ML17276B690
| ML17276B690 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/28/1982 |
| From: | Hoyle T, Martin J, Renberger D WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17276B662 | List: |
| References | |
| NUDOCS 8210260113 | |
| Download: ML17276B690 (309) | |
Text
WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 PUMP AND ALVE INSERVICE TEST PR RAM PLAN 8210260113 821007 PDR ADQCK,05000397
A PDR
~'+)Q~ f PUMP AND VALVE INSERVICE TEST PROGRAM PLAN - REV. 1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 Prepared by Operations Support Engineering
>l>mls Date
~
Approved by Lead Engineer, P ant En ineering 8 Survei ance Da e Approved by Manager, WNP-2 ngineering Date Approved by ~ ~/8>
Assistant Director, Generation Engineering Date Reviewed by Technical Manager, WNP-2 Date Approved by Plan Manager, WNP-2 Reviewed by anager, Oper ational ua1 i y Ass anc 0 te Reviewed by Author ized Nuclear Inservice Inspector Date
RECORO OF PROGRAM PLAN REVISIONS 8/2S/82 4/23/Sl ORIGINAL No. OATE REVISIONS CrlK '0 APP'0
TITLE SHEET DATE/REV. TITLE SHEET DATE/REV.
- 3. Pump Test Title Sheet N/A Pro ram 3-12 Contd Sin Ori . 3-12a Records of Revision 3-12b 3-13 3-14 3-15 1.0 Intro. 3-16 3-17
.0 Table of Contents 2-1 3-18 3-19 3.0 Pump Test Pro ram 3-1 3-20 3-2 3-21 3-3 3-22 3-4 3-23 3-5 3-24 1
3-6 3-25 was 3-24 3-7 3-26a was 3-25 3-7A 3-26b 3-8 4.0 WNP-2 4-1 Valve 3-9 Inservice 4-2 Test 3-10 Pro ram 4-3 3-11 4-4 3-lla Deleted 4-5
TITLE SHEET DATE/REV. TITLE SHEET DATE/REV.
4.0 MgP-2 4-6 4.0 MNP-2 4-26 Valve Valve I ns er v l ce 4-7 Inser vice 4-27 Test Test Pro ram 4-8 Pro ram 4-27a Contd Contd 4-9 4-28 4-10 4-29 4-11 4-30 4-12 4-31 4-13 4-32 4 ]4 4-33 4-15 4-34 4-16 3g 4-17 4-36 4 37 4-19 4-38 4-20 4 39 4-21 4-40 4-22 4 4]
4-23 4 42 4-23a 4-43 4-24 4-25
TITLE SHEET OATE/REV. TITLE SHEET OATE/REV.
4.0 MNP-2 4-46 1 4.0 MgP-2 4-66 Valve Valve Inservice 4-47 Inservice 4-67 Test Test Pro ram 4-48 Pro ram 4-68 Contd Contd 4-49 4-69 4-50 4-70 4-51 4-71 4-52 4-72 4-53 4-73 4-54 4-74 4-55 4-75 4-56 4-76 4-57 4-77 4-58 4-59 4-60 4-61 4-62 4-63 4-64 4-65
TITLE SHEET DATE/R EY. TITLE SHEET DATE/REY.
Floor Drain 5.0 ualit Radioactive M 539 37 Assurance Containment Pro ram 5-1 Coolin EPurae M 543 27 Containment Atmos. Control M 554 21 6.0 Flow Containment Di a rams 6-1 Instru. Air M 556 17 Control Main Steam Service Air M 510* Lea'(a e Cont. M 557 .11 Diesel Oil 8 Steam and Misc. S stems M 512 20 Li ui d Sam. M 607 sh. 2 7 Reactor Core Iso. Coolina M 519 27 Low Pressure Core S ra M 520 25 High Pressure Core Spra M 520 25 Residual Heat Removal M 521 Standby Liq.
Control M 522 12 Reactor Water Cleanu M 523 39 Standby Service Water M 524 30 Reactor Closed Coolino M 525 26 Fuel Pool Coo lin M 526 34 Control Rod Drive M 528 25 Main Steam M 529 29 Reactor Feedwater M 529 29 Reactor Recirc.
Coo lin M 530 27 Equip. Drain Radioactive M 537 33
- Burns E Roe Flow Oia ram Number vii
Page l-l R
- 1. 0 INTRODUCTION This Pump and Valve Inservice Test Program Plan is applicable to the WPPSS Nuclear Project No. 2, hereinafter referred to as WNP-2. A single unit Boiling Water Reactor (BWR), the power plant is located 11 miles north of Richland, Washington, on the Hanford Reservation. The plant employs a General Electric (GE) supplied nuclear steam supply system designated as BWR/5. The reactor is contained within an over-under drywell/wetwell con-tainment vessel designated Mark II. The plant rated electrical output is 1,094 MWe.
This program plan has been prepared as the controlling document governing Pump and Valve Inservice Testing at WNP-2. The requirements for Pump and Valve Inservice Testing are outlined in the ASME Boiler and Pressure Ves-sel Code,Section XI, entitled "Rules for Inservice Inspection of Nuclear Power Plant Components." The scope of this plan encompasses the testing of ASME Section III Nuclear Class 1, 2 and 3 pumps and valves, as defined by Sub-sections IWP and IWV of ASME Section XI.
The WNP-2 FSAR commits to testing Class 1, 2 and 3 pumps and valves ac-cording to.the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1977 Edition with Addenda through Summer 1978. However, Revision 1 is written to comply with the requirements of the 1980 Code Edition with addenda through Winter, 1980. This is consistent with-federal requirements for component testing as stated in Title 10, Code of Federal Regulations, part 50 (10CFR50.55a(g)).
This Program Plan is comprised of two independent subprograms - the Pump Inservice Test Program and the Valve Inservice Test Program. The develop-ment, implementation and administration of these two programs is detailed in subsequent sections (3.0 and 4.0).
Page 2-1 R
2.0 TABLE OF CONTENTS Record of Revisions 1.0 Introducti on 2.0 Table of Contents 3.0 Pump Inservice Test Program Description 3.1 Program Development Philosophy 3.2 Program Implementation 3.3 Program Administration 3.4 Pump Reference List 3.5 Pump Inservice Test Tables 3.6 Requests for Relief from Certain IWP Requirements 3.7 Proposed Pump Test Flow Paths 3.8 Records of Inservice Tests 4.0 Valve Inservice Test Program Description 4.1 Program Development Philosophy 4.2 Program Implementation 4.3 Program Administration 4.4 Valve Test Tables 4.5 Request for Relief from Certain IWV Requirements 4.6 Listing of Category A Valves 4.7 Records of Valve Inservice Tests 5.0 guality Assurance Program 6.0 Piping and Instrument Diagrams
Page 3-1 Revision I 3.0 WNP-2 Pump Inservice Test Program 3.1 Pro ram Develo ent Philoso h Highly reliable safety related equipment is a vital consideration in the operation of a nuclear gener ating station. To help assure operability, the WNP-2 Pump Inservice Test Program (Section 3.5) has been developed.
The Program is designed to detect and evaluate significant hydraulic or mech-anical change in the operating parameters of vital pumps and to initiate cor-rective action when necessary. The Program is based on the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP. To the maximum extent practical, the Program complies with the specifications of the approved Codes,(>) regulations (2) and guidelines.(3)
Consistent with the intent of Subsection IWP, the Supply System has incorpor-ated into this program certain requirements which exceed the specifications of the Code. In particular, the Diesel Fuel Oil Transfer Pumps are included for testing due to their potentially significant impact on plant safety.
The Supply System recognizes that design differences among plants may render impractical certain Code requirements. For example, it is not practical to require suction pressure measurement on vertical turbine ("deep well" ) type pumps. Where such impracticalities exist, they have been substantiated as exceptions as allowed by the Code. Alternate testing requirements have been proposed when warranted. The Relief Requests which document the exceptions comprise Section 3.6.
The Supply System is confident that the WNP-2 Pump Inservice Test Program compli es with the intent of the approved Codes,(>) regulations(2) and guidelines(3) and contributes to ensuring the safety of the general public .
- l. ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP, (1980 Edition with Addenda through Winter, 1980).
- 2. 10CFR 50:55 a(g).
- 3. NRC Staff Guidelines for complying with certain provisions of lOCFR 50:55 a(g) "Inservice Inspection Requirements".
Page 3-2 Revision 1 3.2 Pro ram Im lementation Surveillance testing is performed to detect equipment malfunction or de-gradation and to initiate corrective action. Since the safety related pumps are normally in a standby mode, periodic testing of this equipment is especially important. The WNP-2 Pump Inservice Test Program provides a schedule for testing safety related pumps and will be implemented as part of the normal surveillance routine.
It is anticipated that reference data will be gathered during initial surveillance tests. In most cases, test parameters will be measured with normal plant instrumentation. This approach will simplify the test pro-gram and will promote timely completion of surveillance testing. When permanently installed instrumentation is not available, portable instru-mentation wi 11 be used to record the required parameters.
During subsequent surveillance tests, flow rate will normally be selected as the independent test parameter and will be set to match the reference flow rate. Then other hydraulic and mechanical performance parameters will be measured and evaluated against the appropriate reference values.
The results of such evaluations will determine whether or not corrective action is warranted.
Each pump in the Pump'est Program will be tested according to a detailed test procedure. The procedure will include, as a minimum:
a) Statement of Test Purpose. This section will identify test objec-tives, reference applicable Technical Specifications and note the operating modes for which the test is appropriate.
b) Prerequisites for Testing. System valve alignment, equipment for proper pump operation (cooling water, ventilation, etc.) and addi-tional instrumentation ('e.g., portable temperature or vibration monitors) will be noted. Identification numbers, range and cali-bration verification of additional instrumentation will be recorded.
c) Test Instructions. Directions will be sufficiently detailed to as-sure completeness and uniformity of testing. Instructions will include provisions for returning system to its normal standby con-figuration following testing. (For informational purposes, proposed flow paths are illustrated in Section 3.7.)
d) Acceptance Criteria. The ranges within which test data will be con-sidered acceptable will be established by the Supply System and in-cluded in the test procedure. In the event that the data fall outside the acceptable ranges, operator action will be governed by approved Administrative Procedures.
Finally it is recognized that the Pump Inservice Test Program sets forth minimum testing requirements. Additional testing will be'erformed, as required, after pump maintenance or as determined necessary by the Plant Staff.
Page 3-3 Revision 1 3.3 Pro ram Administration The operations staff of WNP-2 is responsible for the administration and execution of the Pump Inservice Test Program. The Program will be offi-cially implemented upon the issuance of an Operating License and will govern pump testing for a 120 month period. Prior to that time, the Pro-gram will be reviewed and upgraded periodically to assure continued com-pliance with 10CFR 50:55a (g)(4). The Program may also be used as part of the pre-fuel loading surveillance testing program. Subsequent to Operating License, the program will be revised to reflect current ASME requirements consistent with lOCFR 50:55a (g)(4).
Page 3-4 Revision 1 3.4 Pum Reference List This list gives a brief description of each pump identified in the Pump Test Program. The pumps'SME Code Classifications are specified in the Program.
HPCS-P-1 The High Pressure Core Spray pump provides emergency cooling spray to the reactor core. It is capable of injecting coolant at pressures equal to or above normal reactor operating pressures. The pump can take suction from the Condensate Storage Tank or from the Suppression Pool.
