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{{#Wiki_filter:' ,! ' s2o716ossa 820401 PDR ADOCK 05000255 p PDR EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM SAFETY AND RELIEF VALVE TEST REPORT Research Project Vl02 Interim Report, April 1982 Prepared by EPRI Valve Test Program Staff Prepared for Participating PWR Utilities and Electric Power Research Institute 3412 Hillview Avenue Palo Alto, California 94304 EPRI Project Managers T. Auble J: Hosler Nuclear Power Division Copy11ghl 1f* 1982 Elecl11c Power Research lns111u1e.
{{#Wiki_filter:' ,! '
Inc. All 11ghls reserved NOTICE This reporl was p1epared by lhe Elect11c Power Research lnst1tule.
EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM SAFETY AND RELIEF VALVE TEST REPORT Research Project Vl02 Interim Report, April 1982 Prepared by EPRI Valve Test Program Staff Prepared for Participating PWR Utilities and Electric Power Research Institute 3412 Hillview Avenue Palo Alto, California 94304 EPRI Project Managers T. Auble J: Hosler Nuclear Power Division s2o716ossa 820401 PDR ADOCK 05000255 p              PDR
Inc 1EPRll Ne1lher EPRI. members ol EPRI. nor any person acting on their behalf (a) makes any warranty.
 
express or implied. w1!h resoec1 to !he use er any rnformat1on.
Copy11ghl 1f* 1982 Elecl11c Power Research lns111u1e. Inc. All 11ghls reserved NOTICE This reporl was p1epared by lhe Elect11c Power Research lnst1tule. Inc 1EPRll Ne1lher EPRI. members ol EPRI.
appa1alus.
nor any person acting on their behalf (a) makes any warranty. express or implied. w1!h resoec1 to !he use er any rnformat1on. appa1alus. melhod. or process disclosed 1n lh1s report or lhal suc~1 use may no1 1nlr1nge prrvareJy owned 11ghls. or (bl assumes any l1ab1l1t1es wilh respecl to the use ol. or tor damages resulting tram lhe use ol.
melhod. or process disclosed 1n lh1s report or lhal use may no1 1nlr1nge prrvareJy owned 11ghls. or (bl assumes any l1ab1l1t1es wilh respecl to the use ol. or tor damages resulting tram lhe use ol. any 1ntormalion, apparalus.
any 1ntormalion, apparalus. method. or process disclosed 1n this report.
method. or process disclosed 1n this report. ii * 
ii
*
 
* EPRJ PERSPECTIVE PROJECT DESCRIPTION A valve test program was conducted by EPRI for a group of participating PWR utilities to respond to the USNRC recommendations documented in NUREG 0578 Section 2.1.2, "Performance Testing on BWR _and PWR Safety and Relief Valves," and as clarified in NUREG 0737, Item II.D.l.A.
EPRJ PERSPECTIVE PROJECT DESCRIPTION A valve test program was conducted by EPRI for a group of participating PWR utilities to respond to the USNRC recommendations documented in NUREG 0578 Section 2.1.2, "Performance Testing on BWR _and PWR Safety and Relief Valves," and as clarified in NUREG 0737, Item II.D.l.A. Documentation of the Program is contained in four major program outputs.*
Documentation of the Program is contained in four major program outputs.*
* Valve Selection/Justification Report
* Valve Selection/Justification Report
* Test Condition Justification Report (Including the three PWR NSSS Vendor 11 Plant Condition Justification Reports")
* Test Condition Justification Report (Including the three PWR NSSS Vendor 11 Plant Condition Justification Reports")
Safety and Relief Valve Test Report *
* Safety and Relief Valve Test Report
* Application of RELAP 5/MOD 1 for Calculatibn of Safety and Relief Valve Discharge Piping Hydrojynamic Loads This report. entitled 11 Safety an*d Relief Valve Test Report" together with the other .three major program outputs, documents the required information for the participating PWR utilities to use in responding to the above mentioned USNRC recommendations.
* Application of RELAP 5/MOD 1 for Calculatibn of
* Safety and Relief Valve Discharge Piping Hydrojynamic Loads 11 This report. entitled Safety an*d Relief Valve Test Report" together with the other
  .three major program outputs, documents the required information for the participating PWR utilities to use in responding to the above mentioned USNRC recommendations.
PROJECT OBJECTIVE The* objectives of this report are:
PROJECT OBJECTIVE The* objectives of this report are:
* Campi le a list of relief and safety valves utilized in or planned for use iri domestic participating PWR's and identify the valves selected for t<:sting.
* Campi le a list of relief and safety valves utilized in or planned for use iri domestic participating PWR's and identify the valves selected for t<:sting.
* For all tests performed as part of the EPRI PWR Safety and Relief Valve Test Program, present the "As Tested" Test Matrices, Valve f' er f o 1 *man c e D at a and Pr i n c i p a l 0 b s er v at i on s . iii PROJECT RES.UL TS
* For all tests performed as part of the EPRI PWR Safety and Relief Valve Test Program, present the "As Tested" Test Matrices, Valve f' er f o1*man c e Dat a and Pr i nc i pa l 0bs er vat i on s .
