2 c o ca cs o o o s LOCATION ON I sin c o a ss cc c a o J5-85 tl556 1 cocaosa o VALVE CATEGORY acaacasaa AC aooocaoo S I I E I tl I tlCHES o o o o o o cs c~5r VALVE TYPE casse CK ACTUATOR': TYPE ococ cao SA ssaosss ascaaassaacs a c o a ca s s a a a a sa sa-I OSI TION--NORtlAL FAILED scosaooaaoosaa NO NA sssasa EXER.,FREQ.~a a as o cc R aaoosaa a saassassaaca s o o a a a a a sa.H..L...acsaoaaa asa TEST CODE NOTES aasaaaocaca RELIEF REQUESTS ocsasscsaa 3~7 CIA-V-52A THRU 66A G12 C.5 CK SA NC NA C.H.~....1H tl556 1 CIA-V-528 THRU 708 3 C12, C.5 CK tl556 I SA NC tlA C.H.~....1N CIA-V-103A H13 C~5 CK SA NC NA C.H....~~ltl tl556 1 CIA-V-1038 D12 C H556 1 CK SA NC NA C.11.~~.I tl CIA-V-104A H13 tl556 1 8~5 CB HAN NC NA C.H.~~...ltl CIA-V-1048 D12 8 tl556 I~5 GB HAN tlA C.H.~...Itl , CRD-V-10 2 K6 8 tl52S I CB AO NO FC Q GHJK~~~14~20 CRD-V-11 CRD-V-180 Fb tl528 t1528 GB AO AO NO FC Q GHJK..~.14'0 tlO FC Q GHJK~~~~14r20 CRD-V-I 8 I F*8 tl528 CD AO NO FC Q GH JK~~~~14'0 CSP-V-1 2 D6 F 30 BF AO NC FC Q GHJKL.~HS43 1 4r20 CSP-V-2 D6 tl543 1 30 BF AO NC FC Q CHJKL~~~4r20 CSP-V-3 2 C5 F 24 BF AO tl543 1 NC FC GHJKL..4r20 CSP"V-4 C5 tl543 a24 BF AO NC FC Q GHJKL~.~4r20 CSP-V-5 2 C5 F 24 BF AO NC FO Q GHJKL...tl543 1 4r20 0 CSP-V-6 917 H543 2 F BF AO FO GHJKL...4r20 CSP-V-7 C5 FC 24 CK AOrSA NC tlA Q GH..L...6~sr~'s r 4~~
 
WNP-2 PUHP AND VALVE INSERVICE TEST PROGRAH-VALVE TEST TASLES Revision 4t Page 4.4-11 sssseessasasasaaaasss VALVE NUtlBER i c ee 4 s 4 4 s el 4 4 4 4 4 re 4 4 l1 s 4 CSP-V-8 Saic je CODE CLASS SD ri re LOCAT10N Otl Ptr ID i a Casa 814 tl543 I Das serrea VALVE CATEGORY sscerssas FC eesD ress a SITE IN INCHES assicaasa 24 casa VALVE TYPE 1 acies CK ri sisccs ACTUATOR TYPE assasaas AOesA s s s D Dace--POS1T ION--NORtIAL FAlLED a re 4 ee s a 4 a 4 a a s ee NC NA SD EXERT FREON csa SD C DS cssDai a cseecaaaaa GH..L...DCDSSDDSDC TEST CODE NOTES REL1EF REQUESTS asseeaasaaa CSP-V-9 86 M543 1 F 24 OF AO NC FO Q GHJKL~~.CSP-V-10 CSP-V-93 CSP-V-96 2 D6 FC 24 CK AOrSA tIC NA Q GH.~L...6 M543 1 2 F5 F I SV SOL NO FC Q-GHJKL~~~lr M783 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.~M783 fr 4 CSP-V-98 F5 tl783 F 1 SV SOL NO FC Q GtIJKL~..1 r 4 CVB-V-I A CVB-V-lB CVB-V-lC CVB-V-ID CVB-V-IE B12 AC 24 CK AOrsA NC NA Q GH.....6 tl543 1 2 812 AC 24 CK AO e SA tlC IIA Q GH~~~r M543 1 2 812 AC 24 CK AOrsA NC NA Q GH...~..6 6 M543 1 812 AC 24 CK AOrSA NC NA Q GH....~~6 6 tt543 1 2 811 AC 24 CK AOrsA NC NA Q GH.~..r.6 M543 1 CVB-V-1F CVB-V-1G 2 Bl 1 AC 24 CK AOeS*NC NA Q GH M543 1 811 AC 24 CK AOrsA NC NA Q Gtl......M543 I 6 6 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 24 CK AOrSA NC NA Q Glt..r...6 M543 I CVD-V-I I.88 AC CK hOrsh NC NA Q liH......6 6 I~t~I'a II It It WNP-2 PUHP AND VALVE INSERVICE TEST PROGRAM-VALVE TEST TABLES Revision 41 Page 4.4-12 Dccccscssscssscs
ll f
-ac VALVE NUtrBER DQDQQDQCCCCCQCDDDSCS CVB-V-ltl CODE CLASS QCQSQ 2 scscsccc LOCATION ON earn CDSQQCDD 99 tl543 1 sccscass VALVE CATEGORY CSCQCQSQ AC ccac c s SIZE IN INCHES CQ C Q 24 sssss VALVE TYPE CQDQS CK Sc DCDDS sssaasacscsall ACTUATOR--POSITION---
I
, TYPE, NORtlAL FAILED QQDCSQSS SSCCSSDDDDCDQ ADA SA t(C NA DSQSD EXER-FREQ.CDCDC Q SSCDCCCQQ aacssscass ssacscacc GH~~~~~~ccasaacsss TEST CODE NOTES sacscccacc RELIEf REQUESTS DQDSSSDDSQ CVB-V-IN 88 AC=24 CK AOzSA NC-NA Q tl543 1 GH~~~~~6 CVB-V-1P CVB-V-10 89 tt543 97 tr543 AC CK AOeSA tlC NA Q GH....~.6 1 24 CK AC 24 AOlSA NC NA Q GH.....6 1 CVB-V-lR 97 tr543 AC 24 CK AOeSA NC NA Q 1 GH~~~~~~6 CVB-V-1S 87 tl5 4 3 AC 2 AO~SA NC tlA Q GH.~~~~.6 CVB-V-lT 2 87 tr5 4 3 AC 24 CK AO~SA NC NA Q GH~~~~~~6 DO-V-1A J12 tr5 1 2 1.5 SA tlc NA Q~H~~~~~~DO-V-18 DO-V-10 DSA-SPV-SA1/2 DSA-SPV-5A1/4 F12 tl51 2 CB t1512 F10 tl512 E10 tl512 C 1+5 CK SA NC NA Q AH-.-~4 C 1.5 CK SA NC NA Q.H..1 9 2 3-WAY SOL NC FAI A~HJ.~.~o 12 2 8 2 3-HAY SOL NC FAI A.HJ....o 12 2 DSA-SPV-5A2/2 F6 8 2 3-MAY SOL NC FAI A.NJORD~~12 tr512 2 DSA-SPV-5A2/4 D Eb tl512 9 2 3-ltAY SOL NC FAI A~HJ~o~~12 2 DSA-SPV-591/2 9 F10 9 2 3-1IAY SOL NC FAI A HJ...12 t1512 3 DSA-SPV-581/4 Elo H512 9 2 3-rtAY SOL NC FAI A.HJ.."..12 3 DSA-SPV-582/2 Fb tr51 2 9 2 3-llAY SOL 3 NC FAI A.HJ.~~~.12 DSA-SPV-592/4 Eb ll l'0 3-MAY SOL NC FAI~HJ~~.~.12 II~-~~I~~4~h WHP-2 PUHP AND VALVE INSERVICE TEST PROGRAH-VALVE TEST TABLES Revision 4t Page 4.4-I3 VALVE NUtlDER rssasaccssssssssrsssr DSA-SPV-5Cl/1 CODE CLASS D ssasaaaaa scars-saaaaa sasrs sarsa LOCATION Ott PtslD Dsssrsrs E9 tl51 2 1 asssss s VALVE CATEGORY Sl ZE Itt IttcttES VALVE TYPE r s 3-WAY ssscscssss sssrs Ds asar ACTUATOR TYPE DDss rss SOL acssssssarsssa
 
--POSITION"--
2':
NORtlAL FAILED ssssarssssssa NC FAI EXER.FREO.D r~s sc ss s a D-a ss s s cs a s ss a sc s a ssssssssr~HJ~~~o~s Dssssass TEST CODE ttOTES a ss a a a a a ss ss RELIEF REOUESTS aassssrss DSA-SPV-5C1/2 DW-V-156 F9 B 2 3-WAY SOL NC FAI A'HJ....~12 M512 1 2 GB.F-P GT HAN LC NA N..~.L...4 M517 DW"V-157 GB M'517 F-P 2 GT HAN LC ttA N~~~~L~~~EDR-V-19 EDR-V"20 D9 F 3 GT AO NO FC tl537 2 D9 F 3 GT AO NO FC 0 GHJKL~~~4'0 M537 FDR-V-3 2 D6 F 3 BALL AO NO FC 0 tl539 GHJKL~~~4'0 FDR-V-4 Db F 3 BALL AO NO FC M539 0 GtlJKL~~~4I20 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 tl5 2 6 N~~~~~P~~FPC-V 112A D12 M526 C 6 CK SA.NC NA~H~~~~~~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 M526 SA NO NA 0~H~~~~~FPC-V-146A 3 Kll C B CK SA NO NA tl526 0.H......FPC-V-1460 3 K10 C S Ct(SA NO tl526 NA 0 olto~~~~~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 nr~y k m*w N 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 VALVE NUtlDER a=a=ass=accaaccaaaccrccs FPC-V-154 QQQQQ CODE CLASS aaaaa 2 asaasaaQ LOCAT ION OW P&19 aaccaaaaa 911 N526 sassaaaa VALVE CATEGORY Qsac Qaaa F QQ Qasas 5 I LE IN I NCI IE9 Q QQ asasa VALVE TYPE Qs Q GT sasasssa ACTUATOR TYPE aa aaa NO asssccssaasaas
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.
--POSIT10N---
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.
NORtIAL f A ILED Qas ass Qaaaacc NC FAI assaa EXER.FREO.a lc lc Q s Q Q Q a Qsasaasaaa assccsaccaa GHJ L.r~r ssssaaa TFST CODE NOTES a s Q s Q cc Q s Q a RELIEF REQUESTS aassaaaasa 4120 FPC-V-156 CII F 6 GT ND tIS26 NC FAI 0 GHJ.L.~.4120 FPC-V-172 C9 t)526 9 8 GT NO NO FAI 0 GHJ.....3 20 FPC-V-173 9 8 GT)IO tl526 NO FAl 0 GHJ...~3 20 FPC-V-175 C9 tl5 2 6 9 8 GT NO NC FA1 8 GHJ~~~.3 20 FPC-V-181A D14 9 8 tI526 NO NO FAI Q GHJ....3 20 FPC-V-1819 D14 9 8 GT IIO NO FAI 0 GHJ.....3 20 II526 FPC-V-184 C9 9 tl526 GT NO NO FAl 0 GHJ...~~3 20 HCU-V-114 ITYP 185)D HCU"V-1 15 I TYP 185)C2 C~75 CK SA NC NA HE~~HS28 C5 C I CK SA tIC NA.H~~~~~~11 tl5 28 HCU-V-126 I TYP 185)D C4 t)528 9 1 GD AO NC FO.H.....~11 HCU V-127 ITYP 18S)C3 tl528.75 GD AO FO H.....c 11 HCU-V-138 I TYP 185)C4 C.75 CK SA NO tl5 2 8 tIA~H~~~~~~HPCS-RV-14 2 Ch FC 1XI RV-SA NC NA N N520~~~~~P~~HPCS-RV-3S 2 C4 FC IX2 RV SA tlC NA N~~~~P~tl520 HPCS-V-I Ch NS20 9 14 GT tIO NO FA1 0 GHJ~~~~~HPCS-V-2 IIPCS-V"4 Cb~NS20 G7 11~'0 12 CK GT SA HO 0~HE~~...~NA tlC FA I 0 GH J~L~~~4~20
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.
'W l'II HHP-2 PUHP AHD YALYE IHSERYICE TEST PROGRAN-YALYE TEST TABLES Revision 41 Page 4.4-l5 cccaacaccaa Q acacaa VALVE NUNBER aaaaaacaccccacaacaca HPCS"V-5 QDCQQ CODE CLASS C II DDQQDDQQ LOCAT ION ON PtIID cc a I I 8 M520 Q Qcaca VALVE Sl ZE 1N CATEGORY.1NCHES CCCQ C TC 12 QIe D VALVE TYPE CK Daaacaac ACTUATOR TYPE aaaaaaaa AO~SA Q Q Q c Q a Q a c Q a c ee--POSITJON---
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.
NORtlAL FAILED Caaaeeaacaaaca NC NA D QQCQ EXER FREQ.a II II D ee a Ie Q C Q Ie Q Q C D D Q Q D QQQ a Q GH..L...ca-Qaa TEST CODE NOTES D eeaeIDCQQQ RELIEF REQUESTS aaacaacaaa 40 V HPCS-V-6 C5 C I~5 SC SA I tlAtl NO tl520 tlA Q~~~~~~~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..~.~H520 20 HPCS-V-11 HPCS"V-12 2 E3 B 10 CB IIO NC FAI Q CHJ~.~.20 II 520 2 95 F 4 GT II 0 tIC FAI Q'HJ.L...4'0 N520 HPCS-V-15 2 D7 F 18 CT tl0 NC FA1 tl520 OH'...4020 HPCS-V-16 HPCS-V-23 Eb C 24 CK SA NC NA 9.H.~..II520 E4 F 12 GB NO NC FAl Q GHJ~Le 0~N520 4020 HPCS-V-24 2 95 C 16 CK SA NC NA II520 Q I~I~~~~~~HPCS-V-28 3 Cb C 8 CK SA NC NA 0.H.~...tl 524 1 HPCS-V-65 H7 F-P I GB IIAN t1520 LC NA N~~~~L~~~H CS-V-68 F-P 1 GB tIAII LC NA N...Le~.-4 tl520 HY-V"17A E13 F tl5 3 0~75 CT SOL NO FC C GHJK~~.~1G 4020 HY-V"17B 2 E5 F.75 GT SOL NO FC C GHJK..~1G tl530 4020 HY-V-18A E13 II 530 F.75'T S0 I.NO FC C GH JK~~~~I G 4020 HY-V-189 E5 F.75 GT SOL tl530 NO FC C CHJK.~.~IG 4020 IIY-V-I'tA E13 F leee IA.75 CT SOL NO FC C CHJK.~..1C 4020
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.
WWP-2 PUMP AND VALVE INSERVICE TEST PRDGRAH-VALVE TEST TABLES RBYision 4t Page 4.4-ih acaaaaacrcacaslcaaalsa VALVE tIUtIBER c sl c c a c Q c c Q Q Q c Q Q c Q Q Q c HY-V-198 CODE CLASS DCQCQ 2 caaacaca LOCATION Otl PhID Q ace Q ca E5 tl530 VALVE CATECOAY C DcllQQ c a a c Q ls c ss SI1E IW IWCHLS cacccaac.75 Sl Sl Q Q D VALVE TYPE C C Sl ll GT~l a ss c ss ss c Q ACTUA'TOA TYPE Qaaaaaaa SOL aaassslaaaacaaa
 