HPCS-P-2 This pump is dedicated to providing cooling water to the HPCS Emergency Diesel Generator, the standby power source for the High Pressure Core Spray System. HPCS-P-2 is located in the Pump House and takes suction from the spray pond.
LPCS-P-I A high capacity, low head pump, the Low Pressure Core Spray pump provides cooling spray to the reactor core upon receipt of loss of coolant sig-nal. LPCS-P-1 takes suction from the suppression pool except when test-ing to the Reactor Pressure Vessel.
RHR-P-2A, 2B, 2C The Residual Heat Removal pumps are high capacity, low head pumps which have multiple uses during normal and emergency plant conditions. Briefly the system:
a) In conjunction with other systems, restores and maintains reactor coolant inventory in the event of a LOCA b) Removes decay heat after shutdown c) Cools the suppression pool d) Condenses steam generated during Hot Standby e) Can provide cooling spray to upper and lower drywell and to the wetwell f) Can assist in fuel pool cooling g) Can provide a condensing spray to the reactor head h) P<<vides a flow path for Standby Service Mater in case containment flooding is required.
Pumps take suction from the suppression pool in the standby operating mode.
Page 3-5 Revision 1 SLC-P-1A, 18 The Standby Liquid Control pumps are used to inject negative reactivity (sodium pentaborate) into the core independently of the control rod system. Suction is obtained from a storage tank containing the sodium pentaborate solution.
SW-P-lA, 18 The Standby Service Water pumps supply cooling water to separate trains of safety related equipment. The pumps take suction on their respective spray ponds but eventually discharge to the opposite pond. The two ponds are the ultimate heat sink during loss of offsite power conditions.
RCIC-P-1 The turbine driven Reactor Core Isolation Cooling pump supplies coolant to the core in the event of reactor vessel isolation. It can take suc-tion from either the Condensate Storage Tank or from the suppression pool.
DO-P-lA, 18, 2 These pumps transfer diesel generator fuel oil from the subterranean storage tanks to the diesel's Day Tanks. Pump 2 is dedicated to the HPCS Diesel. The discharge lines of Pump lA and 18 are cross tied, and each pump can supply fuel to either Diesel 1A or 18.
FPC-P-lA, 18 The Fuel Pool Circulation (FPC) pumps take suction on the spent fuel pool and discharge through the FPC heat exchangers and, during normal opera-tion, through the Fuel Pool Filter/Demineralizers.
Page 3-6 R vision 0 3.5 Pum Inservice Test Tables The Test Table is the heart of the Pump- Test Proqram. It oresents a graphic display of the type and frequency of testing which the Supply System intends for its Class 1, 2 and 3 pumps. The Table incorporates the exceptions requested in Section 3.6 {Relief Requests).
WNP-2 Pum Inservice Test Table IMP Parameter Lubrication Pump ASNE Code Inlet Discharge Differential Fiowrate, Vibration, Bearing Pump Level/ Relief Ident. Class Pressure, Pressure, Pressure, Temperature Speed, Pressure Request(s)
Pi Po Q V Tb R HPCS-P-1 2 N/A NPCS-P-2 3 H/A N/A N/A NR 4,5 LPCS-P-1 2 N/A NR RHR-P-2A 2 H/A RHR-P-28 2 N/A RHR-P-2C 2 N/A NR SLC-P-lA 2 H/A N/A SLC-P-1B 2 N/A H/A N/A NR SW-P-lA 3 H/A N/A NR 4,5 SM-P-16 3 N/A N/A N/A RCI C-P-1 2 Q Q Q Q Q DO-P-lA 3 Q See Note A Q Q Q H/A Q
DO-P-18 3 See Note A Q N/A NR DO-P-2 3 See Note A Q H/A NR FPC-P-IA 3 Q Q Q NR Q FPC-P-18 3 H/A NR
Page
-
3-7A R
~Le end quarterly (92 day interval) test A Annual test N/A = Not applicable. See Relief Requests NR Not required IWP - 4400 does not require pump speed measurement if pump's directly coupled to a constant speed motor driver.
Note A:
Storage Tank levels will be recorded and correlated to pressure in order to determine Pi and b,P.
Page 3-8 Revision 0 3.6 Pump Test Pro ram Relief Re uests Relief Requests identify Code requirements which are impractical for MNP-2 and provide technical justification for the requested exception.
Mhere appropriate, they also propose alternate testing to be performed in lieu of the Code requirements.
Page 3-9 Revision 1 RELIEF RE(UEST RP-1 (Deleted)
Page 3-10 R
RELIEF RE(UEST RP-2
~Pum (s)
SLC-P-lA SLC-P-1B Section XI Code Requirement for which Relief is re uested Measure pump inlet pressure, Pi, and pump differential pressure, <P.
( IMP-3100) .
Bases for Re uest
- 1. The SLC pumps are positive displacement pumps which, at a constant speed, deliver essentially the same capacity at any pressure within the capabil-ity of the driver and the strength of the pump. The SLC pumps are di-rectly coupled to constant speed drive motors.
- 2. Surveillance requirements specify system alignments which assure adequate NPSH for the pumps.
- 3. There is no provision for suction pressure instrumentation.
- 4. Acceptable discharge pressure and flowrate will suffice as proof of adequate suction pressure.
Alternate Testin Proposed Pump dischar ge pressure and flowrate will be measured and recorded during testing.
ualit /Safet Im act Measurement of these parameters assures acceptable level of quality and safety since inadequate suction pressure would be indicated by erratic discharge pressure indication, subnormal flow rates and increased pump vibration and noise.,These abnormal indications will be investigated and corrected as required by IWP-3200.
Page 3-11 Revision 1 RELIEF REQUEST RP-3 (Oeleted)
Page 3-12 R
RELIEF RE(UEST RP-4
~Pum (s)
HPCS-P-l, RHR-P-2A, SW-P-1A, 00-P-1A FPC-P-1A HPCS-P-2, RHR-P-2B, SW-P-IB, 00-P-IB FPC-P-1B L PCS-P-1, RHR-P-2C, 00-P-2 Section XI Code Requirement for which Relief is Re uested Measure bearing temperature and vibration. (IWP-3100)
Bases for Re uest
- l. Except for FPC pumps, these pumps are vertical turbine ("deep well" ) type pumps and are immersed in the fluid being pumped. This precludes measur-ing pump bearing vibration except for inboard bearings.
- 2. IWP-4300 only requires temperature measurement of "centrifugal pump bearings outside the main flow path". The outboard and intermediate bearings of all pumps are in the main flow path. Therefore, temper ature measurement of these bearings is not required. The inboard bearings of the RHR pumps, LPCS-P-I and HPCS-P-1, are cooled by the seal injection water which returns internally to the discharge flow. The inboard bearing on HPCS-P-2 (the head bearing), SW-P-lA and 1B, and 00-P-1 A, 1B, and 2 are cooled by the pumped fluid which returns to the discharge flow with no provision for temperature measurement.
- 3. Although the FPC bearings are accessible, bearing housing temperature is not necessarily an accurate predictor of bearing condition. Hence, temperature measurement is an unnecessary requirement with unreliable results.
Alternate Testin Pro osed
- l. Except for FPC pumps, axial and radial vibration velocity measurement will be taken at the outboard bearing of the pump's motor. Radial vibration velocity measurements will be taken as close as practical to the inboard pump bearing.
- 2. Vibration velocity measurements will be taken on the inboard and outboard bearings of the FPC pumps.
3 Alert level will be 0.157 ~ Vb 4 0.314 in/sec. Required action level will be Vb ~ 0.314 in/sec. The General Machinery Vibration Severity Chart is provided for information purposes.
Page 3-12A Revision 0 gualit /Safet Impact Measurement of vibration velocity provides more concise and consistent information with respect to pump and bearing condition. The usage of vibration velocity measurements can provide information as to a change in the balance of rotating parts, misalignment of bearings, worn bearings, changes in internal hydraulic forces and general pump integrity prior to the condition degrading to the point where the component is jeopardized.
Hearing temperature does not always predict such problems. An increase in bearing temperature may not occur until the bearing has deteriora ed to a point where additional pump damage may occur. Hearing temperatures are also affected by the temperatures of the medium being pumped, which could yield misleading results. Vibration readings are not affected by the temperature of the medium being pumped, thus the readings are more consistent. The oroposed alternate testing riill result in the maximum meaningful data regarding pump bearing condition. Since vibration velocity analysis is more predictive in nature than bearing temperature measurement, 'he alternate testing serves to increase levels of safety and quality.
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Page 3-13 R
RELIEF RE/VEST RP-5 Pump(s)
HPCS-P-2 SW-P-1A SW-P-IB Section XI Code Requirement for which Relief is Re uested Measure pump inlet pressure, Pi, and differential pressure, b,P. ( IWP-3100)
Bases for Re uest (I) SW-P-lA, 18 and HPCS-P-2 are vertical turbine type pumps which are im-mersed in their water source. They have no suction line which can be instrumented.
(2) Technical Specifications will state minimum allowable spray pond level to assure adequate NPSH and cooling water supplies.
(3) Difference between allowable maximum pond level and minimum level is only six (6) inches of water or 0.2 psi. This small difference will not be significant to the Test Program and suction pressure will be considered essentially constant.
(4) Acceptable flowrate and discharge pressure will suffice as proof of adequate suction pressure.
Alternate Testin Pro osed Spray pond level and pump discharge pressure will be recorded during the test-ing of these pumps.
ualit /Safet Im act The effect of granting this request will be to introduce an error of 0.5 ft./500 ft. = 0.1X at rated discharge flow for SW-P-1A and 1B and an error of 0.5 ft/135 ft. = 0.37K for HPCS-P-2. These small errors will not signifi-cantly impact the quality of test results nor jeopardize the safety of the pub 1 i c.
Page 3-14 3.7 Pro osed Pum Test Flow Paths These flow paths are proposed for use during pump testing and may be used during the valve test program. The valve alignment shown on these draw-ings reflect valve position during testing. Valve position during opera-tions may be different. Surveillance procedures will define actual flow paths.
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B 8 R ORIG. HIGH PRESSURE CGfif !it'(iAY LOFTI PRESSURI=- CO'0" HAPP'7 PRV A
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V-110A V-31A liO-SA RHR-P-2A PRV B
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Page 3- 25 Revision I 3.8 Records of Inservice Tests Records of Pump Inservice Test results will be maintained in accordance with Article I'I!P-6000-af the Code. A file will be established for each pump and wi,ll include:
- 1) Pump identification by eauipment piece number, manufacturer, and serial number.
- 2) Inservice test plans. This may be by reference to the surveillance test procedure by which the pump is tested.
- 3) Summaries of corrective action.
The Pump Inservice Test Program, associated surveillance test procedures and results will be kept at the INP-2 plant site. For informational
'purposes, a sample pump test data sheet is provided.
,L II 0
Page 3-26a SAMPLE PUMP TEST DATA SHEET Pump IO Date Action~ Alert* Measured Init.
Parameters Ran e Ranqe Value Pump Suction Press (PI ) N/A N/A Pslg Before Pum Start Calib. Due Date Pump Suction Press (Pr .) N/A N/A Pslg Durin Test Calib. Oue Date Pump Discharge Press (PI ) N/A N/A Pslg Calib. Due Date Calculated Pump b. P psiD psiO pslo line 3 - line 4 System Flow (FI )m gpm gpm gpm Calib. Oue Date Pump Bearing Vibration See Reverse Side Lubrication Level or Pressure Satisfactory Unsatisfactory COMMENTS:
,
- If deviations fall within the ALERT RANGE, the test frequency is increased to once each 45 days. If deviations fall within the ACTION RANGE, the pump shall be declared inoperable and the deviation investigated and/or corrected.
Where flow is calculated rather than measured, record identification numbers and calibration due date of'nstruments used to collect data (e.g., level indicator, stopwatch).
PUMP VIBRATION DATA Page 3-266 Revision 0 TEST E Q Ul PMENT USED OPERATING CONDITIONS Volts Amps Rpm Sys. Temp.
Temp; Outbd. Bear. o Temp. Outbd. BBar.
Cal ibration Due Date EQUIPMENT SKETCH
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WNP-2 Valve Inservice'est 'Prog. am Pro ram Devel o ment Phil osooh Washington Public Power Supply System Nuclear Project Unit 2 (WNP-2) is a Soiling Water Reactor being constructed in compliance with the ASME Boiler and Pressure Vessel Code. The Code r quires periodic testing of certain safety related valves in order to verify their operability and physical integrity. The WNP-2 Valve Inservice Test Program satisfies these requirements and conforms to FSAR commitments ;or valve testing.
The Program will detect potentially adverse changes in the mechanical condition of valves within the scope of -Section XI, Subsection IWV of the Code. The scope includes all valves "which are required to perform a specific function in shutting down a reactor to the cold shutdown condi-tion or in mitigating, the consequences of an accident". Mary valves users in normal shutdown operations are not necessarily "required" nor would they necessarily be available for that purpose. Hence, the scope of, IWV is restricted to valves required to shutdown the r ac.or in emergency situations and to mitigate accident consequences .
To generat the WNP-2 Program, all ASME Class 1, 2 and 3 valves were analyzed to determine the required +ype and frequency of t sting for each valve. The valves to be tested under Section XI, Subsection IllV commi+-
ments are listed, by system, in the Valve Test Tables (Section 4.4). The Tables schedule only valve exercise tests. Leak rate testing mandated by Section XI will be incorporated into a WNP-2 unified lea!< rate testing program which .vi ll satisfy Section XI and other requirements.
The HNP-2 FSAR commits to meeting the . equi. ements of both 10 CFR 50, Appendix J(1), and of Section XI. Each of these documents addresses particular but slightly different concerns with respect to valve leak-age. Each contains guidance for valve leak rate testing. Appendix J is primarily concerned with lea<age out of containment subsequent to a Loss-of-Coolant Accident (LOCA). It requires leak rate testing of con-tainment isolation valves at the maximum differential pressure (dP) expected during an accident.Section XI requires leak r ate testing o:
all valves for which seat leakage "is limited to a specific maximum amount" and that testing be performed at the valves'perating EP unless II Title 10, Code of Federal Regulations, Part 50, Appendix J.
"Primary Reac+or Containment Leakage Testing for !!ater - Cooled Power Reactors."
Page 4-2 a lowered.P can be shown to give conservative results. OperatingaP may be many times the maximum post-LOCA b. P. Finally, plant Technical Specifications also address leak 'rate testing and impose specific testing requirements (e.g. excess flow check valve operability demonstration; testLP for drywell-wetwell downcomer vacuum breakers).
The testing requirements imposed by the various sources are not identical nor are they mutually exclusive. It is anticipated that Appendix J test-ing may satisfy Section XI leak rate testing in some instances. How-ever, some valves may require both Appendix J and Section XI testing.
Section 4.6 identifies valves which, under the scope of Section XI, Sub-section IWV, are subject to leak rate testing beyond Appendix J require-ments. Relief valves are not required to be leak rate tested (IWV-3512) subsequent to bench testing and are not include'd in Section 4.6.
Normally closed, manually operated containment isolation valves are excluded since these valves are subject only to Appendix J testing. For implementation purposes, the test frequencies mandated in Appendix J, S'ection XI and the Technical Specifications are the same. Leak rate testing will, in general, be performed during outages although some valves may be amenable to leak testing during power operations.
Similar testing frequencies and overlapping requirements necessitates a, unified leak rate testing program which will maximize compliance with the various commitments, provide consistancy in test methodology and reduce duplication of effort. The Supply System is actively developing a uni-fied program which will be submitted for review at a later date. Proce-dures to implement this program are being prepared.
Verification that position indication agrees with actual valve position will be accomplished biannually as part of the valve exercise tests.
Although the tables in Section 4.4 specifically designate position indi-cation verification only for certain manually operated valves and check valves, the position indication for power operated valves will be checked biannually during an exercise test.
The Code recognized that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements. The relief requests for the Valve Inservice Test Program (Section 4.5) identify testing impracticalities, provide technical basis for the request and propose alternate testing where warranted;- Most of the requests ask only for the postponement of test-ing, not cancellation.
The Supply System is confident that the WNP-2 Valve Inservice Test Prp-gram complies qigh the intent of all applicable codes, regulations,(>>
and guidelines'l3) and that it will make a positive contribution to the safe operation of the plant.
10CFR 50:55 a(g)(2)
NRC Staff guidelines for excluding exercising (cycling) tests of certain valves during Plant operations.
Page 4-3 R
4.2 Pro ram Im lementation The Valve Test Program will be executed as part of the normal plant sur-veillance routine. Two types of tests will be conducted as part of the Valve Test Program:
- 1) Valve Operability Tests
- 2) Valve Leak Rate Tests tiall The Operability Tests will verify 1) the valve responds to control commands, 2) the valve stroke time is within specific limits and, 3) remote position indication accurately reflects the observed valve position. Base line data for stroke times will be obtained from ini-Valve Operability Tests . The initial Valve Operability Tests will meet the requirements for preservice testing ( IWV-3100). Where applicable, acceptance criteria for initial stroke times will be within the limits specified in Table 6.2-16 of the WNP-2 FSAR. Otherwise, the Supply System will specify acceptable times. When these times are established, they will be inserted in the Valve Test Tables under the Stroke Time column.
Remote valve position indication will be verified ever y two years.
Manually operated valves with remote position indication have been included in this program.
Fail safe valves will be tested by observing the valve operation upon loss of electrical, pneumatic or hydraulic actuating power. In most cases, loss of electrical powe~ causes loss of actuating fluid and can be accomplished using normal control circuits.
Valve leak rate baseline data will be obtained in accordanc'e with IWV-3100 and accepted industry practice. Leak rate acceptance criteria will be specified by the Owner.
4.3 Pro ram Administration The Valve Inservice Test Program will be administered in a manner analogous to the Pump Inservice Test Program.
Page 4-4 Revision 0 4.4 Valve Test Tables The Valve Test Tables are th essence of the Supply System's Program to meet ASt1E Section XI, Subsection IHV requirements. The Tables reflect the positions taken in support of tie relief requests. To aid the reader in the interpretation of the Tables, brief explanations of the Table headings and abbreviations are provided.
I Cl
Page 4-5 Revision 0 (1) Valve Number Each piece of equipment in tlie plant has a unique "tag" number which identifies the system to which the equipment belongs, the type of equipment (flow control valv FCV, relief valve = RV, rupture disc = RD, etc.), and a unique serial number.
(2) Class ASME Code Class oer Section III of the ASME Boiler and Pressure Vessel Code. These are roughly equivalent to the safety classes defined in Chapter 3 of the FSAR.
(3) Coordinates The specific coordinates of each valve are supplied to ;acilitate location of'he valves on the flow diagram provided.
(4) Valve Category Categories are defined by ASME Section XI, subsection INV. Each valve has specific testing requirements which are determined by the category to which i belongs.
(5) Siz Nominal pipe diameter to which the valve connects is given in inches.
(5) ~Valve T e The following abbreviations are used to describe valve type:
BF = Butterfly valve GT = Gate Valve CK = Ch.ck valve RD = Rupture disc.
DIA = Diaphragm valve RV = Relief Valve GB = Globe valve S/R = Safety/Relief Valve SV = Solenoid Valve
Page Revision
'-6 0 The following abbreviations are used +o describe actuator types. Valves mav be actuated in more than one way.
AO = Air ooerated HO = Hydraulic operated i~1AN = Manually operated MO = Motor operated SA = Self actuated (actuated by a change in system parameters such as flow or pressure, e.g., chec'< and relief valves).
SOL = Solenoid operated-(8) Normal Position Valves may be either normally open (0) or normally closed (C). Throttle valves are not included in +he scooe of this program since they are either passive or regulating type valves. Both types of valves are exempt from INV testing ( IIJV-2100).
- 19) This column defines the operatino modes as defined by the Technical Soecifications, during which, the valve may be safely tested. See below for the definition o, "all," "CSD" and "Refuel."
~eceend t5eanine All Testing is approved during all operating modes and wi 11 be conducted on a quarterly basis, as permitted by olant status.
Page 4-7 Revision 0 CSD Cold shutdown. Guidance >or Inservice 1I valve testing at cold shutdown is: Valve testing should commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after cold shutdown is achieved and continue until complete or until plant is ready to return to power. Comp 1 et i on n.
all valve testing is not a prerequisi.e to return to power.
Any testing not completed at one cold shutdown should be performed durinq the subsequent cold shutdowns to meet the Code specified testing requency.
Refuel Test will be conducted during refueling outages but at least every two years. Cer-tain work which is nominall.y scheduled for a refueling outage may be performed at other times when plant conditions permit.
The two year minimum frequency will be maintained.
IMV-3620 Test frequency will be according to vendor specifications.
(10) Test Testing requirements identified for the valve are identified here.
S/E Stroke exercise; valve timing not, relevant.
Page 4-8 R
S/T Stroke time; valve must meet stroke timing requirements specified in the FSAR or else-where.
Bench Test Relief valves will be tested in accordance with IWV-3500 requirements.
IWV-3620 Rupture disc will be tested in accordance with Section XI, Subsection IWV, paragraph 3620.
Pos Ind Position Indication verification only.
Used only for manual valves. Power oper-ated val ves 'osi ti on indi cati on wi 1 1 be verified biannually during exercise test.
4 r (ll) Stroke Time Reference stroke time will be listed where
( ) appears . Values wi 1 1 be determined during initial surveillance testing and will comply with limiting values of full stroke time specified in the FSAR, Techni-cal Specifications or other commitment documents (12) Notes Generally self explanatory, e.g.,
NO = Normally open FO = Fails open NC = Normally closed FC =. Fails closed (13) Re uests for Relief Cross references documentation which re-quests waiver of certain code require-ments. A valve may have more than one associated relief request.