--POSITION---
v I
NOAtIAL FAILED cllsscrslacaacaa NO fC QcQac EXEA.FAEQ.ll Q Q Q ll C sscaaassalsa aaassssassaaa Q C C Q ll ll ll D Sl CEIJK e~ss c c a ss c a ls r ss 1G TEST CODE NOTES~lacaaaaaaa AELIEf AEGUESTS QCQCQQCsla 4r20 HY-V-20A HY-V-208 HY-V-33A E13 II530 2 E5 II530 2 E13.75~75.75 GB CB GT SOL SOL SOL NO FC C GHJK~...IC WO FC C GHJK....IC NO FC C CHJK....IC 4e20 4r20 4'0 HY-V-338 2 E5 M530 F.75 GT SOL NO FC C CHJK....IG 4e20 HY-V-34A HY-V-348 2 E13 F IIS30 2 E5 F tl530~75.75 GT SOL tIO FC C CHJK....IG 4e20 CT SOL NO FC C GHJK...1C 4e20 HY-V-35A 2 E13 F.75 II530~, SOL NO FC C GHJK....IG 4e20 HY-V-358 2 E5 F II530.75 GT SOL NO FC C CHJK.~~~IG 4e20 HY-V-36A HY-V-368 2 E13 F tl530.75~75 SOL CB SOL NO FC C GHJK.~~.1G NO FC C.GHJK~~~~1C 4e20 4r20 LPCS-FCV-11 LPCS-RV-18 2e 813 II 520 F12 II520 FC GB HO 1.5X2 RV SA NC FAI 6 GHJ~L~~~4 l 20 NC'tIA N~~~~PE 9 LPCS-RV-31 2 C12 II520 FC IXI RV SA NC NA N~~~~~Po~9 LPCS-V-I 2 Dl I tl520 GT HO NO FAI 0 CHJ.L..~4r20 LPCS-V-3 813 tl 520 CK WC 0~I'I~~~~NA LPCS-V-5 Gl 1 II520 12 CT II 0 NC FA I C CH J~L~~IL 4r20 I.PCS-V-A H9 TC 12 CK AOeSA NC WA I GH..L...6 4e 9
 
Pg~
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 hours 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.
 
P  II'~
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.            ~
tl554 CAC-FCV-3A                    DIO        F              2 '            GB    HO              NC              FC          Q        GHJKL ~      .   ~                           I ~ 4 ~ 20 tl5 5 4 CAC-FCV-38                  Db          F              2 ~5          GB      HO               NC            FC         Q        GHJKL        ~ ~                             I r 4120 tI554 CAC-FCV-4A                  FIO        F              2.5            GB      HO              NC             FC         Q      GHJKL. ~                                       1 ~ 4120 tl554 CAC-FCV-48              2    Eb tl554 F              2.5            CD      HO              thC            FC          8      GHJKL. .                                      1 ~ 4 '0 CAC-fCV-5A                    F14.       8              1              CD      HO              NC              FC          Q      GH JK ~    ~ ~ ~                              20 tl5 5 4 CAC-FCV-58                    F2          8              I              CD      HO              NC              FC        0        GHJK ~ ~      re                              20 tl554 CAC-RD-IA                    D12        D              2               RD      SA              NC              NA        N        .......Ih              10 H554 CAC-RD-18                    D3          D                              RD      SA              thC            NA          th        ~ ~ ~ ~ ~  r II        10 N554 CAC-RV-b3A                  E12          C              I   X  2      RV      SA              NC              NA        N        .r      ~ P  ~  r tl554 CAC-RV-b38                  E4          C              I    X  2       RV      SA              NC              IIA        N        ~ ~  r  .PE N554 CAC-RV-b5A                  D13          C              1.5    X  3  RV      SA              NC             NA        N        ~ ~ ~ ~ ~  P ~ ~
tl554 CAC-RV-b5D                                C              1.5    X  3  RV      SA              thC            NA        N        ~ ~   ~   P tl55 4 r
CAC-V-IA                    F15          8              2 D IA    HO            tlC             FC          0        CHJK ~    ~ ~ ~                             20 M554 CAC-V-18                    FI    T                                    D1 A    HD            NC             FC                    CHJK. ~ .                                     20 I~ 'I'                                                                                                                    ~
 
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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    "
FA I            GHJ.L...                           4r20 H554 CAC-V-2A                    2  F12        D       4        DIA    HO          NC        FC        6      CHJK....                            20 tl554 CAC-V-28                        F5                            DI A    HO    =
NC        FC        6      GtlJKr r r                          20 CAC-V-4                        Elo tt 554 F                  GT      tlo        NC        FAI      6      CHJ ~ L ~     ~ ~                   4 '0 CAC-V-6                        HIO        F                  GT      IIO          tlC      FAI      6      CHJ.L .   ~     ~                 4a20 CAC-V-8                        D10        F                  GT      NQ          NC        FAI      6      CHJ.L..         ~                 4r20 tl554 CAC-V-11                    2  06          F        4        GT      HO          NC        FAI      6      CHJ ~ L ~     ~ ~                   4r20 M554 CAC-V-13                    2   Eb          F                          HO          NC   'AI          6     GHJ ~ L ~    ~ ~                  4 ~ 20 CAC-V-15                    2  Hb N554 F        4        GT                  NC        FAI      6     CHJ ~ L ~     ~ ~                   4 '0 CAC-V-17                        Db          F        4         GT      ttn        NC        FAI      6      GHJ.L...                            4r20 tt554 CAS-V-730                  2,  K9 tt51 0 F  -P    1        CD      HAN        LC        NA        N        ~ ~ ~ L~  ~ ~
CAS-VX-82e                                  F  -P              CD      ttAN        LC        NA              ~ ~ ~ ~ L~  ~ ~
tt5 1 0 CCH-RD-IA                      G8 N775 D       3        RD      SA          NC        NA        N      .....It              10 CCH-RD-18                  3  C7          D                 RD      SA          tlC      NA        N      ~ ~ ~ ~ ~ ~ ~  It    10 tt775 CCH-RV-2A                  3  F7          C        .75  X  1 RV      SA          NC       NA      N      ~ ~ ~ ~ ~ P    ~
tt775 ccH-Rv-2n                      B7          C        .75  X  1 RV                  tlc      NA                ~ ~ ~ ~ ~ P    ~
tt775 CEP-V-IA                    2   J13                           DF      AO         NC       FC       6      CtlJKL                              4r20 tl543 I CEP-V-ln                    a                                  Cn      Ao                  FC       6      GtlJKL...                           4 '0
 
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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..
Cl*-RV-5B                      3  911          C                    .75        RV      SA            tlC            NA      N    ~ ~   ~ ~ PE M556 1
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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blkIP-L PUNP AND VALVE IHSERVICE TEST PROGRAII-VALVE TEST TABLES Revision 41 Page 4.4-17 aaacacaacs cjcssjjsssaas VALVE tiUHBER D Q c Q c ss a D D D a D a a c ss s ss c c LPCS-V-12 DCCSD CODE CLASS cracQ 2 a c sca LOCATION ON PhlD~jcsjaassca F14 H520 accccc VALVE CATEGORY caa-r c C S D jjajr SIZE IN INCHES C 12 VALVE TYPE asses GB acjsjsjjjsj jsc ACTUATOR TYPE aaaacsscsc HO~j a c c a ss D D D'cc c a cc--POSITION---
NORtIAL FAILED csscsassjrarca NC FAI a a sj Q a D a jj c a EXER.FREQ.TEST CODE NOTES ccascc cc GHJ.Lo caaaaarcac csasacc aaaaaaaass cs s cs a a ss cs ss a s RELIEF REQUESTS cccaQC c c 4r20 LPCS-V-33 C12 H520 1.5 CK NO tlA Q.H~.~~.~LPCS-V-34 C12.tl520 1.5 SC SArHAtl NO NA Q~H~~~~~~LPCS-V-bb H10 H520 F"P HAN LC tlA~~~L~~~LPCS-V-67 H10 H520 F-P 1 GB HAN LC NA~~~~L~~~HS-RV-I A F10 M529 6 X 10 S/R'AOrSA NC IJA N~~..P~7 HS-RV-18 Ell C 6 X 10.8/R AO r SA tlC tlA N~~P~H529 HS-RV-I C HS-RV-1D HS"RV"2A Fb t1529 E7 tl529 F10 H529 6 X 10 S/R AOrSA NC NA tl o..PE 7 6 X 10 S/R AOrSA NC NA N~~PE~7 C 6 X 10 8/R AOrSA NC NA N.....P..7 HS-RV-28 E10 H529 6 X 10 S/R ADA SA tlC NA tl...P.~7 HS-RV-2C HS-RV-2D HS-RV-3A HS-RV-38 HS-RV-3C HS"RV-3D f7 H529 E7 ti529 F9 tl529 E9 H529 F7 tl5 29 EB 6 X 10 S/R AOrSA NC NA N~~~P 7 6 X 10 S/R AOrSA NC tlA N~~~~~P~7 6 X 10 S/R ADA SA NC NA N P 7 6 X 10 8/R AO~SA NC NA N P 7 6 X 10 8/R AOrSA NC tJA N..~..P.7 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 NUtlBER cocoa-ssassassoacasscsocss tIS-RV-48 CODE CLASS I LOCATION ON Phln D D D CS D D D D E9 tI529 VALVE CATEGORY aaossocaa BC SIZE IN VALVE INCHES TYPE cIcc DDDD DaosIL 6 X 10 S/R ACTUATOR TYPE aaoaacace AOISA--PCS I T10N"--NORtlAL FA lLED aaacaaaccsaoace NC NA EXERT FREQ.oaossa R\LDD aoaaa.H...P..aasscaacoass TEST CODE NOTES RELIEF REQUESTS DDaaass DDD 13 HS-RV-4C I F8 BC 6 X 10 S/R AOeSA NC NA R~H~~~P..13 II529 IIS"RV"40 E8 N529 BC 6 X 10 S/R AOe SA NC NA R.H...P..13 HS-RV"58 I E9 BC II529 6 X 10 S/R AO~SA tIC tIA AH..~PE~13 tIS-RV-5C HS-V-lb F8 BC 6 X 10 S/R AOeSA NC WA H529 I 813 F 3 GT IIO NC FA1 II529 R.H.~~P..0 GHJ.L...4e20 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 F 26 GB AO tlO FC 0 GHJKL~~~4'0 N529 HS-V-22C F5 II 529 26 GB AO NO FC 0 GHJKL..~4e20 HS-V-22D tlS-V-28A I E5 F 26 CB AO NO FC 0 CHJKL...4e20 II529 I F13 F 26 GB AO NO FC 0 CHJKL.~.4e20 II529 IIS-V-28B E13 F II529 26 GB AO NO FC GHJKL...4e20 IIS-V-28C I F4 F 26 GB AO NO FC 0 II529 GHJKL~~~4e20 tlS"V"28D E4 F tI529 26 CB AO NO FC 0 GHJKL 4e20 tlS-V-37 I TYP 18)C6-CII C 10 CK SA NC NA I.H....18 II529 tlS"V-38 ITYP 18)t 2 C6-C I I C 10 CK SA NC NA I tl529~H~~~~~~18 tIS-V-67A F13 F I 5 CT tIO NC FAl 0 tiN>P GHJ LE 4e20 l'r I P I>~h A H I C 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 VALVE tlUtl DER carra ssaracaaa crass NS-V"h79 ssaaa-CODE CLASS ssaaaa assaaaara LOCATION Otl PtslD ass ra rca F13 tl529 arras arr VALVE CATECORY ssaassaacss SIZE IW IWCHES asss:raaaa 1.5 VALVE TYPE aarrss GT ACTUATOR TYPE acaaa ssa NO sscslac ssaaaa assr c a a a ss a a ss ss a a a a--POS I T I OW---WORtlAL FAILED aaaaacacaccaa tIC FA I ccaaa EXER.FREO.a ss a a a 0 aacaaaaaa aaaaassassaa car acr aa GHJ.L...a c r a ss ss a a ss a TEST CODE NOTES caaaaassssaa RELIEF REQUESTS aaaassrrssaa Rs20 tlS-V-h7C F4 N529 I f 1.5 GT tlO WC FAI 0 GHJ.L...4s20 NS-V"h7D DR F N529 1.5 GT NO WC FAI 9 CRT L 4'0 NS-V-14h 2 87 9 24 GT NO WO FAI C tl502 I GHJ....IS 20 NSLC-V-I A 2 87 9 1.5 GT NO WC N557 FAI 6 GH J.~.~20 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 tl557 20 NSLC-V-ID 9 1.5 CT tlO WC FAI 9 GHJ....~20 NSLC-V-2A NSLC-V-28 NSLC-V-2C NSLC-V-2D I CS 8 I~5 GT NO WC FAI C GHJ.~~IR 20 N557 I CS 9 1.5 GT NO WC FAI C OH'..~IR 20 N557 ES 9 1.5 GT NO WC FAI C GHJ~...~IR 20 t!557 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~~-N557 IR 4 s20 NSLC-V"38 CS F 1.5 GT NO WC FAI C CIIJ.L~~~IR tl557 4s20 tlSLC-V-3C I ES F 1.5 GT NO WC FAI C GHJ~LE~..IR 4s20 tl557 NSLC-V-3D I ES F~I s5 CT NO WC FAI C CHJsL~~~N557 IR 4s20 tlSLC-V-4 2 JR N5 9 I~5 GT tlO WC FAI C CHJ~.~.~IR 20 57 tlSI C-V" 5 2.15 9 1-5 I T NO WC FAI C GHJ.....IR 20 lt n I I I If f I~I'I I fl T',I I I MHP-2 PUHP AHD VALVE IHBERVICE TEST PRDGRAII-VALVE TEST TABLES Revision 41 Page.4.4-20 Q a Q r c Q Q Q ss ss a c a Q Q Q a Q r c VALVE NUtlDER QSSQS:ararraSsaaarrrrrs:
tlSLC-V-9 ssrraa CODE CLASS cac r c D r D ss Q r D LOCAT ION ON PAID raarrraa H5 H557 DQDaDQQQ VALVE CATEGORY CLLCQQ QQQQCQCQ Sl IE IN INCHES rrr rara 1.5 QDQCC VALVE TYPE c CLc GT arssaaaaa ACTUATOR TYPE QQDcassssss HO a Q a a a D a ss D D a a D--POSITION
--NORtlAL FAILED rrccrssssaacaass NC FAI ss D D a D EXER.FRESs~sDQQQ C aaassassssssa ssaassssssaaass TEST CODE NOTES rccasscQDD ssrassssaassass GHJ.--IR a a a a ss ss a ss a a RELIEF REQUESTS-aassaaassaa 20 tlSLC-V-10
.H5 tl557 1.5 GT NC FAI C GHJ.~...1R 20 PI-EFC-X18A FC 1 X.5 CK SA NO NA R GH~....=4~15 Pl-EFC-X188 P I-EFC-X18C G9 tl557 G9 tl557 FC FC 1 X~5 CK 1 X.5 CK NO NA R GH...~~~NO NA R GH~~~~~~4~15 PI-EFC-X18D F9 FC 1 X.5 CK SA tl557 R GH~~~~~4~1S Pl-EFC-X29b H7 tl543 1 FC 1 X.5 CK SA NO NA R GH~~~~~~PI-EFC-X291'I-EFC-X30a G13 SA tl0 NA=R GH.~~~~4s15 tl54 3 1 1 X.5 CK H7 FC 1 X.5 CK SA NO NA R GH~~~~~~4'5 tl543 1 P I-EF C-X 30 I'13 FC 1 X.S CK SA NO NA R GH..~.~~N543 1 P I-EFC-X371 D6 tl521 1 FC 1 X.5 CK SA NO NA R GH.~s...4s15 Pl-EFC-X378 D6 FC 1 X.5 CK SA tl0 NA R GH.~....HS21 1 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~~~N529 4s15 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 tl519 4s15 PI-EFC-X38e G6 FC 1 X.5 CK SA NO NA tl519 GH~~~~~~4s15 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
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


WHP-2 PUMP AND VALVE IHSERVICE TEST PROGRAM-VALVE TEST TA8LES Revision 41 Page 4.4-29 VALVE NUtIDER csassacaacscsacacss RCC-V-5 CODE CLASS caaass saascasscaaccaasaaa-aaaaa acs:ssaassss LOC*T 10tl OW PIID c-s ac sr=sr DIO M525 acssscQ a VALVE CATEGORY caasa QQ aasscaaaa Sj jE ltI INCHES Cs SSQ C 10 caQQC VALVE TYPE GT saaaasaa ACTUATOR TYPE Qcaaaaas MO--POSITlON---
II'~
NORtIAL FA ILED asac-a-aa-ss-ss NO FA I caaaa EXER.FREON scca QQ CQCQQQ OH'E~ccaaa casa ID ssasssssaaaa ssaasss-sass TEST CODE tIOTES sass aaasa REL jEF REOUESTS QQ a Q 4s20 RCC-V-21 RCC-V-40 D10 F 10~GT MO NO FAI C GHJL...ID 4r20 M525 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 B 8 GT MO NO FAl 0 GHJ~....20 M525 RCC-V-130 3 Eb, B 8 CT MO NO FAl 0 GHJ.M525 20 RCC-V-131 3 Eb B 8 tl525 GT MO NO FAI 0 GHJ~~~~20 RCC-V-133A H5~C M525 6 CK SA NO NA 0.H...~RCC-V-1338 F5 C tl525 CK SA NO NA 0.H...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 tl519 W 2s10 RCIC-RV-17 C13 C lxl RV SA NC NA tl~..~.P..2 tl519 RCIC"RV-19 09 C tl519 2X3 RV SA WC NA N~~~~P~~2 Rcjc-V-l Ell 8 M519 3 GT MO NO FAl 0 GHJ~....2'0 Rcjc-V"8 Fb F GT MO NO FAl 0 GHJ L.~.4 tl5 1 9 4r20 RC 1 C-V-10 RCI C-V" I I 2 814, tl519 tl519 D 8 GT tIO NO FAl 0 GHJ.~...2 20 C 8 CK SA NC WA 0.Ms'~2 RC I C-V-13 H7 T 6 GT MO tIC FAI C GHJ~L..IK 4s20 s r 4 I 4 kl n 4 l, r I 4 N'a IINP-2 PUHP AND VALVE INSERVlCE TEST PROGRAN-VALVE TEST TABLES Revision 41 Page 4.4-30 rs:aacaaaacaaatrracrc VALVE tlUtlDEA ctraccacacsstrcatrcrc RCI C-V-19 car CODE CLASS CCC araacaaa LOCATION Otl PI(ID caccssraa E7 N519 ca Crace VALVE CATEGORY Dr Ctr C rs DCQCD(s SILE IN INCHES C a QC VALVE TYPE C Caa GD Q Q C a IS Q a D ACTUATOA TYPE~I Is c Is r s(Is c tIO acacaaDacraaa C IS t a D-PCS IT IOtl---EXER NOAtlAL FAILED'REQ~~stra (siss(carat ccrc NC FAI 0 aas(aaarca GHJ.L~.~Qc ccQacac~I-a a II s(a a a s(r c r c a Q ss Q r TEST CODE NOTES aaaaaaacaa RELIEF AEQUESTS cssaaaaass(sa 4(20 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 HS19 HE L.." 4 RCIC-V-30 C7 tl519 C 8 CK SA NC NA~H~~~~~2 RCIC-V-31 RCIC-V-40 2 C7 f 8 GT tlO NC FAI Q GHJ.L~..II519 08 FC 10 CK SA NC NA Q.H.L H519 4(20 RCIC-V-45 2 F11 8 GD HO NC FAI Q CHJ~~~~2'20 t151 9 RCI C-V-46 2 F11 8 tI519 CD II 0 NC FAI 0 GHJ~~~~~2 20 RCI C"V-59 RCIC-V-63 J9 8 6 GT HO NC FAI Q GHJ.(~.2 II519 I H3 F 10 CT tI0 NO FAI Q GHJ.L.II519 20 4(20 RC I C-V-64 I Ch tl519 F-P~10 GT HD LC NA N~~.~L o RCIC V-65 RCIC-V-66 Hb C 6 CK AO~SA" NC NA I GH~~~~~~2'tl519 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~H519 4(20 RC I C-V-76 H3 NS19 F I CO tlO NC FAI 0 GHJ(L~.4 4(20 ACIC-V-86 2 A13 C 2 CK SA NC tlA 0 H~~~.2 I'~'I A't F WNP-L PUHP ANIj VALVE INBERVICE TEST PROGRAH-VALVE TEST TABLEB Revision 41 Page 4.4-31-SSDDCDSCSCSDSCCSDC VALVE NUHDER DDRCDDDDDDDCSDDDRSDU RCIC-V-110 CCC S CODE CLASS DDDCU CC CSDSS LacATION ON Phla DDDDIIDCD E7 H519 CDSSCSSC VALVE CATEGORY CDCIIDDCR S S SIIE IN I NCllES U D S U D S D rl~I IIC SCSDISCSS SD C S C SS VALVE ACTUATOR--POSITIOtl---
Revision   4
EXER.TYPE TYPE NORHAL FAILED FREQ.UDUDD RDDDDDDD DDDDDUURRDIIDD CURDS GT Ha Na FAI Q SSS CS S SC SC DS TEST caoE NaTES C RELIEF REQUESTS UDDDDUDSD DSDIIDSDDDD DDDDDDDUDII GHJ~~~~~4 20 RCIC-V-111 2 tl519 CK SA NC tlA Q~H~~~~~~2~4A RC I C-V-1 12 2 f7 C tlS I 9 CK BA NC NA Q AH~~~~~2r4A RCIC-V-1 13 2 E6 8 tl519 GT tto Na FAI Q GHJ....~20 RCI C-V-184 F-P HS 1 GS tlAtl LC NA N...L tl519 RCI C-V-204 814 C 8 CK SA NC NA Q.H~.....tl519 RCIC-V-740 2 H5 F-P 1 tl519 GD tlAN LC NA N~~~~L~~~4 RC I C-V-742 1 Jh F-P tl519.75 GD HAN LC NA N~~~L~~~Rjtt-V-IOA 1 G12 FC tl529 24 CK SA Na NA C GH..L...1F 4 RFll-V-108 1 G5 FC tl529 24 CK SA t<a NA C GH~.are 1F 4 RFW"V-32A 1 G13 FC tt529-24 CK AO~SA Na NA GH~~L~~~1Frh 4 RFN-V-328 GS FC H529 24 CK AO~SA Na tlA C GH~~L~~~1F ah RFtl"V-bSA RFH"V-658 1 G13 tl52'9 1 G4 F H52'9 24 GT GT Ha tl 0 tla FAI C GHJ L~1F FAI C GHJ.L.~.1F 4r20 4I20 RHR-FCV-64A 2 C12 F 3 GD H521 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 F H521 2 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
: 2. Only those valves which are shutting  down a
'I~I E 4 I I'~
                                    ~~         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.
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 NUMBER CODE CLASS Aacaaaaasasaassla aaaa Daaas RHR-AV 18 LOCAT I ON OW Pt ID sasasaas H5 M521 2 VALVE CATEGOAY saaaacssa FC SIZE IN VALVE INCHES TYPE as'Daalaal DICDCIS.75X1.5 RV ACTUATOA TYPE a aa CI aa s 0 a aa SA--POSITION---
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.
NOAtIAL FAILED~I 0 0 D 0 s Ic a 0 D s 0 0 tIC NA EXER FAEQ.0 Ia 0 s la N TEST CODE NOTES RELIEF AEQUESTS 0 D 0 a A IC 0 0 s~...~P..Dsssallasas ADDSDDDasD RHR-RV-5 RHR-RV-25A RHR-RV-259 CB FC IX2 RV SA NC NA N.....P..9 tl521 1 2 D10.FC 1X2 RV SA NC NA tk~~.~~P tl5 2 1 1 C10 FC IX2 RV SA.NC NA N.....P..9 M521 2 RHR-RV-25C EB tl5 2 1 2 FC IX2 RV SA NC NA N...P..9 RHR-RV-30 C4 FC-P I X2 RV SA NC NA N...L...4 M521 2 RHR-RV-3b 2 F12 FC-P tl521 1 b X 8 AV SA NC NA N~~~~L~~~RHR-RV-BBA 2 C7 M521 I FC.75 X 1 AV SA NC NA N RHR-RV"888 BB~75 X I RV SA NC NA N....~P..9 tl521 2 RHR-RV-BBC 2 DB FC.75 X I RV SA NC NA tl521 2 N~~~~~P~~RHR-V-3A 2 HID 8 18 GT MO tIO FAI 0 M521 GHJ~~~~~20 RHR-V-38 J9 8 18 GT MO M521 2 NO FAI Q GHJ.....20 RHR-V"4A Bb F 24 GT MO NO fAI Q GHJ L M521 1 4I20 RHR"V-49 912 F 24 GT MO tl521 2 NO FAI 0 GHJ.L~..4I20 RHR-V-4C 2 811 F 24 CT MO NO fAI Q tl521 2 GHJ~L~~~4'0 AHR-V-bA 2 98 8 18 CT MO NC FAI Q M521 I CH J~~~~~20 AHA-V-b9 97 tl521 I 18 CT MO NC FAI 0 CAJOLE~.~.20 AIIA-V-8 Eb II I~I 20 GT MO NC FAI C GHJ L..IC 4I20 E a c.I II F 4 II N I*I IL II'1'1 e 1 I!I'I I+I MHP-2 PUHP AHD VALVE IHBERVICE TEST PROGRAM-VALVE TEST TABLES Revision 41 Page 4.4-33 QDQccccrc QcarrrQClQC VALVE tlUtlDER s Qaacaacra scrrDrr DD RHR-V-9 arras CODE CLASS caa D sauaraaa I.OCAT Intl Otl Vain asaaaaaa D5 N521 I cesar aa VALVE CATEGORY DQDQDDDQ aaaacaaa S I ZE I tl I NCIlES rasascsc 20 csaQc VALVE TYPE Caaa-GT aaarracas ACTUATOR TYPE sacass a Q c D rr D D c a D a c a-"POSITION---
: 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.
NORIIAL FAILED Qsaaaaasacc a NC FAI alaaDQ EXER.FREQr asses C aascarraaa Dcsassrrsaa rS c a D s s a a a CHJ.L...D D a rr D c a D D a IC TEST CODE tlOTES D a ar a a rs a r a rs RELIEF REQUESTS Drsaraaacrass 4r20 RHR-V-IIA RIIR"V-I I B El I F"P 4 GT HO LC NA N....L...4 tl521 I 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 tl52 I I 4r20 RHR"V-16B DIO F 16 tl521 2 GT tlO NC FAI Q GHJ~L~~~4r20 RHR-V-17A Hh II 521 F 16 HO NC FAI 0 GHJrL.r.4r20 RHR-V-17D Dll F 16 CT tlo NC FAI Q CHJ.LE~tl521 2 4r20 RHR-V-21 E7 N521 F ls GD IIO tlC FA I.0 GH J L.~.2 4r20 RHR-V-23 K13 T 6 CB HO NC FAI C CHJ.LE~~H521 2 IC 4r20 RHR-V-24A EI 0 F 18 GD t1521 I HO NC FAI 0 GHJ L~4r20 RHR-V-24B RHR-V-27A C10 H521 2 D7 F tl521 I IS CB HO NC FAi 0 CHJ L..~4r20 6 GT HO NC.FAI Q CHJ LE~~4'0 RHR-V-278 DIO F 6 tl521 2 CT tin NC FAI Q CHJ~L~~~4~20 RHR-V-31A D14 tl521 I CK NC NA 0.H.~.~RHR"V-31B RIIR-V-3 I C H521 2 D5 C tl521 2 la IS CK SA NC NA Q.H CK SA NC NA 0.H...r..RHR"V-40--r-"---C4 D tl521 2 4 CD tI0 NC FAI 0 CHJ.....20 RHR-V-41A G5 TC 14 CK AOrSA tlC tlA I CH~.LE~~4o 9 tt'tD I I I
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