U il
System Name CONTROL AND SERVICE AIR Dug. No. M510 Page 1 of 1 a ve equests Valve fiumber Class Coordinates ~~0 Category Size Inches Valve T e Actuator T e Normal Position Test Durin Test Stro1<e Time Notes For Relief CAS-V-453 2 KB X 1 SV SOL C ALL S/E N/A I CAS-CVX-82e 2 X X CK SA ALL, S/E N/A
System ttame DIESEL OIL Nl0 HISC. DO Dwg. No. I4 512 Paqe 1 of 1 a ve equests Valve ~Cate or Size Val ve Actuator ttorma1 Test Stroke For ttumber Class Coordinates A 8 C 0 Inches T e T e Position Durin Test Time Notes Relief 00-V-IA 3 03 X X 1 1/2 CK SA C ALL S/E tt/A 00-V-18 03 X X 1 1/2 CK ALL S/E N/A r
DO-V>>IO HS X X 1 I/2 CK ALL S/E N/A DO-V-40A 3 I 1/2 SV SOL ALL S/E N/A DO-V-408 3 E3 1 1/2 SV SOL ALL S/E N/A DO-V-43 tl6 SV SOL ALL S/E N/A R7 'CD
(~ ID CD Dr CD C
CD
System Name REACTOR CORE ISOLATION COOLING SYSTEM RCIC Dwg. No. M 519 Page 1 of 2 a ve eques s Valve Number Class Coordinates ~I Category C D Size Inches Valve T e Actuator T e Normal Position Test Burin Test Stroke Time Notes For Relief RCIC-V-1 2 El 1 X 3 GT MO 0 ALL S/E N/A Rapid Acting RCIC-V-8 F6 GT MO ALL>> S/T ( )
RCI C-V-10 2 B14 GT HO ALL S/T (NA)
RCIC-V-11 2 813 X X CK SA ALL S/E N/A RCIC-V-13 1 GT HO ALL S/T ( )
RCIC-V-19 2 E7 GB HO ALL S/T ( )
RCI C-V-198 2 J6 1/2 ALL GT S/T ( )
RC I C-V-21 2 EB X X CK SA ALL S/E N/A RCIC-V-22 2 JB HO ALL S/T ( )
RCIC-V-28 2 08 X X 1 1/2 CK SA ALL S/T N/A RCI C-V-30 2 C7 X X ALL CK S/E N/A RCIC-V-31 2 C7 GT HO ALL S/T ( )
RCI C-V-40 2 08 X X 10 CK ALL SA S/E N/A RCI C-V-45 2 Fl1 ALL*
GB HO S/T ( )
RCI C-V-46 2 F1 1 GB MO C ALL S/T ( )
RCIC-V-59 2 J9 GT HO ALL S/T ( )
O
- Valves marked with an ASTERISK extend beyond a 3 month period,
(*) close automatically if not Reactor Vessel Pressure is less than 47 psig. Therefore, if Cold Shutdown conditions IWV testing frequency may be met. However, valves will be tested prior to resuming power operations
( IWV-3416)
System Name REACTOR CORE ISOLATION COOLING RCIC Owg. No. 519 2-M Page 2 of
~I ~
alve Requests Valve Cat~ear Si ze Valve Actuator Normal Test Stroke For Number Class Coordinates Inches T e T e Position Durin Test Time Notes Relief'CIC-V-63
"
1 N3 X 10 GT MO 0 ALL* S/T ( )
RC I C-V-64 1 G6 10 HO ALL* S/T ( )
RCIC-V-65 1 H6 X X CK AO/SA C ALL S/E N/A RCIC-V-66 I J4 X X CK AO/SA CSD S/E N/A RC I C-V-68 2 E7 10 GT HO ALL S/T ( )
RCIC-V-69 2 07 1-1/2 GT MO ALL S/T ( )
RCI C-V-76 I N3 GB HO ALL* S/T ( )
RCIC-V-086 2 A13 X X CK SA ALL S RCIC-V-110 2 E7 GT ALL*
HO S/T ( )
RCIC-V-113 2 E6 ALL*
GT HO S/T ( )
RCIC-RO-I 2 D11 10 RUPTURE SA C I WV-3620 I WV-3620 N/A OISC RCIC-RO-2 2 C12 X 10 RUPTURE SA C IWV-3620 IWV-3620 N/A OISC RCIC-RV-17 2 C13 1xl RV SA C REFUEL BEN( N N/A TEST RCIC-RV-18 2 09 3/4 x I RV C REFUEL BENCII N/A TEST
- See note on RCIC System page I of 2.
System Name LOW PRESSURE CORE SPRAY SYSTEH LPCS Dug. No. M520 Pally .1 of Va ve Requests Valve Cat~eo~r Size Valve Actuator Normal Test Stroke For Number Class Coordinates )( IM: 0 Inches T e T e Position Durin Test Time Notes Relief LPCS-V-1 2 Dll X 24 GT HO 0 ALL S/T ( )
LPCS-V-3 2 B13 X X 16 CK SA ALL S/E N/A LPCS-V-5 1 G11 12 GT MO ALL 5/T ( )
LPCS-V-6 1 ll9 X X 12 CK AO CSD S/E N/A LPCS-'V-12 2 F14 GB HO ALL 5/T ( )
LPCS-V-33 2 C12 X X 1 1/2 SA ALL S/E N/A LPCS-V-51 1 H9 12 GT 0 REFUEL POS IND N/A LPCS-FCV-11 2 B13 GB ALL S/T ( )
LPCS-RV-18 2 F12 1 1/2 x 2 RV C REFUEL BENCH N/A TEST LPCS-RV-31 2 C12 RV C REFUEL BENCH N/A TEST
System Name HIGH PRESSURE CORE SPRAY SYSTEH HPCS Owg. No. H520 Paqe a ve Requests Valve Cat~e~or Size Valve Actuator Normal Test Stroke For Number Class Coor dinates )( 8 0 0 Inches T e T e Position Burin Test Time Notes RelieF HPCS-V-1 2 C6 X 14 GT HO 0 ALL 5/T ( )
HPCS-V-2 2 C6 X X 20 CK ALL S/E N/A HPCS-V-4 1 G7 12 GT HO ALL S/T ( )
HPCS-V-5 1 X X 12 CK AO CSO S/E N/A HPCS-V-7 2 CS X X 1 1/2 SA ALL 5/E N/A HPCS-V-10 2 E3 10 GB ti0 ALL S/T ( )
HPCS-V-11 2 E3 10 GB ALL 5/T ( )
HPCS-V-12 2 85 GT ALL 5/T ( )
HPCS-V-15 2 07 18 GT HO ALL S/T ( )
HPCS-V-16 2 E6 X X 24 CK ALL 5/F. H/A HPCS-V-23 2 12 GB ALL S/T ( )
HPCS-V-24 2 85 X X 16 CK ALL 5/E N/A HPCS-V-28 3 H524 Rev. 19 SA ALL S/E N/A J5 HPCS-V-51 1 HB 12 GT flan 0 REFUEL POS INN N/A HPCS-RV-14 2 C6 1X1 RV SA C REFUEL BENCH N/A TEST HPCS-RV-35 2 C4 1x2 RV C REFUEL BENCH N/A TEST
System Name RESIDUAL IIEAT REHOVAL SYSTEH RHR Dwg. No. H521 Page f ef Valve Number RIII-V-3A Class 2
Coordinates J13
~ a ve Cateqo~r X
0 Size Inches 18 Valve T
GT e
Actuator T
HO e
Normal Posi t ion 0
Test Dur inn ALL Test S/T Stroke Time
( )
Notes Requests For RelieF RIII-V-38 2 J4 18 GT HO ALL S/T ( )
RNR-V-4A 2 E 11 24 GT HO ALL S/T ( )
RIIR-V-48 2 06 24 GT HO ALL S/T ( )
RIIR-V-4C 2 011 24 GT HO ALL S/T ( )
RIIR-V-6A 2 C12 18 GT HO ALL S/T ( )
RIII-V-68 2 C6 18 GT HO ALL S/T ( )
RIB-V-8 F11 20 GT HO CSD S/T ( )
RIIR-V-9 F10 GT HO CSD S/T ( )
RIIR-V-11A 2 F12 GT HO ALL S/T (
RIIR-V-118 2 E7 GT HO ALL S/T ( )
RHR-V-16A 2 16 GT HO ALL S/T ( )
RIS-V-168 2 F6 16 GT HO ALL S/T ( )
RNR-V-17A 2 II10 16 GT HO ALL S/T ( )
RIIR-V-178 2 F6 16 GT HO ALL S/T ( )
System Name RESIDUAL IIEAT REMOVAL SYSTEM RIIR Ikvg. No. H521 Page 2 of 6 a ve equests Valve Cate or Size Valve Actuator Normal Test Stroke For Number Class Coordinates A 8 D Inches T e T e Position Burin Test Time Notes Relief RIIR-V-21 2 E11 X 18 GB MO C ALL S/T ( )
RIIR-V-23 1 H7 GB HO CSD S/T ( )
RIIR-V-24A 2 E12 18 GB HO ALL S/T ( )
RHR-V-248 2 E6 18 MO ALL S/T ( )
RIIR-V-27A 2 E11 GT HO ALL S/T ( )
RIIR-V-278 2 E7 GT HO ALL S/T ( )
RNR-V-31A 2 813 X X 18 CK SA ALL S/E N/A RIIR-V-318 2 X X 18 CK SA ALL S/E N/A RIIR-V-31C 2 X X 18 CK ALL S/E N/A RIIR-V-40 2 G4 ~ 4 GB MO ALL S/T. ( )
RIIR-V-41A 1 G10 X X 14 CK AO CSD S/E N/A RIB-V-418 1 GB X X 14 CK AO CSD S/E N/A RIIR-V-41C 1 G10 X X 14 CK AO CSO S/E N/A RIIR-V-42A 1 G11 GT MO ALL S/T ( )
System Name RESIDUAL MEAT REMOVAL SYSTEM RIIR Owg. No. M521 Page 3 of 6 a ve equests Valve Cat~ear Size Valve Actuator Normal Test Stroke Fnr Number Class Coordinates ~WC D Inches T e T e Position Burin Test Time Notes Rel lef RIIR-Y-428 1 G7 X 14 GT HO C ALL S/T ( )
RNR-V-42C 1 G11 14 GT HO ALL S/T ( )
RIIR-V-46A 2 012 X X CK ALL S/E N/A RNR-V-468 2 E6 X X CK ALL S/E N/A RIIR-Y-46C 2 Dll X X SA ALL S/E N/A RIIR-V-47A 2 J14 18 GT HO ALL S/T ( )
RIIR-V-478 2 J3 18 GT HO ALL S/T ( )