MNP-2 PUMP AND VALVE INSERVICE TEST PROGRAM-VALVE TEST TABLES Revision 4t Page 4.4-34 44S4CQCSQCCSSCQQSCCQ VALVE tlUtlDER 4-ar 4 aa 4 4 4 Q 4 ra o ar 4 aa-Q 4 4 4 RHR-V-4 I D CCCDS CODE CLASS aaosoa I~a 4 4 4 D aa ai 4 LOCATION Otl PIII 9 CQC DQCQ G13 t1521 2~I 4 ra 5 4 4 aa 4 VALVE CATEGORY cacccaac TC csaascscc scssD S I LE IN VALVE 1NCHES TYPE cc 4 5 Q ccccar 14 CK Q 4 4 4 a 4 4 aa ACTUATOR TYPE Qoracccss AOrSA aacscsscsscasaa
I I
-"POSITION---
    ~ TT I
NORtlAL F A I LED saacaaaQsc arQQ NC NA SSQSS EXER.FRED.CCCCC I 4 s 4 4 4 4 Q af s QCCCQQCSQS TEST CODE NOTES acsarsaaca GH..LE ccs csaass CCQSCDSDCS RELIEF REQUESTS QQcscD44raa 4r 9 RHR-V-4 I C RHR-V-42A G7.T tl521 I 14 GT IIO NC FAI C GHJ.L...IL 4r20 RHR-V-428 I G12 T 14 GT IIO NC FAI C GH Jr L~.~IL tl521 2 4r20 RHR-V-42C I El I T H521 2 14 GT HO NC FAI C GHJ.L..IL 4r20 RHR"V-46A 2 C10 C H521 I CK SA NC NA 0.H.~...~RHR-V-460 C6 C 6 CK SA NC NA 0.H.....r II 521 2 RHR-V-46C 2 ES tl521 C 6 CK SA NC tlA 0 AH.~~r~~RHR-V-47A J13 B tl521 I 18 GT tlO NO FAI 0 GHJ~~20 RHR-V-47B 2 J3 B 18 GT NO NO FAI 0 CHJ~~~~20 tl521 2 RHR-V 48A 2 Jl I D 18 GD NO NO FAI 0 GHJ~.~..tl521 20 RHR-V-488 2 JB D tl521 2 18 GD Ilo NO FAI Gll J~~~~~20 RHR-V"49 G4 D 4 GT HO NC FAI 0 GIIJ~~.~~20 tl521 2 I E13 TC 14 CK AOrSA NC tlA I'H..LE~6 4r 9 tl521 2'Q 4;r~r fI r~r.2, r.'.2 pr Ir r I rr~"~t RHR-V"50A F5 TC 12 CK AOrSA tlC NA I GH~L N521 RIIR-V-508 I F13 TC tl5 2 1 2 12 CK AO~SA NC tlA I CH.~L~~6 4r RHR-V-53A I Eb T 12 GT IIO NC FAI C GHJ L..IC 4r20 tl52 I I RHR-V-538---"-""""r--""----"--"-"--"-----"-"-"-"-"---"--"----I 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 I I HNP-2 PUllP AND VALVE INSERVICE TEST PROGRAH-VALVE TEST TABLES'0 R&Yi.sion 41 Page 4.4-35 r, s cseaaaaaaarrcaasscaaca VALVE NUtIBER QQUUUUQDescQQQSQDQQQD RHR-V-608 Scars CODE CLASS Qcrra 2 QacsaDDQ LOCATION Otl PhID s ee r r r c r c I I 8 H521 2 acacssacc VALVE CATEGORY aseaaeerra s a s ss s Q s c SIZE 1N 1NCHES rase rara.75 c s a ss a VALVE TYPE CDQQD SV ACTUATOR TYPE aaeeccscss SOL c a a c c a ss a ss a se a a--POSIT1ON---
IT T \ T  I
NORIIAL FAILED D c Q r es a se D a a Q D es NC FC SDSQQ EXERT FRED~SQacD 0 D c Q s es D s c s acaaasaaaa cassseaesaca GHJK.~~~aaacaassaaa TEST CODE NOTES csssaseaccaa RELIEF REQUESTS aaacsrsQDS ee RHR-V-68A 3 D13 D t1524 I lh GT HO NO.FA1 0 GHJ~....-20 RHR-V-68B RHR-V-73A R I IR-V-7 3 B RHR-V-75A RHR-V-75B 3 014.B 16 GT IIO NO FAI 0 GHJ.....20 tl5 2 4 2 H14 H521 I 2 GB IIO NC FAI 0 GHJ~L~~~4~20 H5 F 2 GB HO tIC FAI 0 GHJ~L~~~4'0 II521 2 2 Gl I B~75 SV SOI NC f C 0 GHJK.~~1 tl521 1 2 G9 B.75 SV SOL tIC FC Q GHJK~~~~1 II521 2 e.i" ge e r,''HR-V-84A RHR-V-848 2 D14 C 1.5 CK SA tIC NA 0.H......17=II521 1 2 B3 C I~5 CK SA NC NA 0 HE..~17 II 521 2 I ee RHR-V"84C C6 C tl5 2 1 2 1.5 CK SA NC NA~H~~~~~~17 RHR-V-85A 2 DI4 C II521 I I~5 SC SAetlAN NC NA 0.H RHR-V-85B~RHR-V-85C RHR-V-89 R I IR-V-1 I 5 D3 C I~5 SC SAVHAN NC tIA 0 H~.~tl521 2 Ch C 1~5 SC SAeHAN NC tIA 0 AH.~~~~tl521 2 JIO C 14 CK ADA SA NC NA 0 GH~~~~~~tl521 2 14 GT tIO NC FAI 0 GHJ....20 11521 2 RHR-V-116 RHR-V-120------r"""-"-"-" 2 Cl I F tl521 I-P 3 GT II AN LC NA.~~L..~J9 0 14 GB HO NC FA1 0 GHJ.~~~~II521 2 4 V t"~vr, RHR-V-121 2 Cll F-P 3 GT HAN LC NA N....L..~4~~,
I~f I P r k e~I r.k~J N, 1~f I 1 II~" y Ih I' Revision 41 Page 4.4-36 Q Q Q a C S S D D C Q D Q D Q D Q C D II VALVE IIUIIBER aellerallusaaaraauaallaa RHR"V-123A aaaaa CODE CLASS cucra I IeassDSDD cDsaasas LOCATION VALVE Otl PIIID CATEGORY C IIQQSQS Dauaa D E5 T H521 I aaaasacll Sl IE IN INCHES Dllulsaura VALVE TYPE CCQQD GT~I S S Il a Il D a ACTUATOR TYPE QCSCSDDD tlO s s s Q c c D Q el c D s Q--POSITION---
tIORHAL FAILED le D D D D C S D Q S Q C Q LC FAI Dallaa EXER.FREQ.SSSDD C QDDDSQSCD a D D S II S D D a D TEST CODE NOTES IIDDDDDD GHJ LE~~ISDQCQQSQS DQDDCSSQSQ RELIEF REQUESTS DCQSQCQSSD 4I20 RHR-V-1238 E13 II521 GT HO LC FAI C CHJ LE~IP 4I20 RHR-V-124A 814.F-P II521 1 1.5 HO LC NA~~~~L~~~RHR-V-1248 2 C12 H521 F-P 1.5 GB II 0 LC NA N~~~~L~~~RHR-V-125A 2 D4 t}521 F-P 2 GB LC NA....L.~~tlWP-2 PUIIP AND VALVE IHSERVICE TEST PROGRAH-VALVE TEST TABLES I 1 I}'I ts P4 I~S~I (t p'N I ts 3 I~e RHR-V-1258 RHR-V-13IIA RHR-V-1348 RHR-V-209 RRC-V-13A RRC-V-138 RRC-V-IAA RRC-V-I68 RRC-V-19 2 D3 tl521 F14 tl521 F5 tl521 D5 H5I21 C13 II530 813 II530 C14 II530 814 tl530 Fl 1 H530 F-P 2 tl0 LC NA N~~~~L~~~F 2 GB HO I FAI Q GHJ~L~~~4I20 TC~75 CK NC NA R.H.~L.~~4IS FC s75 CK SA tIO NA C~tl~.L~~~1 J FC.75 CK NO NA C.H.~L.s.1J e75 GT tIO FAI C CHJ~L..I J 4e20 F.75 GT HO tlO FAI C GHJ.L~~~1J 4e20 F~75 SV SOL NC FC Q CHJKL~I le 4 F 2~GB tIO NC FAI Q CHJ.L~..4 20 2 se t t\i'I I-.}'S',t lt I":I\r..s RRC-V-20 F12 tl53 0 75 SV SOL NC FC 0 CHJKL~~~le 4 RWCU-V-I F15 tl523 GT tI0 tI0 FA I C-GHJ~L...IN 4e20 RHCU-V-4 RIICU-V-40 I E15 tl523 Hl I~~~I F h CT GT II 0 tl0 NO FAI C GHJ.L...1N NO FAI C GHJ.L...IN I 4e20 4e20 C I, il I li~>1 I, I h I I'l kI%I I.)Ih'I I II I 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 VALVE NUIIBER 4 4 sa 4 a 4 a 4 a a 4 4 a 4 Is a sa aa 4 a-BA-V-109 4 4 c la aa CODE CLASS ss aa 4 4 4 4 4 4 4 4 4 ca 4 LOCATION ON PhID 4 4 c 4 4 4 sa 4 Jb tl510 aaaccaass VALVE CATEGORY araacaaa F-P 44444444 S I LE IN INCHES Caasaaaa VALVE TYPE 4 Q 4 4 ca GT ssaccsaaa saaaasaaaaassass ACTUATOR--POD IT I ON---TYPE NORtlAL FAlLED~saaaaasaua Qaaascaaasaaaasa tlAN LC NA EXER.FRED.aacsaa tl 4 a s ca 4 a ca=cs aaascaaa 4 Qaaaaaaca~~~~L~~~caaaaaaacc TEST CODE NOTES saacaaaaaaa RELIEF REQUESTS aacaaaaccaaa SLC-RV-29A E6 C tl522 I X 2 RV SA NC tlA tl.....P SLC-RV-298 2 D6 tl522 C I X 2 RV SA tlC NA N.....P~.SLC-V-IA 2 E4 8 4 GD HO NC FAI 0 OH'..20 tl5 2 2 SLC-V-18 D4 tl522 8 4 GB tlO NC FAI 0 GHJ.....20 SLC-V-4A SLC-V-48 SLC-V-6 I FS FD I~5 SHEAR EXPL NC NA N....L.V.4 t1522 I DS FD I~5 SHEAR EXPL NC NA N...L.V.tIS22 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 tI522 I~5 CK BA NC tlA 0~H~~~~~~SLC-V-338 D7 C I~5 CK SA NC NA H522 0~H~~~~~~SW-RV-IA Sff-RV-18 Sff-TCV-IIA C14 C I RV'A NC tlA N~~P N524 I FI 4 C RV SA NC NA tl~~P~~tl524 2 G5 8 2'GB HO NT FO 0.II.K.~~22 II775 SW-TCV-118 Sff-TCV-15A Cb 8 2'GD HO NT FO 0 IH~K~~ll7 7 5 J10 8 2~5 GD HO tlT FO 0.H.K---~tl7 7 5 22 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 VALVE NUtlBER cccscscaapcarcscsssscas Sll-V-I 8 caracas CODE CLASS acres 3 LOCATION ON ParD saa caaaa C5 tl524 2 VALVE CATE CORY caacaaa-saaacssassa asssascasa aaaaassa SIZE IN INCHES apc c a 20 a s c s aa VALVE TYPE acsaa CK ss a ca aa s ac r sa ACTUATOR TYPE scsssaas SA s s c a as s a c s c s s a arras aacsasaasa RELIEF REQUESTS--POSITION---
Pg~
EXER.NORtlAL FAILE D FREG.rcrsasaascsss asasaa NC NA 0 TEST CODE NOTES sc ss c a ca c s c aa~H~~~~~~sssaaacaaac ccasaaaaass aaassssaassssas ssasaasaas SW-V-2A 3 H6 9 20 BF NO NC FAI N524 I 0 GHJ.cc.20 SW-V-28 G6.B 20 BF NO NC FAI 0 CHJ..N524 2 20 SW-V-4A 3 E9 9 8 CT tlO NO FAI 0 GHJ.....20 tl524 1 SW-V-4B G9 N524 9 8 GT NO NO FAI G GHJ.~..20 2 3 F7 9 8 GT tlO NO FAI G GHJ...~20 tl524 1 SW-V-12A G3 N524 9 18 GT NO tIC FAI 0 GHJ.~~.20 1 SW-V-128 G3 tl5 2 4 2 18 GT NO NC-FAI 0 GHJ....20 SW-V-24A G9 9 2 CT NO NO FAI 0 CHJ.~c.N524 1 20 SW-V-249 f10 tl524 9 2 CT NO NO F*l 0 GHJ....20 2-SW-V-24C K10 9 N524 2 2 GT NO NO FAI 0 GHJ.....20 SW-V-29 C6 9 8 11524 1 tlD NC FAI 0 CHJ~~~~~20 BW-V-34 Cl 1 B 1~5 GB SOL N524 2 NO FO 0 GHJK....1 SW-V-44 E9 9 2 GT NQ NO FAI 0 GHJ....20 N524 1 SW-V-54 F7 B 2 GT tlO NO N524 FAI G GHJ.....20 SW-V-75A A13 tl5 2 4 I 2 NO tIC FAI 0 GHJ~~~~~20 SW-V-759 Bl 4 N524 r---"-"-"-""""""--""-"""-"-""""-"--"--"--"-""--"-""----"---"------------9 2 GD NO tIC FAI 0 GHJ...~20 2 SW-V-187A G14 9 6 CT NO NO FAI 0 GHJ..c..3 20 6 C g'1 II'F I N I tf J'1 1 0 y.g l'IA h tl 4 WHP-2 PUIIP AND VALVE INSERVICE TEST PROGRAH-VALVE TEST TABLES Revision 41 Page 4.4-39 4~'caassaaaaaaagaaasssgasa VALVE IIUIIBER ss D a a a ss a a g a sa ss a a ss a a c Q Q SH-V-1878 SII-V-188A SW-V-188B SII-V-223A Sll"V-2238 a as as sa sa CODE CLASS Q QCD~s ss Q a a a a ss LOCATION ON PI(ID DCQD a a C13 tl524 2~S SS Q S Sj ja Sj Sa VALVE CATEGORY DCDCCQDC ssaaaacg SI2E 1N 1 tICHES jr ass ja jr asDsr aagg-VALVE TYPE csssca GT~saaasaaaa ACTUATOR TYPE jsaasajjagc tlO aaaaggaagggaa
R bivalve.
--POSIT10N--
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.
NORNAL FAILED EXERT FREOr TEST CODE NOTES S D a sj D Q a a Q aaaaaaaaag QDDCQDQQD js gccaaaasa asscasasaacgaa js casaca tIO FA1 8 GHJ-~~-~3 DQDDQSSDCD RELIEF REQUESTS aaaaaaaaca 20 3 H13 8 6 GT IIO NO FAI N521 I OH'...20 D12 B 6 GT IIO tlO FAI 0 GHJ....20 tl524 2------------I 3 K5 C 3 CK SA NC tIA 0.H~.....N775 3 E5 C 3 CK SA NC NA 0~H~~~...N775 4 44 4 (4(4 r,s SH-V-226A F7 C N775 CK SA NC NA~H~~~~~~SII-V-2268 3 Bh C 3 CK S*NC NA 0.H...~..M775 SII-V-'t3 IA SII-V-9318 TIP-V-I T1P"V-2 T1P-V-3 T1P-V-4 s j 3 K4 C II524 I I CK SA NO NA 0~H~~~~~~J4 II524 C 1 CK SA NO NA 0 AH...~2 2 GH12 F.375 II604 BALL SO NC FC CHJKL..~Ir 4 2 GH12 F N604~375 BALL SO tlC FC 0 CHJKL~1~4 GH12 F.375 BALL SO NC FC 8 CHJKL~~~I~4 II604 CH12 F.375 BALL SO NC FC 0 CHJKL~~~I~4 tlb04'I s j*s 4 4(T1P-V-5 2 CH12 F.375 BALL SO NC FC tlb04 8 GH JKL~~~Ir 4 TIP-V-6 GI I 1 2 F C I CK SA NO tIA 1.H..L~..4r 11 tlb04 T IP-V-7 CHI 2 II604 FD.375 SHEAR EXPL NO FO N..~...V.4 TIP-V-8 CH12 FD tlb04.375 SHEAR EXPL NO FO N~~~~~~V~TIP-V"V GI I I 2 FD.375 SHEAR EXPL NO FO..~.~~V.s h 1 H C l5~p=e'I t ll~*
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).
WHP-2 PUHP AND VALVE INBERVICE TEST PRtjGRAH-VALVE TEST TABLES Revision 41 Page 4.4-4Q gauaaaaaaassacaaaaaass VAI.VE tlUtlDE R sscssaaraaccrggagaaarss TIP-V-10 CODE CLASS~'ag 2 a g ss ss a a ss ss LOCATION ON PtsID~scggoccc GH12 t1604 a a r a-ss r ss VALVE CATEGORY gcassrgcr FD caaacaaa SITE IN INCHES cg c aaa.3l5 arear VALVE TYPE cager SHEAR araaacga ACTUATOR TYPE arssssgaaa EXPl~sggrgagaggaaa
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 ~
-POSIT ION"-NORtlAL FAILED ssssaaaccass-agg NO FO EXER.FREQ~ss ac r N aaraaagga aassacacaar cccgrara~~~~~V~a ss ss ss ss ss a ss a ss TEST CODE NOTES a r ss a a a a ss a a RELIEF REQUESTS racgcgarga 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...tt 604 ls 4 TOTAL COUNT 597 P,*I fl'E~-~~E I' 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).
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.
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.
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.
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.
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.
Valves that cannot be exercised during plant operations shall be specifically identified by the Owner and shall be full-stroke exercised during cold shutdowns.
These valves are not listed under Relief Request RV-4.
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.
HPCS-RV-14, 35 LPCS-RV-18, 31 RHR-RV-lA, 1B., 5, 25A, 25B, 25C, 88A, 888, 88C
The testing of these valves shall commence immediately (within 48 hours)following the establishment of cold shutdown conditions in accordance with the owner's established schedule.Testing shall continue only as long as the plant is scheduled to be in cold shutdown to perform required maintenance.
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 RHR-V-9 RHR-V-23 RHR-V-53A, 8 1, A 1, A 1, A 1, A Isolation valves in RHR shutdown cooling suction line from recirculation loop A RHR supply to vessel head spray 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 RCC-V-21 RCC-V-40 RCC-V-104 2, A 2, A 2, A 2, A Isolation valves for reactor closed cooling water lines gg~ifi~i~n
-Closure 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.