RIIR-V-48A 2 J13 X, 18 GB MO ALL 5/T ( )
RIIR-V-488 2 JS 18 GB ALL S/T " ( )
RIIR-V-49 2 GT MO S/T ( )
RIIR-Y-50A 1 G10 X X 12 CK AO CSO S/E N/A RIIR-V-508 1 GB X X 12 CK AO CSO S/E N/A RIIR-V-53A 1 G11 12 MO CSO S/T ( )
RIIR-V-538 1 G7 12 GB HO S/T CSO ( )
System Name RESIDUAL HEAT REMOVAL SYSTEM RHR Dwg. No. M521 Pa 9-e 4 of 6 a ve equests Valve Number Class Coordinates ~~D Cate<~or Size Inches Valve T e Actuator T e Normal Position Test Durin Test Stroke Time Notes For Relief RHR-V-60A 2 H12 X 3/4 SV SOL C ALL S/E N/A RHR-V-608 2 JS 3/4 SV SOL ALL S/E N/A RHR-V-68A 3 M524 REV. 19 16 GT MO ALL S/T ( )
H12 RHR-V-68B 3 M524 REV 19 16 GT MO ALL S/T ( )
Hll RHR-V-75A 2 H12 3/4 SV SOL ALL S/E N/A RHR-V-75B 2 d5 3/4 SV SOL ALL 5/E N/A RHR-V-84A 2 813 X X 1 1/2 CK ALL S/E N/A RHR-V-84B 2 B7 X X 1 1/2 CK ALL S/E N/A RHR-V-84C 2 X X 1 1/2 CK ALL S/E N/A RHR-V-89 2 X X 14 CK AO ALL S/E N/A RHR-V-101A 2 F14 X X CK SA ALL S/E N/A RHR-V-1018 2 F4 X X CK SA ALL S/E N/A RHR-V-103A 2 F14 X X CK ALL S/E N/A RHR-V-1038 2 F4 X X CK ALL S/E N/A
System Name Rf 5 IOUAL IIEAT RDIOVAL SYSTEII RIIR Owq. tin. tl521 nf 6 a vc .eqni sts Valve Cate or Size Valve Actnatnr ttnrmal Test Strnke Fnr Hunker Class Conrail inates A 8 0 Inches T e Tvne Pnsition Onrln Test Time ttntns Rclln~
RIIR-V-111A 1 09 X ln liT WN 0 REFUEL POS I'VO N/A Rt8-V-1118 1 ln GT 0 REFUEL PrIS INO N/A RI8-V-111C 1 ln GT 0 REFUFL POS I.'ID tl/A RI8-V-112A 1 G9 0 REFUEL POS INO N/A RI8-V-1128 1 GB 12 Gr NAN 0 RFFIIFL POS INO tl/A RI8-V-113 1 G9 20 GT IIAN 0 REFUE L POS Itin tl/A RI8-V-115 2 GT ALL S/T ( )
RIIR-V-116 2 J6 IIO ALL S/T ( )
RI8-V-124A 2 D14 1-1/2 GiB BIO ALL S/r ( )
RIIR-V-1248 2 Din 1-1/2 YO ALL 5/T ( )
RI8- Y-125A 2 04 l-l/2 IIO ALL S/T ( I RIL'l-V-1258 2 D4 l-l/2 ALL S/T ( )
RIIR-V-134A 2 G15 GiB HO ALL S/T ( )
RIIR-V-1348 2 F2 GB I!0 AI.I S/T ( )
RtlR-V-182 2 3/1 SV SOL ALL S/E I/A RI8-V- jj09 I F IU X X rK PFFIIr< S/F. Il/A
System Name RESIDUAL HEAT REMOVAL SYSTEM RHR Dwg. tlo. N521 Paq L of a ve equests Valve Size Valve Actuator Normal Test Stroke For Number Class Coordinates l~C
~Cate ~or 0 Inches T e T e Position Burin Test Time Notes RelieF RHR-FCV-64A 2 C12 X 3 GB NO 0 ALL S/T ( )
RHR-FCV-648 2 CS GB MO ALL S/T ( )
RHR-FCV-64C 2 CB GB NO ALL S/T ( )
RIS-RV-1A 2 J14 X 3/4 x 1 1/2 RV REFUEL BENOI N/A TEST RIS-RV-18 2 J3 X 3/4 x 1 1/2 RV C REFUEL BENCH N/A TEST RIS-RV-5 2 C11 1x2 RV C REFUEL BENCII N/A TEST RIS-RV-25A 2 F12 1x2 RV SA C REFUEL BEtICH N/A TEST RHR-RV-258 2 F6 1x2 RV C REFUEL BENCH N/A TEST RHR-RV-25C 2 E11 1x2 RV C REFUEL BEfICH N/A TEST RIS-RV-30 2 A7 >/qx 1 RV C REFUEL BENCH N/A TEST RHR-RV-36 2 G13 6x8 C REFUEL BEIICH tl/A TEST RIS-RV-BBA 2 E11 3/4 x 1 RV C REFUEL BENCH N/A TEST RHR-RV-888 2 E6 3/4 x 1 RV C REFUEL BENCH N/A TEST RHR-RV-BBC 2 C11 3/4 x 1 RV SA C REFUEL BENCH N/A TEST
System Name STANDBY LI UID CONTROL SLC Awg. No. H522 Paqe I of I a ve Requests Valve Cat~eor~ Size Valve Actuator Normal Test Stroke For Number Class Coordinates II IV C 0 Inches T e T e Position Durin Test Time Notes Relief SLC-V-IA ' E4 X 4 GB HO C ALL 5/T ( )
5LC-V-1B 2 D4 GB HO ALL 5/T ( )
SLC-V-4A 1 FB 1-1/2 5HEAR 5QUI BB C REFUEL INV N/A PLUG 3610 SLC-V-4B 1 DB 1-1/2 SIIEAR SQUIBB C REFUEL INV N/A PLUG 3610 SLC-V-6 F11 X X 1-1/2 CK C REFUEL 5/E N/A SLC-V-7 F13 X X 1-1/2 CK SA C REFUEL 5/E N/A SLC-V-8 F12 1-1/2 GT HAII 0 REFUEL POS IND N/A SLC-V-33A 2 F7 X X 1-1/2 CK ALL 5/E N/A SLC-V-33B 2 07 X X 1-1/2 CK SA ALL 5/E N/A SLC-RV-29A 2 E6 1x2 RV SA C REFUEL BENCII N/A TEST SLC-RV-29B 2 De lx2 C REFUEL BENCH N/A TEST
System Name REACTOR WATER CLEANUP RWCU Owg. No. H523 Paqe 1 of 1 a ve eques s Valve Ca~te ~or Size Valve Actuator Normal Test Stroke For Number Class Coordinates )( B C 0 Inches T e T e Position Ourin Test Time Notes Relief RWCU-V-1 1 F15 X 6 GT HO 0 ALL S/T ( )
RWCU-V-4 1 E15 GT HO ALL S/T ( )
RWCU-V-40 1 H11 GT HO ALL 5/T ( )
System Name STANDBY SERVICE 'WATER SW ling. No. H524 Page a ve eques s Valve Number Class Coordinates ~t Category:
C II Size Inches Valve T e Actuator T e Normal Position Test Durin Test Stroke Time Notes For Relief SM-V-1A 3 N5 X X 20 CK SA C ALL S/E N/A SM-V-1B G5 X X 20 CK SA ALL S/E N/A SW-V-2A N6 20 BF HO ALL S/T ( )
SM-V-28 G6 20 HO ALL S/T (
SW-V-4A E9 GT HO ALL S/T ( )
SW-V-4B G9 GT HO ALL S/T ( )
SM-V-4C F7 GT HO ALL S/T ( )
SW-V-12A G3 18 GT HO ALL S/T ( )
SW-V-12B G3 18 GT HO ALL S/T ( )
SM-V-24A G9 GT HO ALL S/T ( )
SM-V-24B Flo GT HO ALL 5/T ( )
SM-V-24C Klo .GT HO '0 ALL S/T ( )
SM-V-29 BF HO ALL S/T ( )
SM-V-34 Cl I I 1/2 GB SV ALL S/T ( )
SM-V-44 E9 GT HO ALL S/T ( )
SW-V-54 F7 HO ALL S/T ( )
System Name STANOBY SERVICE WATER SW Owg. Ho. H524 H607 Page 2 of 3 a ve eques s Valve Category Size Valve Actuator Normal Test Stroke For Number Class Coordinates ~1 Hl Inches T e T e Position Ourin Test Time Notes Relief SM-V-69A 3 G3 X 1& GT HO 0 ALi. S/T ( )
SM-V-698 F3 18 GT HO ALL S/T ( )
SM-V-70A G2 18 GT HO ALL S/T ( )
SW-V-708 F3 18 GT HO ALL S/T ( )
SM-V-90 HB GT HO ALL S/T ( )
SM-V-92 H9 X X CK SA ALL S/E N/A 9
SM-V-20'I 3 C14 1/2 SOL ALL S/E H/A 9
SM-V-202 3 C14 1/2 CK SA ALL S/E H/A 9
SW-V-203 3 C14 1/2 CK SA ALL S/E N/A 9 )
SM-V-204 3 C14 1/2 SV ALL S/E H/A 9 )
SW-V-206 3 815 1/2 SV SOL ALL S/E N/A 9
SW-V-207 3 815 CK SA Al.L S/E H/A 9 )
SW-V-208 3 815 1/2 CK SA ALL S/E N/A 9
SM-V-209 3 815 1/2 SV SOL ALL S/E N/A 9 )
SM-V-210 3 Al 1 1/2 SV SOL ALL S/E N/A 9 )
SW-V-211 3 Bll 1/2 SV SOL ALL S/E N/A
System Name STANDBY SERVICE MATER SM Owg. No. H524 H607 Page 3 of 3 a ve eques s Valve Category Size Valve Actuator Normal Test Stroke For Number Class Coordinates 3M/ C 0 Inches T e. T e Pos I t ion Our in Test Time Notes Relief g
SW-V-212 3 A14 X 1/2 SV SOL 0 ALL S/E N/A
SW-V-214 3 G8 BF AO ALL S/T ( )
SM-V-215 GB BF ALL SIT ( )
SM-V-216 BF ALL S/T ( )
SW-V-217 BF ALL S/T ( )
SM-V-75A 3 A13 GB ALL S/T ( )
SW-V-758 3 814 GB ALL S/T ( )
SW-V-187A 3 G14 ALL S/T ( )
SM-V-1878 3 C13 ALL S/T ( )
SM-V-188A 3'l13 3 GT ALL S/T ( )
SM-V-1888 012 GT ALL S/T ( )
(1) These valves are not yet installed and may not be installed until the first fuel outage. Above test program will be implemented after valves are installed and operable.
KI a n3 C EQ
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System Name REACTOR CLOSED COOLING lbg.
RCC No. MS25 Paqe 1 of I a ve equests Valve Number Class Coordinates ~8Cat~e or>> Size Valve Actuator Normal Test Stroke For C D Inches T e T e Position Durin Test Time Notes Relief RCC-V-5 2 D10 X 10 GT HO 0 CSD S/T ( )
RCC-V-21 2 D10 10 GT MO CSO S/T ( )
RCC-V-26 2 D11 X X 10 CK CSD S/E N/A RCC-V-40 2 D10 10 GT MO CSO S/T ( )
RCC-V-104 2 E10 10 GT MO CSD S/T ( )
RCC-V-129 3 E5 GT HO ALL S/T ( )
RCC-V-130 3 E6 GT HO ALL S/T ( )
RCC-V-131 3 E6 GT HO ALL S/T ( )
System I!arne FUEL POOL CODLIIIG SYSTEN FPC 0 t9. Uo. I4528 Pano 1 n~ 1 a ve Romaunt;t s Valve ~Cate eo Size Valve Actuator I!nrmal Teast Strn'ke Fnc IIunher Class Coordinates A 8 C 0 Inches T e T e Position Our Inn Test T{mn >Intns Rel ier FPC-V-112A 3 D12 X 6 CK SA 0 AI L 5/F. 8/A FPC-V-1128 3 D12 ALL 5/F. II!A FPC-V-153 2 811 GT ALL S/T ( )
FPC-V-154 2 811 GiT >ID ALI. S/T ( )
FPC-V-158 2 Cll GT ALL 5/T ( )
FPC-V-172 3 C9 GT 90 ALL S/T ( )
FPC-V-173 3 C8 GT !t!0 ALL 5/T ( )
FPC-V-175 3 C9 GT ALL S/T ( )
F PC-V-181A 3 014 GT 'IO ALL S/T ( )
F PC-V-1818 3 D14 GT ALL S/T ( )
FPC-V-184 3 C9 1!0 ALI 5/T FPC-RV-117A 3 Dll 3/4 x 1 SA C PEFUFL DEN"II 8/A TEST FPC-RV-1178 3 Cll 3/4 x 1 RV SA REFUEL 8ENrH II/O TEST
System Name CONTROL ROO DRIVE CRO HCU [kg. No. M528 Page I of g a ve eques s Valve Catego~r Si ze Valve Ac tuator Normal Test Stroke For Number Class Coordinates JM~. 0 Inches T e T e Position Durin Test Time Notes Relief CRD-V-10 2 K6 X 1 GB AO 0 ALL S/T ( )
CRD-V-11 F6 GB ALL S/T ( )
CRO-V-llOA 2 013 1-'1/2 SV SOL N/A CSO S/E N/A Normally energized 9 to ressurize cram a ve CRD-V-1108 2 013 1-1/2 SV SOL N/A CSO 5/E II/A diaphragms CR0-V-111 2 OI3 1-1/2 CK SA CSO S/E N/A CRD-RV-12 2 H6 3/4 x 1 SA C REFUEL BENCH N/A HCU-V-114 2 C2 X X SA ALL S/E N/A HCU-V-115 2 C5 X X CK SA ALL S/E N/A HCU-V-117 2 03 SV ALL S/E N/A HCU-V-118 2 D3 SV SV ALL S/E N/A HCU-V-120 2 C4 SV SV ALL 5/E N/A TYPICAL OF 185 CONTROL HCU-V-121 2 C4 ALL S/E N/A ROD DRIVE UNl TS HCU-V-122 2 C4 ALL S/E N/A HCU-V- l23 2 C4 SV ALL S/E N/A HCU-V-126 2 C4 GT AO ALL S/E N/A
System Name CONTROL ROD DRI VE CRD HCU Ihvg. No. H528 Page 2 of 2 Valve Requests Valve Number Class Coordinates ~~5Categorry Size Inches Valve T e Actuator T e Normal Position Test Durin Test Stroke Time Notes For Relief HCU-V-127 2 C3 GT AO ALL S/E H/A HCU-V-137 2 C4 X X CK ALL S/E H/A HCU-V-138 2 C4 X X CK SA ALL S/E N/A
System Name MAIN STEAM SYSTEM HS Dwg. tto. H529 page I of a ve eques s Valve Catego~r Size Valve Actuator Normal Test Stroke For ttumber Class Coordinates lM~. II Inches T e T e Position Durin Test Time Notes Relief HS-V-16 1 813 X 3 GT HO C ALL S/T ( )
HS-V-19 814 GT HO ALL S/T ( )
HS-V-22A I F12 26 ALL S/T ( )
HS-V-228 I E12 26 GB ALL 5/T ( )
HS-V-22C 1 F5 26 GB AO ALL S/T ( )
HS-V-22D 1 E5 26 GB ALL 5/T ( )
MS-V-28A F13 26 GB ALL 5/T ( )
HS-V-288 1 E13 26 GB ALL 5/T ( )
HS-V-28C 1 26 ALL 5/T ( )
MS-V-280 1 E4 , 26 GB ALL 5/T ( )
HS-V-37 C6-Cl 1 X X 10 CK SA CSD S/E N/A TYPICAL OF 18 5 SERIES HS-V-38 C6-Cl 1 X X 10 CK CSD S/E N/A TYPICAL OF 18 5 SERIES HS-V-67A F13 1-1/2 GT HO ALL S/T ( )
HS-V-678 F13 1-1/2 GT HO ALL S/T ( )
HS-V-67C F4 1-1/2 . GT HO ALL 5/T ( )
System Name HAIN STEAN SYSTEH HS Dwg. No. H529 Page 7 of 3 a ve eques s Valve Number Class Coordinates ~f Hi Category Size Inches Valve T e Actuator T e Normal Position Test Burin Test Stroke Time Notes For Rel ief HS-V-67D 1 D4 X I- I/2 GT HO C ALL S/T HS-RV-IA F10 6 x 10 S/R AO/SA C REFUEL BENOI N/A TEST HS-RV-18 Ell 6 x 10 S/R AO/SA C REFUEL BENCH N/A TEST HS-RV-1C F6 6 x 10 S/R AO/SA C REFUEL BENCH N/A TEST HS-RV-1D E7 6 x 10 5/R AO/SA C REFUEL BENCH N/A TEST HS-RV-2A F10 6 x 10 S/R AO/SA C REFUEL BENCH N/A TEST HS-RV-28 E10 6 x 10 S/R AO/SA C REFUEL BENCH N/A TEST HS-RV-2C F7 6 x 10 S/R AO/SA C REFUEL BENCH N/A TEST HS-RV-2D E7 6 x 10 S/R AO/SA C REFUEL BENCH N/A TEST HS-RV-3A F9 6 x 10 S/R AO/SA C REFUEL BENCH N/A TEST HS-RV-3B E9 6 x 10 S/R AO/SA C REFUEL BENCH N/A TEST HS-RV-3C F7 6 x 10 S/R AO/SA C REFUEL BENOI N/A TEST HS-RV-30 EB 6 x 10 S/R AO/SA C REFUEL BENCH N/A
.TEST HS-RV-4A F9 6 x 10 S/R AO/SA C REFUEL BENCH N/A ADS VALVE TEST HS-RV-4B E9 6 x 10 5/R AO/SA C REFUEL BENCH N/A ADS VALVE TEST HS-RV-4C FB 6 x 10 S/R AO/SA C REFUEL BENCH N/A ADS VALVE TEST
- Tech Specs require stroking ADS Valves at least with Reactor steam dome pressure greater 'than every 18 months or equal to 100 psig.
0 System Name HAIN STEAH SYSTEH HS Dag. No. H529 Page 3 of 3 a ve eques s Valve Number Class Coordinates ~l ~J Category Size Inches Valve T e Actuator T e Normal Pos i t ion Test Burin Test Stroke Time Notes For Relief HS-RV-40 1 EB X 6 x 10 S/R AO/SA C REFUEL BENCH N/A ADS VALVE TEST HS-RV-SB Eg 6 x 10 S/R AO/SA C REFUEL BENCH N/A ADS VALVE TEST HS-RV-5C FB 6 x 10 S/R AO/SA C REFUEL BENCH N/A ADS VALVE TEST
- See note on previous page.
System Name REACTOR FEEDMATER SYSTEH RFM Dug. No. H529 Page I of I a ve equests Valve Number Class Coordinates ~I Cat~ear C D S I ze Inches Valve T e Actuator T e Normal Position Test Our in Test Stroke Time Notes For Relief RFM-V-10A 1 G12 X X 24 CK SA 0 CSO S/E N/A RFM-V-108 1 G5 X X 24 CK CSO 5/E N/A RFM-V-32A 1 G13 X X 24 CK AO CSO S/E N/A RFM-V-328 1 G5 X X 24 CK AO CSO S/E N/A RFM-V-65A 1 G13 24 GT HO CSO S/T ( )
RFM-V-658 1 G4 24 GT HO CSD S/T ( )
System Name REACTOR REC IRCULATION COOLING RRC HY Owg. No. N530 Paqe 1 of 2 a ve enuests Valve Number Class Coordinates ~I P6 Cateqory Size Inches Val ve T e Actuator T e Normal Position Test Durin Test Stroke Time Notes For Relief RRC-V-13A 2 C12 X X 3/4 CK SA 0 REFUEL S/E N/A RRC-V-138 2 B12 X X 3/4 CK 0 REFUEL S/E N/A RRC-V-16A 2 C14 3/4 GT 0 REFUEL S/T ( )
RRC-V-16B 2 3/4 GT 0 HO REFUEL S/T ( )
RRC-V-19 1 F ll 3/4 ALL S/E N/A RRC-V-20 1 F12 3/4 SV SOL ALL S/E u/A
System Name REACTOR REC IRCULATION COOLING RRC HY Owfl. No. II 530 Page 2 of 2 a ve Renuests Valve Size Valve Actuator Normal Test Stroke For Number Class Coordinates 3~K Cat~e ~or 0 Inches T e T e Pos I t 1 on Burin Test Time Notes Relief IIY-V-17A, 8 2 E4 X 3/4 5V SOL 0 CSO S/E N/A I, 10 HY-V-18A, 8 2 E4 3/4 SV SOL CSO 5/E N/A 1, 10 HY-V-19A, 8 2 E4 3/4 SV SOL CSO S/E N/A HY-V-20A, 8 2 E4 3/4 SV SOL CSD S/E N/A 1, 10 HY-V-33A, 8 2 E13 3/4 5V SOL CSO 5/E N/A 1, 10 HY-V-34A, 8 2 E13 3/4 SV SOL CSO S/E N/A 1, 10 HY-V-35A, 8 2 E13 3/4 SV SOL CSO 5/E N/A 1, 10 HY-V-36A, 8 2 E13 3/4 SV SOL CSO 5/E N/A 1, 10 R '22
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System Name FLOOR DRAIN RADIOACTIVE FDR Owg. No. H539 Page f of f a ve Reouests Valve Cate or SIze Valve Actuator Normal Test Stroke For Number Class Coordinates C 0 Inches T e T e Position Ourin Test Time Notes RelleF FDR-V-3 2 D6 X 3 GT AO 0 ALL S/T ( )
FOR-V-4 06 GT AD S/T ( )
System Name E UIPHENT DRAIN RADIOACTIVE EDR Dwg. No. M537 Paqe I of a ve equests Valve Number Class Coordinates ~I~Ca thor~
D Size Inches Valve T e Actuator T e Normal PositIon Test Durln Test Stroke TIme Notes For Relief EDR-V-19 2 09 X 3 GT AO 0 ALL S/T ( )
EDR-V-20 2 GT AO 0 ALL S/T ( )
System tlame PRIttARY COttTAIHNENT COOLItlG I'URGE CSP CEP Dug. No. N543 Pate 1 nf L a ve Renuests Valve Size Valve Actuator tlormal Test Stroke For ttumber Class Coordinates ~8 Ca~te o~r
- l. 0 Inches T e T e Position Burin Test Time Notes Relief CSP-V-5 2 C5 X 24 BF AO C ALL S/T ( ) tlC/FO CSP-V-6 814 BF AO C ALL S/T ( ) NC/FO CSP-V-7 X X CK AO/SA C ALL S/E N/A CSP-V-8 815 X X 24 CK AO/SA C ALL S/E tl/A CSP-V-9 86 24 BF AO ALL S/T ( ) NC/FO CSP-V-10 2 X X 24 CK AO/SA C ALL S/E N/A CEP-V-18 2 J13 GT AO ALL S/T { ) tl0/FC CEP-V-28 2 J13 GT AO ALL S/T ( ) HO/Fl'.