Qg~~I.~Fn~in Page~4-4~Revision 4 RFH-V-10A, 8 RFH-V-32A, 8 RFH-V-65A, 8, 1, A-C 1, A-C 1, A Reactor feedwater inboard check valves Reactor feedwater outboard check valves 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.
1
2)Category A-C valves are held open by feedwater flow and cannot be closed during power operations.
            'I 4
G)V v HY-V-17A, 8 HY-V-18A, 8 HY-V-19A, 8 HY-V-20A, 8 HY-V-33A, 8 HY-V-34A, 8 HY-V-35A, 8 HY-V-36A, 8 Gmh.~Em~i 2, 8 Valves provide hydraulic control fluid to the 2, 8 reactor recirculation flow control valve 2, 8 hydraulic operators.
I k
Recirculation.flow 2, 8 control valves are RRC-V-60A and RCC-V-608.
ll t
2, 8 2, 8 2, 8 2, 8 i~--E ii fii lyi i.:,.i y.p Iii g:f the reactor recirculation flow control valve, causing undesirable 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.
I
This is unsafe to do while the plant is operating.
                ~ L I
CI BL RRC-V-13A, 8 RRC-V-16A, 8 2, A-C 2, A Inboard and outboard isolation valves for the 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.t\1d i 1pp i h possibility of an intersystem LOCA.L)CadeMi.~F LPCS-V-5 1, A RHR-V-42A,B,C 1, A LPCS discharge isolation to the reactor vessel.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.
10.
II>~Ce~CIA-SPV-18-198 3, B CIA-SPV-1A-15A 3, 8 CIA-V-52A-66A 3, C CIA-V-52B-70B 3, C Emergency nitrogen supply isolation valve, Emergency nitrogen supply check mode.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 RNCU-V-4 RHCU-V-40 1, A 1, A 1, A Containment Iso., RHCU Pump Suction Iso.Containment Iso., RHCU Pump Suction Iso.Containment Iso., RHCU Pump Discharge Iso.J~-".">>d overheating of the pumps, significantly increasing the potential for equipment damage.GL~F RHR-V-123A RHR-V-1238 1, A 1, A CIV, HI-LO Pressure Iso.CIV, HI-LO Pressure Iso.Justifi~iog
These    rupture discs are of is required per IHV-3620.
-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.
a nontestable design.
'a~s r I e I k 0~I I II'I
II ~
~F~in Page 4.4-44 Revision 4 HSLC-V-2A HSLC-V-3A HSLC-V-28 MSLC-V-38 HSLC-V-2C MSLC-V-3C HSLC-V-20 HSLC-V-30 HSLC-V-4 MSLC-V-5 HSLC-V-9 HSLC-V-10 1, 8 1, A 1, 8 1, A 1, 8 1, A 1, 8 1, A 2, 8 2, 8 2, 8 2, 8 Prevent Radioactive Material Release CIV, Prevent Radioactive Material Release Prevent Radioactive Material Release CIV, Prevent Radioactive Material Release Prevent Radioactive Material Release CIV, Prevent Radioactive Material Release Prevent Radioactive Material Release CIV, Prevent Radioactive Material Release Prevent Radioactive Material Release Prevent Radioactive Material Release Prevent Radioactive Material Release 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:
Revision   4 Therefore; no testing CAC-RD-1A, 1B CCH-RD-1A, 18 RCIC-RD-1,2
(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 ifi 2, 8 Isolation Valve, Main Steam Supply to Auxiliary Equipment This valve is normally open at power.Closing this valve at power would isolate steam from the following equipment.
: 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.
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.
V~lv                                                 ~@&Per          i 1 HCU-114                   Check vlv to scram hdr       4.1.3.2 (a, b, 5 c)
V t W F~V'I t I~'Y r I I 4 I V l h II t't II'~Revision 4 2.Only those valves which are~~to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident are required to be tested per Subsection IWV of the Code.Using this criteria the following valves are not re-quired to be tested per Subsection IWV, but due to their functional importance are included in the valve list at the Owner's discretion.
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)
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 I I~TT I IT T\T I Pg~R The valve actuator was installed to facilitate stroke testing of the bivalve.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.
HCU-127                  Hithdraw AOV                    4.1.3.2 (a, b, & c)
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 1'I 4 I k ll t~L I I II~Revision 4 10.These rupture discs are of a nontestable design.Therefore; no testing~is required per IHV-3620.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 HCU-114 HCU-115 HCU-126 HCU-127 HCU-138 Check vlv to scram hdr Charging wtr ck vlv Drive water AOV Hithdraw AOV Cooling wtr ck ylv~@&Per i 1 4.1.3.2 (a, b, 5 c)4.1.3.5.b.2 4.1.3.2(a, b, 5 c)4.1.3.2 (a, b,&c)4.1.3.1.2.a
HCU-138                  Cooling wtr ck ylv              4.1.3.1.2.a


==Reference:==
==Reference:==
 
SER Appendix.B, item   15
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
: 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.
-5A-5A-5A-5B-5B-5B-5B-5C-5C 1/2 1/4 2/2 2/4 1/2 1/4 2/2 2/4 1/1 1/2  
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:==
==Reference:==
SER Appendix B, item 14


SER Appendix B, item 14 J'W Pg~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.  
J'W Pg~
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.


P Il~Revision 4 RELIEF REQUEST NO.RV-1 m Various Rapid acting valves.(Applies to Open Position, Closed Position or Both Positions.)
RELIEF REQUEST NO. RV-1 P  Il ~
Corrective action based on an increase in stroke time (INV-3417(a)).
Revision    4 m
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.
Various Rapid acting valves.       (Applies to   Open Position, Closed Position or Both Positions.)
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);
Corrective action based     on an   increase in stroke time (INV-3417(a)).
li f The corrective action based on an increase ln stroke time (per 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.
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  
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:==
==Reference:==
3.1.1.1 Relief request is granted      as  requested.
t
    'I
              ~L E
a l
P
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.


3.1.1.1 Relief request is granted as requested.
It TABLE RV-1 (CONTINUED)
t''I~L E a l P Revision 4 TABLE RV-11 V CAC-FCV-1A CAC-FCV-1B CAC-FCV-2A CAC-FCV-2B CAC-FCV-3A CAC-FCV-3B CAC-FCV-4A CAC-FCV-4B CSP-V-93 CSP-V-96 CSP-V-97 CSP-V-98 2 2 2 g*2 Hydrogen Recombiner Flow Control 5 Isolation'ydrogen Recombiner Flow Control 5 Isolation Hydrogen Recombiner Flow Control 5 Isolation Hydrogen Recombiner Flow Control 5 Isolation Hydrogen Recombiner Flow Control&Isolation Hydrogen Recombiner Flow Control 5 Isolation Hydrogen Recombiner Flow Control 5 Isolation Hydrogen Recombiner Flow Control 5 Isolation Containment Isolation Containment Isolation Containment Isolation Containment Isolation 1.For information only.Not part of relief request.
V   lv                                         n P
It P II~Rev i sion 4 TABLE RV-1 (CONTINUED)
Rev II  ~
V lv n'P I-VX-251 P I-VX-250 PI-VX-253 P I-VX-256 P I-VX-257 P I-VX-259 P I-VX-262 P I-VX-263 P I-VX-264 P I-VX-265 P I-VX-266 PI-VX-268 P I-VX-269 Radiation monitor RAD-RE-12B inlet valve Radiation monitor RAD-RE-12B outlet valve Radiation monitor RAD-RE-12B outlet valve Radiation monitor RAD-RE-12A inlet valve Radiation monitor RAD-RE-12A inlet valve Radiation monitor RAD-RE-12A outlet valve Hydrogen-oxygen monitor sample iso.valve Hydrogen-oxygen monitor sample iso.valve Hydrogen-oxygen monitor sample iso.valve Hydrogen-oxygen monitor sample iso.valve Hydrogen-oxygen monitor sample iso.valve Hydrogen-oxygen monitor sample iso.valve Hydrogen-oxygen monitor sample iso.valve PSR-V-X73-1, 2 PSR-V-X77A1, 2 PSR-V-X77A3, 4 PSR-V-X80-1, 2 PSR-V-X82-1, 2 PSR-V-X82-7, 8"'2=''" PSR-V-X83-1,2 PSR-V-X84-1, 2 PSR-V-X88-1, 2 A A A A A'A A A A Containment Containment Containment Containment Containment Containment Containment Containment Containment Isolation Isolation Isolation Isolation Isolation Isolation Isolation Isolation Isolation RHR-V-60A RHR-V-60B RHR-V-75A RHR-V-75B RRC-V-19 RRC-V-20 SH-V-34 TIP-V-1 Tjp-V-2 TIP-V-3 TIP-V-4 TIP-V-5 TIP-V-15 Loop A sample (inboard)Loop B sample (inboard)Loop A sample (outboard)
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)
Loop 8 sample (outboard)
RHR-V-60B                 Loop B sample  (inboard)
Reactor recirculation sampling Iso valve.Reactor recirculation sampling Iso valve.Cooling Hater Isolation Containment Isolation Containment Isolation Containment Isolation Containment Isolation Containment Isolation Containment Isolation  
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 Valve(s)ASHE Classification Function Standby Liquid Control (SLC)SLC-V-6, SLC-V-7 Code Class: 1 Category'.
RELIEF REQUEST NO. ~V-System                   Standby Liquid Control (SLC)
B-C (SLC-V-6)A-C (SLC-V-7)Standby Liquid Control discharge to reactor vessel.Code Testing Requirement 1.Quarterly exercising (INV-3521) 2.Cold shutdown exercising (INV-3522)
Valve(s)                  SLC-V-6, SLC-V-7 ASHE                    Code   Class: 1                 Category'. B-C (SLC-V-6)
Basis for Rel i ef 1.Valves have no operator with which they may be stroked.2.Exercising the valves require the initiation of the SLC system and full flow injection into the reactor vessel.Initiation of SLC flow involves the discharge of Category 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.
Classification                                                        A-C (SLC-V-7)
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 lOCFRSO Appendix J (Type C)testing.The proposed testing complies fully with the intent of the Code (INV-3522).
Function                Standby Liquid Control discharge     to reactor vessel.
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  
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:==
==Reference:==
3.4.1.1 Relief granted      as requested'


3.4.1.1 Relief granted as requested' N
N System RELIEF REQUEST NO. ~V-Containment Instrument    Air P II ~
P II~Rev)s)on 4 System Valve(s)ASME Classification Function RELIEF REQUEST NO.~V-Containment Instrument Air Valves affected by this rel)ef request are)dentif)ed)n Table RV-3.Code Testing Requ)rement quarterly testing (INV-3412)
Rev) s)on   4 Valve(s)
Basis,.for Relief 2.The CIA-V-40 series check valves are located)ns)de the conta)nment and are)naccess)ble during power operations.
ASME                   Valves affected by   this rel)ef request are )dentif)ed     )n Classification          Table RV-3.
There is no way to remotely isolate the valves and observe the pressure decay of.the accumulators.
Function Code   Testing         quarterly testing (INV-3412)
There)s no local or remote position indication for these check valves.Alternate Testing 1.to be Performed 2.During refueling outages, pressure decay tests w)11 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.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).
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.
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  
: 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:==
==Reference:==
3.9.1.1., 3.9.1.2 Relief granted    as requested.


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).


R TABLE RV-3 CIA-V-31A'IA-V-31 B A-C A-C Instrument air supply to ADS valves (outside containment)
1 b
CIA-V-40 H, N, 2 P, R, S, U, and V A-C Instrument air to ADS Accumulators (inside containment)
 
CIA-V-21 A-C Instrument air supply to containment (outboard check valve).
P9~
1 b P9~Revision 4 REQUEST FOR RELIEF NO.gV-4 System, Valves, Category A, Containment Isolation Valves.and ASME Classification Function Code Testing Requirement Basis for Relief Containment Isolation Leak Test Requirements (INV-3420)
Revision       4 REQUEST FOR RELIEF NO.     gV-4 System, Valves,         Category A, Containment Isolation Valves.
The purpose of leak rate testing is, ultimately, to assure that the limits of 10CFR100 are not exceeded.Hence the~v~leakage from the containment is the critical parameter in leak rate testing, not individual valve leak 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, to be Performed These valves wi 11 be leak tested according to 10CFR50, 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-4.1/fe 2.3.NNP-2 wi 1 1 specify a perm)ssible leakage 1 imi t based on valve type, size and equipment history for those valves being Type C leak tested.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).These valves are all category A valves and whether active or passive perform a common safety function of containment isolation.
and ASME Classification Function               Containment    Isolation Code   Testing         Leak Test Requirements       (INV-3420)
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  
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:==
==Reference:==
3.1.2 1, 3.1.3.1
                                ~
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.