CEP-V-38 2 C14 GT ALL S/T ( ) NO/FC CEP-V-48 2 C14 GT AO ALL S/T ( ) NO/FC CVB-V-1A 2 812 X X 24 CK AO/SA ALL S/E N/A CVB-V-18 2 812 X X 24 CK AO/SA C ALL S/E N/A CVB-V-IC 2 812 X X 24 CK AO/SA C ALL S/E N/A CVB-V-1D 2 812 X X 24 CK AO/SA ALL S/E H/A CVB-V-IE 2 811 X X 24 CK AO/SA ALL S/E N/A CVB-V-1F 2 811 74 AO/SA C ALL S/F. N/A
System ttame PRIMARY COIITAINIIEttT COOLlttG & PIIRGE CVB Ihcg. No. H543 Paqe a ve equests Valve Cat~ear Size Valve Actuator ttormal Test Stroke For ttumber Class Coordinates ~~C 6 Inches T e T e Position Ourinn Test Time Notes Relief CVB-V-IG 2 811 X X 24 CK AO/SA C ALL S/E N/A CVB-V>>IH 2 811 X X 24 CK AO/SA C ALL S/E N/A CVB-V-IJ 2 89 X X 24 CK AO/SA -
C ALL S/E N/A CVB-V-IK 2 89 X X 24 CK AO/SA ALL 5/E N/A CVB-V-1L 2 88 X X 24 AO/SA C ALI. S/E N/A CVB-V-IM 2 BB X X 24 CK AO/SA C ALL S/E N/A CVB-V-1N 2 88 X X 24 AO/SA ALL S/E N/A CVB-V-IP 2 88 X X 24 CK AO/SA C ALL 5/E N/A CVB<<V-III 2 87 X X 24 AO/SA C ALL S/E N/A CVB-V-IR 2 87 X X 24 CK AO/SA ALL S/E N/A CVB-V-IS 2 87 X X 24 CK AO/SA C ALL S/E N/A CV8-V-1T 2 87 X X 24 CK AO ALL 5/E N/A PI-VX-250 2 F13 SV SOL ALL S/E N/A PI-VX-251 2 F13 SV SOL ALL S/E N/A PI-VX-253 2 F13 SV SOL ALL S/E N/A
System tlame PRIHARY CONTAIHIIENT COOLItlG B PURGE CVB PI Dug. tlo. H543 Paqe 3 oF 3 Valve Number PI-VX-256 Class 2
Coordinates F7
~h X
~
a ve Cat~e~or Size Inches 1
Valve T
SV e
Actuator T
SOL e
Normal Position 0
Test Durin ALL Test S/E Stroke Time N/A Notes eques s For Relief PI-VX-257 2 F7 SV SaL ALL S/E N/A P I-VX-259 2 SV ALL S/E N/A UM-NUHBERED 2 F12 X X CK ALL S/E N/A HAVE POSITIOII Utt-IINIBERED 2 F7 X X CK ALL S/E H/A PI-VX-262 2 E13 SV saL ALL 5/E N/A PI-VX-263 2 E13 SV SOL ALL S/E N/A PI-VX-264 2 E13 SV SOL ALL S/E N/A PI-VX-265 2 E14 ALL S/E H/A P I-VX-266 2 E7 SV SOL ALL S/E tl/A PI-VX-267 2 E7 SV SOL ALL S/E N/A PI-VX-268 2 E7 SY SOL ALL S/E N/A PI-YX-269 2 E6 SV SOL ALL S/E N/A
Sys tern Name CONTAINMENT ATHOSPNERE CONTROL (CAC Dog. No. H554 Page ACC IDENT HI TIGATION a ve eques s Valve Number Class Coordinates 7~~
Category Size Inches Valve T e Actuator T e Normal Position Test Ourin Test Stroke Time Notes For Relief CAC-V- IA 2 F15 X 2 OIA NO C ALL S/T ( )
CAC-V-18 2 Fl DIA IIO ALL S/T ( )
CAC-V-2 G10 GT HO ALL S/T ( )
CAC-V-2A 2 F12 OIA UO ALL S/T ( )
CAC-V-28 2 F5 OIA IIO ALL S/T ( )
CAC-V-4 EIO GT HO ALL S/T ( )
CAC-V-6 HIO GT HO ALL S/T ( )
CAC-V-8 D10 GT ALL S/T ( )
CAC-V-11 2 G6 GT HO ALL S/T ( )
CAC-Y-13 2 E6 GT HO ALL S/T ( )
CAC-V-15 ll6 GT MO ALL S/T ( )
CAC-V-17 2 GT MO ALL S/T ( )
CAC-V-318A 2 012 GT C REFUEL IND N/A CAC-V-3188 2 D12 GT MAN C REFUEL IND N/A CAC-FCV-1A 2 Hlo 2-1/2 ALL S/T ( )
System Name CONTAINNENT ATHOSPHERE CONTROL CAC Dwg. No. N554 Page a ve eques s Valve Category Size Valve Actuator Normal Test Stroke For Number Class Coordinates 1nches T e T e Position Dur in Test Time Notes Relief CAC-FCV-18 2 H6 2-1/2 GB HO C ALL S/T ( )
CAC-FCV-2A 2 Glo 2-1/2 GB HO ALL S/T ( )
CAC-FCV-28 2 G6 2-1/2 GB ALL S/T ( )
CAC-FCV-3A 2 010 2-1/2 HO ALL S/.T ( )
CAC-FCV-38 2 06 2-1/2 GB ALL S/T ( )
CAC-FCV-4A 2 F10 2-1/2 GB ALL S/T ( )
CAC-FCV-48 2 2-1/2 ALL S/T ( )
CAC-FCV-5A 3 F14 HO ALL S/T ( )
CAC-FCV-58 3 F2 GB ALL S/T ( )
CAC-FCV-6A 2 G12 ALL S/T ( )
CAC-FCV-68 2 G4 ALL S/T ( )
CAC-RV-63A 3 E12 X 1 x2 RV SA REFUEL BENCH N/A TEST CAC-RV-638 3 E4 lx2 RV SA C REFUEL BENCH N/A TEST CAC-RV-65A 3 D13 11/2x3 RV SA C REFUEL BENCH N/A TEST CAC-RV-658 3 1 1/2 x 3 RV SA C REFUEL BENCH N/A TEST
System Name CONTAINHENT INSTRUHENT AIR CIA tkg. No. H556 Page a ve eques s Valve Category Size Valve Actuator Normal Test Stroke For Number Class Coordinates Inches T e T e Position Ourin Test Time Notes ~
Relief CIA-V-20 2 J6 X 3/4 GB HO 0 ALL S/T ( )
CIA-V-21 2 J6 X X 3/4 CK SA 0 REFUEL S/E N/A CIA-V-24 N4-K4 X X 1/2 CK SA C REFUEL S/E N/A TYP. OF 4 SERIES CIA-V-30A 2 N6 1/2 GB HO ALL S/T ( )
CIA-V-308 2 F6 1/2 GB HO ALL S/T ( )
CIA-V-31A 2 H6 X X 1/2 CK SA 0 REFUEL S/E N/A CIA-V-318 2 X X 1/2 CK SA 0 REFUEL S/E N/A CIA-V-36 84-II4 X X 1/2 SA C REFUEL S/E N/A TYP. OF 18 SERIES CIA-V-39A 3 117 1/2 SV SOL ALL S/E N/A CIA-V-398 3 N7 1/2 SV SOL ALL S/E N/A CIA'-V-40 N5-85 X X 1/2 CK SA REFUEL 5/E N/A TYP. OF 7 SERIES CIA-V-41A 3 N7 X X 'I/2 SA REFUEL S/E N/A CIA-V-418 3 X X 1/2 CK SA REFUEI. S/E N/A
0 System tlame HAIN STEAM LEAKAGE COtlTROL MSLC Dug. No. M557 Page 1 of 1 a ve equests Valve Category Size Valve Actuator Normal Test Number Class Coordinates ~B C 0 Inches T e T e Position Our in Test Stroke Time Notes For Relief HSLC-V-lA 2 87 X 1-1/2 GT MO C ALL S/T ( )
MSLC-V-18 2 BS l-l/2 GT HO S/T ( )
MSLC-V-1C 2 D7 l-l/2 HO ALL 5/T ( )
HSLC-V-1D 2 05 1-1/2 GT HO C ALL S/T ( )
HSLC-V-2A 1 CB 1-1/2 GT HO ALL 5/T ( )
HSLC-V-28 1 CB 1-1/2 GT MO ALL 5/T ( )
HSLC-V-2C 1 ES l-l/2 GT HO ALL S/T ( )
HSLC-V-20 1 ES 1-1/2 "ALL GT HO 5/T ( )
HSLC-V-3A 1 C9 1-1/2 GT HO ALL S/T ( )
HSLC-V-38 1 CB 1-1/2 GT HO ALL S/T ( )
HSLC-V-3C 1 EB l-l/2 GT HO ALL 5/T ( )
HSLC-V-30 1 EB 1-1/2 GT HO ALL S/T ( )
HSLC-V-4 2 JS l-l/2 GT HO ALL S/T ( )
HSLC-V-5 2 JS 1-1/2 GT HO ALL 5/T ( )
HSLC-V-9 2 II5 1-1/2 GT HO ALL S/T ( )
HSLC-V-10 2 ll5 1-1/2 GT IIO "ALL S/T ( )
Page 4-43 Revision 0
(
4.5 Requests for Relief from Certain Code Requirements Relief Requests are presented to document differences between the Code and MHP-2's ~lalve Test Program. The requests include technical justification for the differences and, where appropriate, propose alternate testing.
Page 4-44 Revision 1 GENERAL RELIEF REQUEST (OELETED)
Page 4-45 Revision 1 REQUEST FOR RELIEF NO. RV-1 System Various Valves(s)
ASME Solenoid valves affected by this relief request are Classificati on identified in TABLE A.
Function Code Testing 1. Timing of valve stroke (IMV-3413)
Requirement Bases for 1. Solenoid valves are very rapid acting, with stroke Relief times much less than one second. It is meaningless to measure their stroke times "to the nearest second".
Alternate Testing 1. Valves will be full stroke tested. Satisfactory to be Performed operation of equipment downstream of the solenoid valve will constitute satisfactory valve operation.
ualit /Safet Im act The only valves in Table A for which timing might be an important parameter are the Category A valves which are containment isolation valves. However, these valves have position indication displayed in the Control Room and on the Transient Data Acquisition System. Furthermore, each of the Category A valves have backup valves which can be used to isolate the line should it be required.
The proposed exercise testing and regular position indication verification will provide adequate assurance of quality and public safety.
Page 4-46 R
RV-1 TABLE A Valve Code Class Cate or Function HY-V-17A, 8 Hydraulic supply for Reactor Recirculation Flow Control Valves 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 RRC-V-19 Reactor recirculation sampling Iso valve.
RRC-V-20 Reactor recirculation sampling Iso valve.
CIA-V-39A Cross ties between air and nitrogen C IA-V-398 headers.
DO-V-40A Diesel fuel oil day tank 3A inlet valve DO-V-408 Diesel fuel oil day tank 38 inlet valve DO-V-43 Diesel fuel oil day tank 3C inlet valve CRD-V-110A Back-up Scram Valve (Air Supply)
CR D- V-1108 Back-up Scram Valve (Air Supply)
Page 4-47 Revision 0 RV-1 TABLE A (Cont'd}
Valve Code Class Cate or Function PI-VX-251 Radiation moni or RAD-RE-128 inlet valve P I-VX-250 Radiation monitor RAO-RE-128 outlet valve PI-VX-253 Radiation monitor RAD-RE-128 outlet valve PI-VX-256 Radiation monitor RAO-RE-12A inlet valve PI-VX-257 Radiation monitor RAO-RE-1?A inlet valve PI-VX-259 Radiation monitor RAO-RE-12A outlet valve PI-VX-262 H2, 02 monitor inlet and outlet PI-VX-263 2 valves {S-SR-13)
P I -VX-264 PI-VX-265 P I-VX-266 H2, 02 monitor inlet and ou.let PI-VX-267 valves (S-SR-14)
P I-VX-268 PI-VX-269 CAS-V-453 Air supply to drywell - wetwell down-comer vacuum breakers.
RHR-V-60A Loop A sample (inboard)
RHR-V-608 Loop 8 sample (inboard)
RHR-Y-75A 8 Loop A sample (outboard)
RHR-V-758 8 Loop 8 sample {outboard)
RHR-V-182 Drain Vv between Valves isolating Service '~later from RHR
Page 4-48 ReYi sion 0 RV-1 TA8l E A (Cont'd)
.Valve Code Class Cate or y Function SM-V-201 Cooling Mater to H2, 02 analyzers SM I 204 S-SR-13, 14.
SM-Y-206 SM-V-209 SM-Y-210 SM-V-211 SLI-V-212 SM-V-213
Page 4-49 Revision I REQUEST FOR RELIEF NO. RV-2 System Various Emergency Core Cooling Systems Valve(s)
ASME Valves affected by this relief request are identified in Cl assi fi cati on TABLE 8.
Function Code Testing Quarterly valve exercising (IWV-3411)
Requirement Bases for Valves cannot be opened against the differential Relief pressure which exists across them during power operations. Reactor coolant system pressure holds the valves closed.
- 2. Valves are located inside containment and cannot be temporarily isolated to allow testing.
Al ternate Testing l. Valve exercising will be performed during cold to be Performed shutdown.
ualit /Safet Im act Nore frequent testing of the valves in Table 8 would require plant shutdowns solely to accommodate testing. Such requirements violate the intent of the Code (IWV-3412(a)), which recognizes that certain valve tests are not prac-tical during plant operation. Furthermore, the redundancy of the emergency core cooling system ensures that no single failure of the valves in Table 8 will compromise the plant. The proposed testing and plant design, provide an acceptable level of quality and safety.
Page 4-50 RV-2 TABLE B Valve Code Class Cate or Function HPCS-V-5 A-C HPCS discharge to reactor vessel.
LPCS-V-6 A-C LOCS discharge to reactor vessel.
RHR-V-41A A-C RHR loop A discharge to reactor RHR-Y-41B A-C RHR loop B discharge to reactor RHR-V-41C A-C RHR loop C discharge to reactor RHR-V-50A A-C RHR loop A discharge to recirculation pump discharge.
RHR-V-50B A-C RHR loop 8 discharge to recirculation pump discharge.
RHR-V-209 A-C Pressure relief bypass around RHR-V-9.
RC IC- V-66 A-C RCIC discharge to reactor vessel head.
Page 4-51 Revision RE(VEST FOR RELIEF NO. RV-3 System Containment Instrument Air Valve(s)
ASi~iE Valves affected by this relic request are identified in Classification TA8LE C.
Function Code Testing quarterly testing { INV-3412) Position indication Requirement ver i f i cat i on ( IMV-3522) 8ases for The 40 series, 36 series and 24 series valves are Relief located inside containment and cannot be accessed during power operations. There is no way to remotely isolate the valves and observe the pressure decay o, the accumulators.
- 2. There is no local or remote position indication for these check valves.
Alter nate Testing 1. During refueling outages, pressure decay tests will to be Performed be performed for the accumulators associated with the Hain Steam Isolation Valves and with the >lain Steam Safety/Relief Valves in order to verify closure abil-ity of 40 series, 35 series, and 24 series valves.
Each accumulator will be tested at least every two years.
- 2. Closure ability of CIA-V-21, 31A and 8, and 41A and 8 will be verified by normal 10CFR i', Appendix J (Type C) testing.
ualit /Safet~ Imoact The proposed testing qualitatively verifies valve closure on the most prac-tical regular basis. This satisfies the intent of the Code (IMV-3412). Valve opening is verified when the accumulators are pressurized in preparation for the pressure decay test.
The valves in Table C are in the pneumatic supply to the auto-depressurization System valves, a safety related system. However, the proposed alternate testing together with the redundancy of the pneumatic supplies and individual accumulators, of the AOS valves themselves and of the high pressure iniections systems assures an acceptable level of quality and public safety.
Page 4-52 Revision 1 RV-3 TABLE C Valve Code Class Cate or Function C IA-V-31A 8-C "2 supply to ADS valves (0/C)
C IA-V-31B B-C C IA-V-41A 8-C Cross tie between air and N2 line C IA-V-41B B-C CIA-V-40 series 2 A-C N2 to AOS Accumulators (inside (7 valves) containment CIA-V-36 series 2 A-C Air supply to Main Steam Relief (18 valves) (inboard check valve)
Valves'ccumulators CIA-V-24 series 2 A-C Air supply to Main Steam Isolation (4 valves) Valves ( Inboard)
C IA-V 2 8-C Instrument air supply to containment (outboard check valve).
Page 4-53 Revision 1 REQUEST FOR RELIEF NO. RV-4 System Standby Liquid Control (SLC)
Valve(s) SLC-V-6, SLC-V-7 ASME Code Class: 1 Category: A-C Classification Function Standby Liquid Control discharge to reactor vessel.
Code Testing I) Quarterly exercising (IWV-3521)
Requirement 2) Cold shutdown exercising (IWV-3522)
Basis for l. Valves have no operator with which they may be stroked.
Relief 2. Exercising the valves require the initiation of the SLC system and full flow injection into the reactor vessel. Initiation of SLC flow involves the discharge of Class D explosive activated valves.
Alternate Testing At least once per 18 months, one of the Standby Liquid Con-to be Performed trol System loops, including the associated explosive valve, will be initiated. A flow path to the Reactor Vessel will be verified by pumping demineralized water to the vessel. Valve closure capability will be verified in conjunction with 10CFR50 Appendix J (Type C) testing.
ualit /Safet Im act The purposed testing complies fully with the intent of the Code (IWV-3522).
Additionally it is noted that the SLC system will be required to perform its safety function only under very infrequent circumstances (ATWS). The proposed testing provides adequate assurances of quality and public safety.
Page 4-54 Revision I REQUEST FOR RELIEF NO. RV-5 System Main Steam Valve(s) MS-V-37 series (18 total), MS-V-38 series (18 total)
ASME Code Class: 3 Category: A-C Class ification Function Vacuum Breakers for main steam relief line downcomers.
Code Testing Quarterly exercising (IWV-3521)
Requirement Bases for Valves have no power operator by which they may be Relief stroked remotely.
- 2. Valves are located inside primary containment and, consequently, are inaccessible during power operations.
Alternate Testing Valves are accessible during cold shutdown and will be to be Performed exercised at that time in accordance with the requirements of paragraph IWV-3522. Valves will be verified to be closed at the completion of exercise testing.
ualit /Safet Im act The proposed testing complies fully with the intent of the Code (IWV-3522) which allows less frequent testing if "such operation is not practical during plant operation". Further, each downcomer has redundant vacuum breakers for additional reliability. The alternate testing and valve redundancy assure acceptable levels of quality and safety.
Page 4-55 Revision 1 REQUEST FOR RELIEF NO. RV-6 System Reactor Feedwater (RFW)
Valve(s)
ASME Valves affected by this relief request are identified in C1 ass if i cati on TABLE 0.
Function Code Testing Quarter ly exercising (IWV-3411, IWV-3521)
Requirement Bases for Closure of either Category A valve (RFW-V-65A, 65B)
Relief 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.
Alternate Testing Valves will be exercised during cold shutdown.
to be Performed ualit /Safet Im act The Code does not require disruption of plant operation to support valve testing ( IWV-3412, IWV-3522). The proposed testing is the maximum practical during normal power operations and, together with a system design featuring three valve in series, assures acceptable levels of quality and safety.
Page 4-56 R
RV-6 TABLE D Valve . Code Class Cate ory Function RFW-V-10A A-C Reactor Feedwater inboard check RFW-V-108 A-C valves.
RFW-Y-32A A-C Reactor Feedwater outboard check RFW-V-32B A-C valves.
RFW-V-65A Reactor Feedwater stop valves.
RFW-V-65B
Page 4-57 Revision 1 RE(VEST FOR RELIEF HO. RY-7 System Reactor Recirculation Coolant (RRC)
Valve(s)
ASME Valves affected by this relief request are identified in Classifi cati on TABLE E.
Functi on Code Testing quarterly exercising (IWV-3411 and IWV-3521)
Requirement Bases for Closure of Category A valves (RCC-V-16A, -16B) would Relief terminate seal purge water, flow to recirculation Pump 1A or 18, respectively. Loss of purge flow may result in excessive seal wear and possibly failure of the seal. The risk associated with seal failure are greater than the benefits gained by quarterly valve testing.
- 2. Category A-C valves are held open by purge water flow and cannot be closed during power operations.
Alternate Testing Valves will be exercised during cold shutdown.
to be Performed gualit /Safet Im act NRC Guidance (i.e., Oraft Reg. Guide MS901-4) states that "valves which when exercised (cycled) could put the plant in an unsafe condition" should be excluded from testing. The valves in Table E, if cycled, would endanger the reliability of the Reactor Recirculation pumps and, consequently, cause unsafe conditions. Postponing, therefore, contributes to assuring acceptable levels of quality and safety.
Page 4-58 R
RV-7 TABLE E Valve Code. Class Cate ory Function RRC-V-13A A-C Recirculation pumps'eal purge RRC-V-138 A-C line inboard isolation valve.
RRC-V-16A Recirculation pumps'eal purge RRC-V-16B water supply line outboard isola-tion valve.
Page 4-59 R
RE(VEST FOR RELIEF NO. RV-8 System Reactor Closed Coolant (RCC)
Valve(s)
ASME Valves affected by this relief request are identified in Classification TABLE F.
Function Code Testing quarterly exercising (IWV-3411 and IWV-3421).
Requirement Basis for Closure of any isolation valve will interrupt coo'iing water Relief flow to the Reactor Recirculation (RRC) Pump seals, to the RRC pump motor coolers and to the Drywell Air Coolers pos-sibly causing equipment failure or disruption of reactor operation. The risks associated with these consequences outweigh any potential benefits derived from quarterly testing of these valves.
Alternate Testing Valves will be exercised during cold shutdown.
to be Performed ualit /Safet Im act Failure of any one of the valves in Table F would terminate cooling water flow to equipment inside containment. NRC guidance suggests that such valves are not required to be tested to normal IWV schedules. Therefore, granting of this relief request will contribute to acceptable levels of quality and safety by increasing the reliability of plant equipment.
Page 5-1 Revision 1 5.0 qua lity Assu'rance Program The WNP-2 Pump and Valve Inservice Test Program activities will be conducted in accordance with Topical Report WPPSS-gA-004, the Supply System's Operational quality Assurance Program description.
Page 6-1 Revision 1 6.0 Flow Diagrams The Flow Diagrams used to generate this Program are included for user reference. Oue to the time required for Program publication, an administrative cut-off date of June>1982 was chosen to "freeze" drawing revisions used for Revision 1 of the Program. However, system design is not expected to change radically, and, in any case, more current diagrams will be provided as the Program is updated.
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