3.1.2~1, 3.1.3.1 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.
'I 4
'I 4~'II c.7 C Ih 0 II~Revision 4 TABLE RV-41 CAC-FCV-1A CAC-FCV-18 CAC-FCV-2A CAC-FCV-28 CAC-FCV-3A CAC-FCV-38 CAC-FCV-4A CAC-FCV-48 CAC-V-2 CAC-V-4 CAC-V-6 CAC-V-8 CAC-V-11 CAC-V-13 CAC-V-15 CAC-V-17 CAS-V-730 CAS-VX-82e CEP-V-1A CEP-V-18 CEP,.V-2A CEP-V-28 CEP-V-3A CEP-V-38 CEP-V-4A CEP-V-48 CIA-V-20 CIA-V-21 CIA-V-30A CIA-V-308 CIA-V-31A CIA-V-31 8 CSP-V-1 CSP-V-2 CSP-V-3 CSP-V-4 CSP-V-5 CSP-V-6 CSP-V-7 CSP-V-8 CSP-V-9 CSP-V-10 CSP-V-93 CSP-V-96 CSP-V-97 CSP-V-98 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2~2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2.2'2 A A A A A A A A A A A A A A A A A A A A A A A A A A A AC A A AC AC A A A A A A AC AC A AC A A A A V v DW-V-156 DW-V-157 EDR-V-19 EDR-V-20 FDR-V-3 FDR-V-4 FPC-V-149 FPC-V-153 FPC-V-154 FPC-V-156 HPCS-V-4 HPCS-V-5 HPCS-V-12 HPCS-V-15 HPCS-V-23 HPCS-V-65 HPCS-V-68 HY-V-1/A HY-V-178 HY-V-18A HY-V-188 HY-V-19A HY-V-198 HY-V-20A HY-V-208 HY-V-33A HY-V-338 HY-V-34A HY-V-348 HY-V-35A HY-V-358 HY-V-36A HY-V-368 LPCS-FCV-11 LPCS-V-1 LPCS-V-5 LPCS-V-6~LPCS-V-12 LPCS-V-66 LPCS-V-67 MS-V-16 MS-V-19 MS-V-22A MS-V-228 MS-V-22C MS-V-22D 5!Itlh 2 2 2 2 2 2 2 2 2 2 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 2 2 2 1 1 1 1 1 1 A A A A A A A A A A A AC AC For information only-not part of relief request.
                ~
4 4 Ei 4~I 4~~4 4 4~4,~4 IE 4 4 4  
7 II c.
'll'~Revision 4 TABLE RV-4 (CONTINUED)
C Ih 0
Elks V lv Nm MS-V-28A HS-V-288 MS-V-28C HS-V-28D HS-V-67A MS-V-678 HS-V-67C MS-V-67D HSLC-V-3A HSLC-V-38 MSLC-V-3C MSLC-V-3D PI-EFC-X18A PI-EFC-X188 PI-EFC-X18C PI-EFC-X18D P I-E FC-X29b PI-EFC-X29f PI-EFC-X30a PI-EFC-X30f PI-EFC-X37e PI-EFC-X37f PI-EFC-X38a PI-EFC-X38b PI-EFC-X38c P I-EFC-X38d PI-EFC-X38e P I-EFC-X38f PI-EFC-X39a P I-EFC-X39b P I-EFC-X39d P I-EFC-X39e P I-EFC-X40c PI-EFC-X40d PI-EFC-X40e P I-EFC-X40f PI-EFC-X41c P I-EFC-X41d P I-EFC-X41e P I-EFC-X41 f P I-E FC-X42a P I-E FC-X42b P I-EFC-X42c P I-EFC-X42f PI-EFC-X44Aa PI-EFC-X44Ab A.A A A A A A A A A A A 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 I 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 2 2 1 1 2 2 1 1 A A A A A A.A A A A A A AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC PI-EFC-X448g PI-EFC-X448I1 PI-EFC-X448]
P I-EFC-X448IQ P I-EFC-X4481 P I-EFC-X448m PI-EFC-X61a PI-EFC-X61 b PI-EFC-X61c PI-EFC-X62b PI-EFC-X62c P I-EFC-X62d P I-EFC-X66 PI-EFC-X67 PI-EFC-X69a PI-EFC-X69b PI-EFC-X69e P I-EFC-X69f PI-EFC-X70a PI-EFC-X70b P I-EFC-X70c PI-EFC-Xjod PI-EFC-X70e P I-EFC-X70f PI-EFC-X7la P I-EFC-Xj 1 b PI-EFC-X71 c P I-EFC-X71 d PI-EFC-X71 e PI-EFC-X71 f 8 8 8 8 8 8 P I-EFC-X44Ac PI-EFC-X44Ad P I-EFC-X44Ae PI-EFC-X44Af PI-EFC-X44Ag PI-EFC-X44Ajl P I-EFC-X44A]
PI-EFC-X44Ak P I-EFC-X44A1 P I-E FC-X44Am PI-EFC-X448a PI-EFC-X448b 8 PI-EFC-X448c 8 PI-EFC-X448d PI-EFC-X448e PI-EFC-X448f 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 1 1 2 2 1 1 1 1~1 1 1 1 1 1 1 1 1 1 1 1 AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC h
Pg~Rev)sion 4 TABLE RV-4 (CONTINUED)
V v PI-EFC-X72a PI-EFC-Xjzf P I-EFC-X73a PI-EFC-X73e PI-EFC-X74a PI-EFC-X74b PI-EFC-X74e PI-EFC-X74f PI-EFC-X75a PI-EFC-X75b PI-EFC-X75c PI-EFC-X75d PI-EFC-X75e PI-EFC-X75f PI-EFC-X78a PI-EFC-X78b P I-EFC-X78c P I-EFC-X78f P I-EFC-X79a P I-EFC-X79b P I-EFC-X82b.
PI-EFC-X84a P I-EFC-X86A PI-EFC-X86B P I-EFC-X87A P I-EFC-X878 P I-E FC-X106 P I-EFC-X107 PI-EFC-X108 PI-EFC-X109 P I-EFC-X110 P I-EFC-X111 PI-EFC-X112 PI-EFC-X113 PI-EFC-X1,14 PI-EFC-X115 P I-EFC-X119 Pr-V-X42d P I-V-X54Bf P I-V-X61 f P I-V-X62 f P I-V-X69c P I-VX-216 P I-VX-218 PI-VX-219 P I-VX-220 Gln.z AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC ,AC A A A A A A A A A P I-VX-221 P I-VX-250 P I-VX-251 PI-VX-253 PI-VX-256 P I-VX-257 PI-VX-259 PI-VX-262 PI-VX-263 PI-VX-264 PI-VX-265 PI-VX-266 PI-VX-268 PI-VX-269 PSR-V-X73-1 PSR-V-X73-2 PSR-V-X77A1 PSR-V-X77A2 PSR-V-X77A3 PSR-V-X77A4 PSR-V-X80-1 PSR-V-X80-2 PSR-V-X82-1 PSR-V-X82-2 PSR-V-X82-7 PSR-V-X82-8 PSR-V-X83-1 PSR-V-X83-2 PSR-'-X84-1 PSR-V-X84-2 PSR-V-X88-1 PSR-V-X88-2 RCC-V-5 RCC-V-21 RCC-V-40 RCC-V-104 RCIC-V-8 RCIC-V-1 3 RCIC-V-1 9 RCIC-V-28 RCIC-V-31 RCIC-V-40 RCIC-V-63 RCIC-V-64 RCIC-V-66 RCIC-V-68 C 2 2 2 2 2 2 2 2 2 2 2 2 2.2 2 2 1 1 1 2 2 2 2 2 A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A AC A~AC A A AC A 1
Pg~Rev)s1on 4 TABLE RV-4 (CONTINUED) g'ELK kU Gl~Gaia~~~RCIC-V-69 RCIC-V-76 RCIC-V-184 RCIC-V-740 RCIC-V-742 RFW-V-10A RFW-V-108 RFW-V-32A RFW-V-328 RFW-V-65A RFW-V-658 RHR-FCV-64A RHR-FCV-648 RHR-FCV-64C RHR-RV-30 RHR-RV-36 RHR-V-4A RHR-V-48 RHR-V-4C RHR-V-8 RHR-V-9 RHR-V-11A RHR-V-118 RHR-V-16A RHR-V-168 RHR-V-17A RHR-V-178 RHR-V-21 RHR-V-23 RHR-V-24A RHR-V-248 RHR-V-27A RHR-V-278 RHR-V-41A RHR-V-418 RHR-V-41C RHR-V-42A RHR-V-428 RHR-V-42C RHR-V-50A RHR-V-508 RHR-V-53A RHR-V-538 RHR-V-73A RHR-V-738 RHR-V-I20 RHR-V-121 2 1 2 2 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2.1.1 2 2 2 2 2 2 2 1 2 2 2 2 1 1 1 1 1 1 1 1 1 2 2 2 2 A A A A A AC AC AC AC A A A A A AC AC A A A A A A A A A A A A A A A A A AC AC AC A A A AC AC A A A A A A RHR-V-123A RHR-V-1238 RHR-V-124A RHR-V-1248 RHR-V-125A RHR-V-1258 RHR-V-134A RHR-V-1348 RHR-V-209 RRC-V-13A RRC-V-138 RRC-V-16A RRC-V-168 RRC-V-19 RRC-Y-20 RWCU-V-1 RWCU-V-4RWCU;V-40 SA-V-109 SLC-V-4A SLC-V-48 SLC-V-7 TIP-V-1 TIP-V-2 TIP-V-3 TIP-V-4 TIP-V-5 TIP-V-6 TIP-V-7 TIP-V-8 TIP-V-9 TIP-V-10 TIP-V-11 TIP-Y-15 1 2 2 2 2 2 2 1 2 2 2 2.1 1 1 1 2 1 1 2 2 2.2 2 2 2 2 2 2 2 2 A A A A A A A A AC AC AC A A A A A A A A AD AD AC A A A A A AC AD AD AD AD AD A n~~k I 1~f 9~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.  
TABLE RV-41 V  v II 5!Itlh
                                                                  ~
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.


Revision 4 RELIEF REQUEST NO.~RV-System Valves ASME Classification Function Primary Containment Cooling and Purge CVB-V-1A, B, C, 0, E, F, G, H, J, K, L, M, N, P, Q, R, S, T Code Class: 2 Category: A-C To.break vacuum on the drywell to suppression chamber down-comers and imi 1 fr h wn Code Testing Requirement Basis for Re 1 i ef IWV-3420, Valve Leak Rate Test These check valves cannot be tested individual.ly, there-fore, assigning a limiting leakage rate for each valve is not practical.
4 4
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.
Ei 4 ~I  4
                ~  ~
4 4
4 4
~ 4, ~    IE                4 4
4
 
                                                        'll'~
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
 
h Pg~
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
 
1 Pg~
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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    ~ ~
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9~
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.
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  
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:==
==Reference:==
3.10.1.1 Relief granted      as requested.


3.10.1.1 Relief granted as requested.
4 fh 4 If
4 fh 4 If~~~~I h h 9~Revision 4 RELIEF REQUEST NO.3V-7 System Valves ASHE Classification Containment Instrument Air CIA-V-40M, N, P, R, S, U, V Code Class: 2 Category: A-C 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 Requirement l.IWV-3424, Seat Leakage Measurement.
            ~
Basis for Relief 1.These check valves can only be tested by the method 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.
h I
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  
h
 
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:==
==Reference:==
3.9.1.3 Relief granted    as requested.


3.9.1.3 Relief granted as requested.
lg H 4
lg H 4 Revision 4 RELIEF REQUEST NO.~RV-System Valves ASME Classification Function Residual Heat Removal RHR-V-209 Code Class: 1 Category: A-C Containment isolation and Reactor Coolant System Pressure Boundary and r u li f i in w n v v Code Testing Requirement Basis for Relief l.INV-3521, that each category C valve be exercised at least once every 3 months.1.This check valve is located inside the containment and does not have valve position indication or an operator of any type.It cannot be tested without interrupting RHR shutdown cooling flow.During power operations, access is prohibited.
 
During cold shutdown condi-tions, RHR cannot be out of service more than 2 hours per an 8 hour interval (per NNP-2 Technical Specifica-tion).Additionally, containment will not be de-inerted during all cold shutdowns.
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.
Al ternate Testing 1.Thi s check valve wi 1 1 be exerci sed at refuel ing out-to be Performed ages.Furthermore, thi s check val ve i s veri fi ed to shut by being leak tested at least once every 18 months per Technical Specification 4.4.3.2.2.
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 hours per an 8 hour interval (per NNP-2 Technical Specifica-tion). Additionally, containment will not be de-inerted during all cold shutdowns.
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).
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.
The proposed alternate testing avoids extraordinary testing efforts with inherent potential for violations of the NNP-2 Technical Specification.
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  
This   will provide   adequate   assurance   of material quality   and public safety.
N   A           /     D       M   7 SER/TER  


==Reference:==
==Reference:==
3.3.1.1 Relief granted    as requested.


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


P9~Revision RELIEF REQUEST NO.~System RCIC, HPCS, LPCS, and RHR.Qm.Gaimarz~F RCIC-V-65, 66 LPCS-V-6 HPCS-V-5 RHR-V-41A,B,C RHR-V-50A, 8 1 1 1 1 A-C A-C A-C A-C A-C RCIC discharge to the reactor vessel head LPCS discharge to the reactor vessel HPCS discharge to the reactor vessel RHR Loop A, 8, C discharge to the reactor vessel RHR Loop A, 8 discharge to the recircu-lating pump discharge Code Testing Requirement Basis for Relief l.INV-3521, that check valves be'exercised at least once every 3 months, except as provided by INV-3522.1.The Velan operation and maintenance manual for the 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 to be Performed 1.These check valves will be exercised with the reactor at cold shutdown and the containment.deinerted.
I 4
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.
Pg~
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.
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.
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.
For extended outages, cold- shutdown testing does not need to start within 48 hours as long as all valves are tested before startup.
All cold shutdown valves will I 4 Pg~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 hours 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-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 operated in the event of an emergency during normal power operations.
This alternate testing meets the intent of OM-10 which     will be required in the future.
Lengthening the interval between tests as recommended will not preclude the timely evaluation of valve oper-abilityty and thus provides adequate assurance of material quality~.and public safety.1 1 SER/TER  
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:==
==Reference:==
3.1.4.1 Relief granted as. requested      ~
IO


3.1.4.1 Relief granted as.requested~IO 4
4 RELIEf REQUEST NO. Q~
RELIEf REQUEST NO.Q~DELETEO PRIOR TO SER REVIEW  
DELETEO PRIOR TO SER REVIEW


System Valves ASME Classification Function RELIEF REOUEST NO.~V-11 Process Instrumentation PI-EFC-X72f, X73e and TIP-V-6 Code Class: 1 Category: AC 2 (TIP-V-6)Containment Isolation.
RELIEF REOUEST NO. ~V-11 Pg~
Pg~Revision 4 Code Testing Requirement Basis for Re 1 i ef INV-3521.Check valves shall be exercised at least once every 3 months.These containment isolation valves are located inside the containment and can only be observed/tested during cold shutdown conditions when the containment is de-inerted.
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)
Alternate Testing to be Performed These valves will be tested at cold shutdown conditions with the containment de-inerted.
Function                  Containment     Isolation.
Cold shutdown testing shall commence immediately (within 48 hours)following establishment of cold shutdown de-inerted conditions.
Code     Testing           INV-3521. Check valves shall be exercised at least once Requirement              every 3 months.
Testing shall continue only as long as the plant is scheduled to be in cold shutdown with the contain-ment de-intered.
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.
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.
Alternate Testing         These valves will be tested at cold shutdown conditions to be Performed          with the containment de-inerted.
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.
Cold shutdown       testing shall commence immediately (within 48 hours) 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 hours as long as all valves are tested before startup.
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 hours 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  
                          .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:==
==Reference:==
3.11.1.1.
Relief granted        as required.
Pg~
Revision 4 RELIEf REQUEST NO. ~V~
DELETED Design change deleted valves DO-V-40A, 40B.


3.11.1.1.Relief granted as required.
II RELIEF REQUEST NO. QV ~1 Pg~
Pg~Revision 4 RELIEf REQUEST NO.~V~DELETED Design change deleted valves DO-V-40A, 40B.
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.
II RELIEF REQUEST NO.QV~1 Pg~Revision 4 System Val ves ASHE Classification Function Code Testing Requirement Basis for Relief Main Steam HS-RV-30, 4A, 4B, 4C, 4D, 5B, 5C Code Class: 1 Category: BC 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.l.INV-3411, Test Frequency 2.INV-3413, Stroke Time of Power Operated Valves l.Valve exercise on a quarterly basis during power oper-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.
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.
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.
: 2.     These valves are not equipped with position indicators based directly on the valve obturator,or valve actua-                     ,
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.
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.
This will provide adequate assurance of material quality and public-safety.
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  
M       1   1 SER/TER  


==Reference:==
==Reference:==
3.6.1.1 Relief granted    as  requested.


3.6.1.1 Relief granted as requested.
                                                                    'll'~
'll'~Revision 4 RELIEF REQUEST NO.RV-14 System Valves ASME Classification Function Control Rod Drive CRD-V-10 and 180, CRD-V-ll and 181 Code Class: 2 Category: B These valves are the vent and drain valves on the scram discharge volumes.Code Testing Requirement INV-3413.Measure the stroke-time of power operated valves.Basis for Relief CRD-V-10 and 180, as well as CRD-V-ll and 181 are located in series, share the same position indication, and the same actuating source (air).Valve indication indicates shut when~i~valve closes.Valve indication indicates open only when~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.
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.
Valve closure will be verified by local observation.
Code   Testing         INV-3413. Measure the stroke-time of power operated valves.
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  
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
                                ~~
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:==
==Reference:==
3.7.1.1 Relief granted    as requested.
J C I
tQ i
n 5 -    C P '


3.7.1.1 Relief granted as requested.
QV-l'j 9~
J C i I tQ n 5-C P' 9~Revision 4 RELIEF REQUEST NO.QV-l'j System Valves ASHE Classification Function Various All excess flow check valves in the program Containment Isolation Code Testing Requirement l.IHV-3521, Test Frequency Basis for Relief 1.These are instrumentation line excess flow check 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.to be Performed These valves shall be exercised at least once every 18 months per WNP-2 Technical Specifications.
Revision   4 RELIEF REQUEST NO.
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  
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:==
==Reference:==
3.1.5.1 Relief granted    as required.


3.1.5.1 Relief granted as required.
l e 4'
l e 4' 4, II'~Revision TABLE RV-151 P I-EFC-X18A PI-EFC-X18B PI-EFC-Xl SC PI-EFC-X180 P I-EFC-X29b P I-EFC-X29f PI-EFC-X30a PI-EFC-X30f PI-EFC-X37e PI-EFC-'X37f P I-EFC-X38a PI-EFC-X38b PI-EFC-X38c PI-EFC-X38d P I-EFC-X38e P I-EFC-X38f PI-EFC-X39a PI-EFC-X39b PI-EFC-X39d P I-EFC-X39e PI-EFC-X40c PI-EFC-X40d PI-EFC-X40e P I-EFC-X40f P I-EFC-X41 c PI-EFC-X41d PI-EFC-X41e PI-EFC-X41f P I-EFC-X42a P I-EFC-X42b PI-EFC-X42c P I-EFC-X42f P I-E FC-X44Aa PI-EFC-X44Ab P I-EFC-X44Ac PI-EFC-X44Ad P I-EFC-X44Ae P I-EFC-X44Af PI-EFC-X44Ag P I-EFC-X44Ah PI-EFC-X44A j P I-EFC-X44Ak PI-EFC-X44A1 PI-EFC-X44Am PI-EFC-X44Ba 1 1 1 1 1 2 2 2 MXW!CX AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC PI-EFC-X44Bb PI-EFC-X448c PI-EFC-X44Bd PI-EFC-X44Be P I-EFC-X44Bf P I-EFC-X44Bg PI-EFC-X44Bh PI-EFC-X44B]
 
PI-EFC-X448k PI-EFC-X44B1 PI-EFC-X44Bm PI-EFC-X61a P I-EFC-X61b PI-EFC-X61 c PI-EFC-X62b PI-EFC-X62c PI-EFC-X62d PI-EFC-X66 PI-EFC-X67 P I-EFC-X69a PI-EFC-X69b PI-EFC-X69e PI-EFC-X69f PI-EFC-X70a PI-EFC-X70b PI-EFC-X70c P I-EFC-X70d P I-EFC-X70e P I-EFC-X70f P I-EFC-X7 1 a PI-EFC-X71b PI-EFC-X71c PI-EFC-Xjl d P I-EFC-X71e PI-EFC-X71 f PI-EFC-X72a PI-EFC-X73a PI-EFC-X74a P I-EFC-X74b PI-EFC-X74e P I-E FC-X74f PI-EFC-X75a PI-EFC-X75b P I-EFC-X75c PI-EFC-X75d MZa~~r AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC For information only-not part of relief request.
II'~
N a n Pg~Revi s ton 4 TASLE RV-15 (CONTINUED)
Revision 4,
CL Cat.l~KI5 PI-EFC-X75e 1 P I-EFC-X7 5P 1 P I-EFC-X78a 2 PI-EFC-X78b 1 PI-EFC-X78c 1 P I-EFC-X78f 1 PI-EFC-X79a 1 PI-EFC-X79b 1 PI-EFC-X82b 2 P I-EFC-X84a 2 P I-EFC-X86A 2 PI-EFC-X868 2 PI-EFC-X87A 2 PI-EFC-X878 2 P I-EFC-X106 1 PI-EFC-X107 1 PI-EFC-X108 1 P I-EFC-X109 1 P I-E FC-X110 1 P I-EFC-X111 1'I-E FC-X112 1 PI-EFC-X113 1 PI-EFC-X114 PI-EFC-X115 1 PI-EFC-X119 2 AC AC AC AC AC AC AC AC" AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC AC Il~Revision 4 RELIEF REQUEST HO.f~DELETED SER/TER  
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
n
 
Pg~
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:==
==Reference:==
3.2.1.1 Re1ief request denied  for  RCIC-V-111 and 112.


3.2.1.1 Re1ief request denied for RCIC-V-111 and 112.
I
I't Revision RELIEF RE/VEST NO.g~System Valves ASHE Classification Function Code Testing Requirement Basis for Re 1 i ef HPCS, LPCS, and RHR HPCS-V-7, LPCS-V-33, and RHR-V-84A, 84B, 84C Code Class: 2 Category: C Open: To permit the water leg pump to fill the system with water and maintain it pressurized.
  't
Close: To prevent overpressurization of the waterleg pump and associated piping.INV-3521, Test Frequency These valves cannot be verified to be closed without either 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.
Revision RELIEF RE/VEST NO.       g~
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.
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.
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  
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:==
==Reference:==
3.1.6.1 Relief requested granted, provided                if excessive  leakage is noted, both valves shall    be  repaired or replaced.


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.
Revision 4 RELIEF REQUEST NO.EVE System Valves ASME Classification Function Main Steam 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 Code Class: 2 Category:.BC Open: To break vacuum in the downcomers of the main steam relief valves.Code Testing Requirement Basis for Rel i ef Alternate Testing to be Performed Close: To direct steam to the quenchers in the wetwell.INV-3521, Test Frequency Testing requires personnel access to the containment.
Close:   To direct   steam to the quenchers in the wetwell.
This requires that the reactor be shutdown and the containment be de-inerted.
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.
These valves will be exercised when'he reactor is shutdown and the containment 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.
The valves will be man-ually operated and visually verified to open and reseat.Cold shutdown testing shall commence immediately (within 48 hours)following establishment of cold shutdown de-inerted conditions.
Cold shutdown     testing shall commence immediately (within 48 hours) 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 hours as long as all valves are tested before startup.
Testing shall continue only as long as the plant is scheduled to be in cold shutdown with the contain-ment de-intered.
This alternate     testing   meets the   intent of OM-10 which will be required in the future.
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 hours 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 1 provide adequate assurance of material quality and public safety.SER/TER  
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:==
==Reference:==
3.6.2.1 Relief granted    as  requested.


3.6.2.1 Relief granted as requested.
RELIEF REQUEST NO. /VV ')
P II~Revision 4 RELIEF REQUEST NO./VV')OELETED SER/TER  
P II ~
Revision 4 OELETED SER/TER


==Reference:==
==Reference:==
3.8.1,1 Relief request denied for  HY valves.


3.8.1,1 Relief request denied for HY valves.
P j'l
P j'l System Valves Various RELIEF REQUEST NO.Q~page~M3 Revision 4 ASME Classification Function Ail power operated valves except rapid action valves covered by Relief Request RV-1.System control valves and Containment isolation valves.Code Testing Requirement IWV-3417(a) which requires comparison of measured stroke time with"the previous test".Basis for Rel ief WNP-2 Administrataive Procedures require specific accept-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 as a result of plant conditions or test personnel, the re-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.
page~M3 Revision    4 RELIEF REQUEST NO. Q~
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.
System                  Various Valves ASME                   Ail power operated valves except rapid action valves           covered Classification          by Relief Request RV-1.
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  
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:==
==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
Pg~
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


3~1.1.2 Relief granted as requested.
Pg~
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


TABLE RV-201 V lv N r gl gglIUIIIII Pg~Revision 4~l.~~~r CAC-FCV-1A CAC-FCV-18 CAC-FCV-2A CAC-FCV-28 CAC-FCV-3A CAC-FCV-38 CAC-FCV-4A CAC-FCV-48 CAC-FCV-5A CAC-FCV-58 CAC-V-1A CAC-V-18 CAC-V-2 CAC-V-2A CAC-V-28 CAC-V-4 CAC-V-6 CAC-V-8 CAC-V-11 CAC-V-13 CAC-V-15 CAC-V-17 CEP-V-1A CEP-V-18 CEP-V-2A CEP-V-28 CEP-V-3A CEP-V-38 CEP.-V-4A CEP-V-48 CIA-V-20 CIA-V-30A CIA-V-308 CIA-V-39A CIA-V-398 CRD-V-10 CRD-V-11 CRD-V-180 CRO-V-181 CSP-V-1 CSP-V-2 CSP-V-3 CSP-V-4 CSP-V-5 CSP-V-6 CSP-V-9 EDR-V-19 EDR-V-20 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 3 3 2 2 2 2 2 2 2 2 2 2 2 2 2 A A A A A A A A 8 8 8 8 A 8 , 8 A A A A A A A A A A A A A A A A A A B 8 8 8 8 A A A A A A A A A FDR-V-3 FDR-V-4 FPC-V-149 FPC-V-153 FPC-V-154 FPC-V-156 FPC-V-172 FPC-V-173 FPC-V-175 FPC-V-181A FPC-V-1818 FPC-V-184 HPCS-V-1 HPCS-V-4 HPCS-V-10 HPCS-V-ll HPCS-V-12 HPCS-V-15 HPCS-V-23 HY-V-17A HY-V-178 HY-V-18A HY-V-188 HY-V-19A HY-V-198 HY-V-20A HY-V-208 HY-V-33A HY-V-338 HY-V-34A HY-V-348 HY-V-35A HY-V-358 HY-V-36A HY-V-368 LPCS-FCV-11 LPCS-V-1 LPCS-V-5 LPCS-V-12 MS-V-16 MS-V-19 MS-V-22A MS-V-228 MS-V-22C MS-V-220 MS-V-28A MS-V-288 A A A A A A 8 8 8 8 8 8 8 A 8 A A A A A A A A A A A A A For information only-not part of relief request.
Pg~
I'9~I I ,4 TABLE RV-20 (CONTINUED)
Revision 4 RELTEF REQUEST NO. ~V- 1 DELETED Design changes deleted valves SW-V-214, 215, 216, and 217,
~~~Vltt Cl~l~garz~~~VI Pg~Revision 4+t'ai MS-V-28C MS-V-28D MS-V-67A MS-V-678 MS-V-67C MS-V-67D MS-V-146 MSLC-V-1A MSLC-V-18 MSLC-V-1C MSLC-V-1D MSLC-V-2A MSLC-V-28 MSLC-V-2C MSLC-V-2D MSLC-V-3A MSLC-V-38 MSLC-V-3C MSLC-V-3D MSLC-V-4 MSLC-V-5 MSLC-V-9 MSLC-V-10 RCC-V-5 RCC-V-21 RCC-V-40 RCC-V-104 RCC-V-129 RCC-V-130 RCC-V-131 RCIC-V-1 RCIC-V-8 RCIC-V-10 RCIC-V-13 RCI C-V-1 9 RCIC-V-22 RCI C-V-31 RCI C-V-45 RCIC-V-46 RCI C-V-59 RCIC-V-63 RCIC-V-68 RCIC-V-69.RCIC-V-76 RCIC-V-110 RCIC-V-11 3 RFW-V-65A RFW-V-658 1 1 1 1 1 1 2 2 2 2 2 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 3 3 3 2 1 2 1 2 2 2 2 2 2 1 2 2 1 2 2 1 1 A A A A A A 8 I 8 8 8 8 8 8 8 8 A A A A 8'8 8 8 A A A A 8 8 8 8 A 8 A A 8 A 8 8 8 A A A A 8 8 A A RHR-FCV-64A RHR-FCV-648 RHR-FCV-64C RHR-V-3A RHR-V-38 RHR-V-4A RHR-V-48 RHR-V-4C RHR-Y-6A RHR-V-68 RHR-V-8 RHR-V-9 RHR-V-16A RHR-V-168 RHR-V-17A RHR-V-178 RHR-V-21 RHR-V-23 RHR-V-24A RHR-V-248 RHR-V-27A RHR-V-278 RHR-V-40 RHR-V-42A RHR-V-428 RHR-V-42C RHR-V-47A RHR-V-478 RHR-V-48A RHR-8-488 RHR-V-49 RHR-V-53A RHR-V-538 RHR-V-68A RHR-V-688 RHR-V-73A RHR-V-738 RHR-V-115 RHR-V-116 RHR-V-123A RHR-V-1238 RHR-V-134A RHR-V-1348 RRC-V-16A RRC-V-168 RWCU-V-1 RWCU-V-4.RWCU-V-40 2 2 2 2 2.2 2 2 2 2 1 1 2 2 2 2 2 1 2 2 2 2 2 1 1 1 2 2 2 2 2 1 1 3 3 2 2 2 2 1 2 2 2 2 1 1 1 A A A 8 8 A A A 8 8 A A A A A A A A A A A A 8 A A A 8 8 8 8 8 A A 8 8 A A 8 8 A A A A A A A A A
'1 t Pg~R TABLE RV-20 (CONTINUED)
V v SLC-V-1A SLC-V-18 SW-V-2A SH-V-ZB SH-V-4A SH-V-48 SW-V-4C SH-V-12A SH-V-128 SH-V-24A SH-V-248 SH-V-24C SH-V-29 SH-V-44 SH-V-54 SH-V-75A SH-V-758 SH-V-187A SH-V-1878 SH-V-188A SH-V-1888 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 8 8 8 8 8 8 8 8 8'8 8 8 8 8 8 8 8 8 8 8


Pg~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 Valves ASME Classification Function Code Testing Requirement Basis for Relief Emergency Chilled Water SW-TCV-11A, 118, 15A, 158 Code Class 3, Category B These are the temperature control valves for cooling water flow to the chiller heat exchangers, IWV-3413, measure the stroke time of power operated valves.These are hydraulically operated globe valves used for control of chillwater temperature.
f I
They do not have'a manual control switch or any remote position indicators.
 
Alternate Testing to be Performed Valve exercising per INV-3412 will provide adequate assurance of valve operability.
9'~
Verification of 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  
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:==
==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.


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~
Ilvv Pg~Revision 4 RELIEF REQUEST NO.]LVV System Valves PSR-V-X73-1
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-X77A1                PSR-V-X82-1         PSR-V-X84-1
*PSR-V-X77A3 PSR-V-X80-1 PSR-V-X82-1 PSR-V-X82-7 Post Accident Sampling PSR-V-X83-1 PSR-V-X84-1 PSR-V-X88-1 ASME Classification Code Class: 2*Code Class: 1 Category: A Function Closed Position-Containment Isolation Code Testing Requirement Basis for Relief Alternate Testing to be Performed INV-3413, Power Operated Valves (stroke times)These nine PSR solenoid valves are the inboard 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.The stroke time of the slowest valve will be measured by terminating the stroke time measurement when the 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.
                              *PSR-V-X77A3                PSR-V-X82-7          PSR-V-X88-1 ASME Classification           Code   Class:   2         Category:  A
The proposed alternate testing will verify that the valves respond in a timely manner and provide information for monitoring signs of material degradation.
                              *Code Class:       1 Function                     Closed Position       - Containment Isolation Code Testing Requirement                   INV-3413, Power Operated Valves (stroke times)
This provides adequate assurance of material quality and public safety.A/M 1 1 SER/TER  
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:==
==Reference:==
3.1.4.1.1 Relief granted    as requested.


3.1.4.1.1 Relief granted as requested.
E RELIEF REQUEST NO. f~V-9~
E 9~Revision 4 RELIEF REQUEST NO.f~V-System Valves ASME Classification Function Code Testing Requirement Basis for Relief Alternate Testing to be Performed li/Containment Instrument Air CIA-SPV-1A through 15A CIA-SPV-1B through 198 Code Class: 3 Category: B Emergency Nitrogen Bottle Isolation Valve IWV-3413, Power Operated Valves<stroke times)These valves have neither a manual control switch nor suitable valve position, indicators.
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)
The proposed alternate testing will confirm valve operability and detect any defective valves.The valves will be tested per IWV-3410 with the exception of IWV-3413.Verification that the valve opens and closes is based on observation of appropriate system responses.
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.
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  
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:==
==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.


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
I g ,h P g~Revision RELIEF REQUEST NO.RVV,'j System Valves ASME Classification Function Al 1 All valves tested at cold shutdown.Various Various-See Note 1 to valve test tables.Code Testing Requirement Basis for Relief IHV-3412 Exercise valves during cold shutdowns, IHV-3522 if valve is not full stroke exercised each 3 months during plant operation.
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It is a hardship to test all cold shutdown valves at 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.Alternate Testing to be Performed.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.Cold shutdown testing shall commence immediately (within 48 hours)following establishment of cold shutdown conditions.
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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.
Revision RELIEF REQUEST NO. RVV,'j System                 Al 1 Valves                All valves tested at cold     shutdown.
The decision whether to start cold shutdown testing on any particular procedure will depend on the estimated length of the cold II~Revision 4 Relief Request No.~i (Continued) li/shutdown period;system outages/conditions; time interval from the last cold shutdown testing;or other particular conditions.
ASME  Classification  Various Function              Various   See   Note 1 to valve test tables.
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 hours 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.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.
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.
e/M 7 SER/TER  
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 hours) 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 hours 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:==
==Reference:==
3.1.7;1 Relief granted only for valves that      can be tested during any cold shutdown.
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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~
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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
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Relief Request  No. 9V  ~  (Continued)
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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)
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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
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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$ &#xc3; 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
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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.


3.1.7;1 Relief granted only for valves that can be tested during any cold shutdown.
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Pa~Revision 4 RELIEF REQUEST NO.I'LL~System Valves ASHE Classification Function Code Testing Requirement Basis for Relief Alternate Testing to be Performed Standby Liquid Control (SLC)SLC-V-33A, 338 Code Class 2 Category: C SLC-P-1A and 1B discharge check valves 1.Quarterly exercising (INV-3521) 2.Cold shutdown exercising (INV-3522)
R R
There are no test connections to allow back flow testing 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.
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.
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.
                        '~
During each refueling outage verify closure of these 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 P II~Revision 4 RELIEF REQUEST NO.fQf~System RCIC, HPCS, LPCS and RHR RCIC-V-65, 66 LPCS-Y-6 HPCS-V-5 RHR-V-41A,B,C RHR-V-50A, 8 1 1 1-.1 A-C A-C A-C A-C A-C RCIC discharge to the reactor vessel head LPCS discharge to the reactor vessel HPCS Discharge to the reactor vessel RHR Loop A, 8, C discharge to the reactor vessel RHR Loop A, 8 discharge to the recircu-lating pump discharge Code Testing Requirement Basis for Relief 1.Quarterly exercising (INV-3521) 2;Cold shutdown exercising (INV-3522)
PT Control       &                               Emergency Chilled r           i Diesel Oil         &                           Pri. Containment RIL       RRII Demineralized                                 Post Accident r                                            lin Reactor Core li High/Low Pressure r
These valves (except RCIC-V-65) function as Reactor 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.2.3.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.Other than the above two instances, these check valves have exhibited excellent leak-tight integrity during the last eight years since commercial operation.
Residual Heat v                   M    1 Standby Liq.
l E'I g J Relief Request No.9V~(Continued)
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.
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 1 of Attachment 1 of Generic Letter 89-04.5.6.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.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.
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}}
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.
Alternate Testing to be Performed 8.During normal plant operation, these valves are.normally closed and do not open.During each refueling outage (not to exceed 18 months)l.z.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.
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 Pg~R f I rv Records and reports pertaining to Valve Inservice Testing will be maintained according to Article INV-6000 of the Code.
1 i 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 VALVE ID LPCS-V-I VALUE V".14 ALERT LO (+1)91.60 ALERT HI (+1)152.67 ACTION HI (+1)183.21~T LO (+I)120.50 9037 MEASURE VALUE ALERT HI (+1)150.62 ACTION HI (+I)180.75 LPCS-FCV-ll 17.09 12.82 2136 U>.64 16.62 12A 20.78 24.93, (" LPCS-V-12 11.74'A NA 936, 4.68 LPCS-V-3 LPCS-V-33 LPCS-V-34 NA NA NA NA NA NA NOT OPEN NOT OPEN NOT OPEN iNA NA NA NA NA NA NA iNA NA iNOT CLOSED NOT 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 7.4.5.1.7 REVISION PAGE'34 of 18 TWO YIIAR VP)VI.~111~I(.ATIAN DATA csl-lI..IST VALVE NUMBER VALVE COHDITIOH INSPECTED Vf Rl'IED OPLtH LOCAL IHDICATIOH INITIALS AS FULL raaua asau SAT UHSAT REMOTE INDICATION LOCATION OF Vr I VL'RIPIED CI.OSL'D REMOI E IN DICATIOH SAT UNSAT IHITIALS (+I)AS FOUND ruLL CI.OSr: LOCAL INDICATION VALVE OPERATION%PULL OPEN (+2)LPCS-V-I LPCS-FC V-I I LPCS-V-12 (+3)STEP I STCP 2 STEP 3 STEP 5 STEI'STEP 4 I I)3/P60 I I I I3/PGO I I I I3/P60)STEP 4 STEP 4 STCP 2 STEP 3 STEP 5 STEP 6 STEP 8 STEP 7 (+I)If thc 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)If tha 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 X FUI.L OPQN 5 5 at Full Ctuscd 9$&#xc3;at Full Opcu 90'I As Fuood Open (90 5)/(95.5)x l00~9d.c 4~xse~ALsSS X I'UI.L OPQtt 0 at Full Close J 6.0 st Full Open 5.$Aa Found Open ($.$-0)/(6.0-0) x III~9I.7X iloh7~l1~AISttkiiSv~il II a 0 at I'ull Close J I 2 5 at Irull Otscsl I l.5 Aa Iruuud t)pcu A I UI.L Of'QN<<(I I.S.O)/(I'2.$
.0)x l00~9'2.04 ittst~n~ns~nt~I so St FULL OPQN JS't Pull Closad 27$at Full Open 23S'a FounJ Open (23$.65)/(27$.45fx l00~82.6 A (I3)I pCS.V I'2 4 cunsldcrcd Full Open lf lt 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, AIIIICIIIIICIII 9.5 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.
R Pg~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&r i Diesel Oil&RIL RRII'~Demineralized r Emergency Chilled Pri.Containment Post Accident lin Reactor Core li High/Low Pressure r Residual Heat v 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 M 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}}

Latest revision as of 06:43, 4 February 2020

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


Text

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).

P9~

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).

P9~

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

~ ~

~ ~

~ ~

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)

'll'~

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

'll ~

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

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

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+~ .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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0I RD-1 A V-225A Fx-IA PI 2 I/2 Pl IA V-710A 34 J 3 v-70<A CC-EV-IA / 3 V-IOSD X-IA V-822A 2 I/2 V

FLX 2A+4 +3 3 3 P-IA V-1060 2 I/2 V-3A V"226A V-107D REFERENCES(

EMERGENCY CHILLED IIAI'ER PIPING ORRDMG M775

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V-7828 V-782A V-8238 FE-358 3

TCV-118 2

r' I/2 V-IONIC g 2 I/2 V-2278 Cell tjI V-2258

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(- 10 8 ~ ~8 V-145A V-1458 V-.l RSA Y-1468 FE-16 FPC- FPC-TK-IA TK-1S

(- 10 V-130 ~ 8 I FFUSERS~

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20 V-2A V-IA 16 20 20 .18 2A RIIR-HX-I A y 706A PI HPCS-P-2 SM-P-I A 20 RHR-V-68A RHR-V<<IAA FE-6A PUHP SPRAY 18 20 ~ HOUSE A POND A PUHP HOUSE MALL 12 20 20 PCV-38A V-12A 20 SM-P-I B DCM HX- I A2 SM-P-I B V-170A FE-IA DCM HX-IAI PUHP SPRAY RO-2A HOUSE B POND B REFERENCES'&RDMG H524 SH I SERVICE MATER

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8 R R DMG SERVICE MATER HS24 Stt 2

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.

Attachment 9.2 rhea 7.4.5.1.7 15 of 18

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Bearin 4 Probe Vibrsaca Velociry (ia/sec)

Locaaoa Reier Measured Alert EK Acdoa HI Value Vshe (+ l) (+ l)

N4 0.130 0.700 D.(L11)

E-W 0.150 0.700 Q.<~ l.)

0. 100 0.600

(+ l) For measured values beyoad tho Alert Value or Acaoa Value reier co ~aoa sad L'miuaoas 4.6 or 4.7, resp ecavely.

Attachment 9.3 FROCK) URE WOMBEk . PAGS 7.4.5.1.7 46 Of 18

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LPCS-P-1 ACCEPTANCE CRITERIA 3m I

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. 630 638l M83 64CO 6420 644l 64K 64M 6500 6520 6540 6560 FLOWRATE - GPM ALERT RANGE - Area Outside I-2-3-4 ACTtON RANGE - Area Outside 5-6-7-8 Attachment 9.4 .

2RGCKURE WMEZ REVTSiON 1.4,5.1.7 17 oi 18

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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.

ll f

I

2':

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after cold shutdown is achieved and continue until complete or until 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.

P II'~

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.

0 6

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. ~

tl554 CAC-FCV-3A DIO F 2 ' GB HO NC FC Q GHJKL ~ . ~ I ~ 4 ~ 20 tl5 5 4 CAC-FCV-38 Db F 2 ~5 GB HO NC FC Q GHJKL ~ ~ I r 4120 tI554 CAC-FCV-4A FIO F 2.5 GB HO NC FC Q GHJKL. ~ 1 ~ 4120 tl554 CAC-FCV-48 2 Eb tl554 F 2.5 CD HO thC FC 8 GHJKL. . 1 ~ 4 '0 CAC-fCV-5A F14. 8 1 CD HO NC FC Q GH JK ~ ~ ~ ~ 20 tl5 5 4 CAC-FCV-58 F2 8 I CD HO NC FC 0 GHJK ~ ~ re 20 tl554 CAC-RD-IA D12 D 2 RD SA NC NA N .......Ih 10 H554 CAC-RD-18 D3 D RD SA thC NA th ~ ~ ~ ~ ~ r II 10 N554 CAC-RV-b3A E12 C I X 2 RV SA NC NA N .r ~ P ~ r tl554 CAC-RV-b38 E4 C I X 2 RV SA NC IIA N ~ ~ r .PE N554 CAC-RV-b5A D13 C 1.5 X 3 RV SA NC NA N ~ ~ ~ ~ ~ P ~ ~

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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 "

FA I GHJ.L... 4r20 H554 CAC-V-2A 2 F12 D 4 DIA HO NC FC 6 CHJK.... 20 tl554 CAC-V-28 F5 DI A HO =

NC FC 6 GtlJKr r r 20 CAC-V-4 Elo tt 554 F GT tlo NC FAI 6 CHJ ~ L ~ ~ ~ 4 '0 CAC-V-6 HIO F GT IIO tlC FAI 6 CHJ.L . ~ ~ 4a20 CAC-V-8 D10 F GT NQ NC FAI 6 CHJ.L.. ~ 4r20 tl554 CAC-V-11 2 06 F 4 GT HO NC FAI 6 CHJ ~ L ~ ~ ~ 4r20 M554 CAC-V-13 2 Eb F HO NC 'AI 6 GHJ ~ L ~ ~ ~ 4 ~ 20 CAC-V-15 2 Hb N554 F 4 GT NC FAI 6 CHJ ~ L ~ ~ ~ 4 '0 CAC-V-17 Db F 4 GT ttn NC FAI 6 GHJ.L... 4r20 tt554 CAS-V-730 2, K9 tt51 0 F -P 1 CD HAN LC NA N ~ ~ ~ L~ ~ ~

CAS-VX-82e F -P CD ttAN LC NA ~ ~ ~ ~ L~ ~ ~

tt5 1 0 CCH-RD-IA G8 N775 D 3 RD SA NC NA N .....It 10 CCH-RD-18 3 C7 D RD SA tlC NA N ~ ~ ~ ~ ~ ~ ~ It 10 tt775 CCH-RV-2A 3 F7 C .75 X 1 RV SA NC NA N ~ ~ ~ ~ ~ P ~

tt775 ccH-Rv-2n B7 C .75 X 1 RV tlc NA ~ ~ ~ ~ ~ P ~

tt775 CEP-V-IA 2 J13 DF AO NC FC 6 CtlJKL 4r20 tl543 I CEP-V-ln a Cn Ao FC 6 GtlJKL... 4 '0

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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..

Cl*-RV-5B 3 911 C .75 RV SA tlC NA N ~ ~ ~ ~ PE M556 1

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

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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...

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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

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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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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;

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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

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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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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

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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

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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

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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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) 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.

Page~4-4~

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.

~

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.

II> Ce~

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)

V lv n P

Rev II ~

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).

1 b

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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

~

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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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.

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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

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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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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

~~

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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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.

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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~

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Revision 4 DELETED SER/TER

Reference:

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

I

't

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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.

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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.

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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

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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

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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

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.

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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.

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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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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

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RELIEF REQUEST NO. fQf~

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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

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Relief Request No. 9V ~ (Continued)

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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)

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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.

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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

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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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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.

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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

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