* iii
 
PROJECT RES.UL TS
* A total of seven safety valves and ten relief valves were selected for testing. All valve performance tests were completed in December, 1981. The "as tested 11 test matrices, valve performance data and principal observations have been compiled in a form such that pcrticipating utilities may use the results in developing their response to the USNRC recommendations documented in NUREG 0578 Section 2.1.2, and as clarified in NUREG 0737 Item II.D.1.A.
* A total of seven safety valves and ten relief valves were selected for testing. All valve performance tests were completed in December, 1981. The "as tested 11 test matrices, valve performance data and principal observations have been compiled in a form such that pcrticipating utilities may use the results in developing their response to the USNRC recommendations documented in NUREG 0578 Section 2.1.2, and as clarified in NUREG 0737 Item II.D.1.A.
Thomas Auble and John Hosler, Project Managers Nuclear Power Division iv * *
Thomas Auble and John Hosler, Project Managers Nuclear Power Division iv
* ABSTRACT A safety anrl relief valve test program was conducted by EPRI for a group of ticipating PWR utilities to ri?spond to the USNRC recommendations documented in NUREG 0578 Section and as clarified in NUREG 0737 Item II.D.l.A.
* ABSTRACT A safety anrl relief valve test program was conducted by EPRI for a group of par-ticipating PWR utilities to ri?spond to the USNRC recommendations documented in NUREG 0578 Section 2.1.~, and as clarified in NUREG 0737 Item II.D.l.A. Seventeen safety and relief valve~ rep1~sentative of those utilized in or planned for use in participating domestic PWRs wer~ tested under the full range of selected test conditions. This report contains a listing of the selected test valves and the corresponding "as tested" test matrices, valve performance data and principal observations for the tested safety and ~*elief valves. The information contained in this report may be used by the participat ng utilities in developing their response to the above mentioned USNRC recommendations .
Seventeen safety and relief of those utilized in or planned for use in participating domestic PWRs tested under the full range of selected test conditions.
v
This report contains a listing of the selected test valves and the corresponding "as tested" test matrices, valve performance data and principal observations for the tested safety and valves. The information contained in this report may be used by the participat ng utilities in developing their response to the above mentioned USNRC recommendations . v
* ACKNOWLEDGMENTS This work was performed by the Electric Power Research Institute on behalf of the electric power utilities participating in the EPRI PWR Safety and Relief Valve Test Program.
* ** ACKNOWLEDGMENTS This work was performed by the Electric Power Research Institute on behalf of the electric power utilities participating in the EPRI PWR Safety and Relief Valve Test Program. EPRI wishes to thank the following individuals and organizations who contributed to the completion of the Safety and Relief Valve Test Report, Interim Report, April.1982:
EPRI wishes to thank the following individuals and organizations who contributed to the completion of the Safety and Relief Valve Test Report, Interim Report, April.1982:
D. Abdollahian  
D. Abdollahian           s. Levy, Inc.
: s. Levy, Inc. s. Kucharski Intermountain Technologies, Inc. B. Sans Electric Power Research Institute (on loan from Framatome)
: s. Kucharski               Intermountain Technologies, Inc.
G. Wi 11 i amson Continuum Dynamics, Inc . vii-
B. Sans                   Electric Power Research Institute (on loan from Framatome)
* *
G. Wi 11 i amson         Continuum Dynamics, Inc .
* SECTION 1.0. 2.0 2.1 2.2 2.3 3.0 2.3.l 2.3.2 3.1 3 .1.1 3 .1. 2 3 .2. 3.2.1 3.2.2 3.3 3.3.l 3.4 3.4.1 3.4.2 3 .. 5 3. 5 .1 3:5.2 TABLE OF INTRODUCTION PWR PRESSURIZER SAFETY AND RELIEF VALVES List of Valves in Plants Selected Test Valves and Valves Represented Des:ription of Test Valves Sa f:?ty Valves Relief Valves SUM'1ARY OF SAFETY VALVE OPERABILITY DATA Dresser Safety Valve Model 31739A Valve Description and Inlet Piping Configuration, '"As Tested" Test Matrix and Valve Performance Data Principal Observations Dre .ser Safety Valve Model 31709NA Val"e Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Priticipal Observations by HB-BP-86 3K6 (Steam Internals)
**                                         vii-
Val1e Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Principal Observations HB-BP-86 3K6 (Loop Seal Internals)
* SECTION 1.0.             INTRODUCTION TABLE OF CO~TENTS PAGE 1-1 2.0             PWR PRESSURIZER SAFETY AND RELIEF VALVES         2-1 2.1          List of Valves in Plants                         2-1 2.2          Selected Test Valves and Valves Represented       2-2 2.3          Des:ription of Test Valves                       2-4 2.3.l    Sa f:?ty Valves 2.3.2    Relief Valves 3.0            SUM'1ARY OF SAFETY VALVE OPERABILITY DATA         3-1 3.1          Dresser Safety Valve Model 31739A                 3-3 3 .1.1    Valve Description and Inlet Piping Configuration,
Valve Description and Inlet Piping Configuration. "As Tested" Test Matrix and Valve Performance Data Pri11cipal Observations HB-BP-86 6M6 (Loop Seal Internals)
                '"As Tested" Test Matrix and Valve Performance Data 3 .1. 2  Principal Observations 3 .2.        Dre .ser Safety Valve Model 31709NA 3-23 3.2.1    Val"e Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data 3.2.2    Priticipal Observations 3.3          Cro~  by HB-BP-86   3K6 (Steam Internals)         3-35 3.3.l    Val1e Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data
Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Principal Observations ix PAGE 1-1 2-1 2-1 2-2 2-4 3-1 3-3 3-23 3-35 3-53 3-65 SE CTI ON 3.6 3. 6 .1 3.6.2 3.7 3. 7 .1 3.7.2 4.0 4. l 4 .1.1 4.1.2 4.2 4.2.1 4.2.2 4.3 4.3.1 4.3.2 4.4 4.4.1 4.4.2 4.5 4.5.1 4.5.2 4.6 4.6.1 4.6.2 Crosby HB-BP-86 6NB (Steam Internals)
      ~.3.2    Principal Observations 3.4          Cro~.by  HB-BP-86 3K6 (Loop Seal Internals)     3-53 3.4.1    Valve Description and Inlet Piping Configuration.
Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Principal Observations Targd Rock 69C Valvr* Description and Inlet Piping Configuration, "As **e*sted" Test Matrix and Valve Performance Data Prin*:i pa 1 Observations SUMK\RY OF RELIEF VALVE OPERABILITY DATA Dres:.er Relief Valve "As **ested" Test Matrices and Valve Performance Data Prin( ipal Observations Crosl*y Relief Valve. "As **ested" Test Matrices and Valve Performance Data Prine ipal Observations Target Rock Relief Valve "As **ested" Test Matrices and Valve Performance Data Principal Observations Control Components Relief Valve 11 As lested" Test Matrices and Valve Performance Data Prine ipal Observations Masoreilan Relief Valve "As lested" Test Matrices and Valve Performance Data Principal Observations Relief Valve (316 w/Stellite Plug and 17-4PH Cage) "As lested" Test Matrices and Valve Performance Data Principal Observations x PAGE
                "As Tested" Test Matrix and Valve Performance Data 3.4.2    Pri11cipal Observations 3 ..5        Cro~by  HB-BP-86 6M6 (Loop Seal Internals)       3-65
* 3-83 3-95 4-1 4-3 .4-13 4-23'
: 3. 5 .1  Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data 3:5.2    Principal Observations
* 4-31 4-49 4-61
* ix
* SE CTI ON 4.7 4.7.1 4.7.2 4.8 4.8.1 4.8.2 4.9 4.9.1 4.9.2 4.10 5 ... 0 4.10 .1 4 .10. 2 Copes-Vulcan Relief Valve (17-4PH Plug and Cage) "As Tested" Test Matrices and Valve Performance Data Principal Observations MUESCO Controls Relief Valve Tested" Test Matrices and Valve Performance Data Principal Observations Controls Relief Valve Tested" Test Matrices and Valve Performance Data Principal Observations Garrett Relief Valve Testtid" Test Matrices and Valve Performance Data Principal Observations RE I ERENCES PAGE 4-67 4-75 4-83 4-91 5-1 APFcNDIX A -Definition of Key Terms and Parameters A-1 for Safety Valves xi
 
* *
SE CTI ON 3.6
: 3. 6 .1 Crosby HB-BP-86   6NB (Steam Internals)
Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data PAGE 3-83
* 3.6.2        Principal Observations 3.7          Targd Rock 69C                                         3-95
: 3. 7 .1    Valvr* Description and Inlet Piping Configuration, "As **e*sted" Test Matrix and Valve Performance Data 3.7.2      Prin*:i pa 1 Observations 4.0            SUMK\RY OF RELIEF VALVE OPERABILITY DATA               4-1
: 4. l          Dres:.er Relief Valve                                 4-3 4 .1.1    "As **ested" Test Matrices and Valve Performance Data 4.1.2      Prin( ipal Observations 4.2          Crosl*y Relief Valve.                                 .4-13 4.2.1      "As **ested" Test Matrices and Valve Performance Data 4.2.2      Prine ipal Observations 4.3 4.3.1 4.4 4.3.2 Target Rock Relief Valve "As **ested" Test Matrices and Valve Performance Data Principal Observations Control Components Relief Valve 4-23' 4-31 4.4.1      11 As lested" Test Matrices and Valve Performance Data 4.4.2      Prine ipal Observations 4.5        Masoreilan Relief Valve                                 4-49 4.5.1    "As lested" Test Matrices and Valve Performance Data 4.5.2    Principal Observations 4.6        Cope~-Vulcan Relief Valve (316 w/Stellite Plug and       4-61 17-4PH Cage) 4.6.1    "As lested" Test Matrices and Valve Performance Data 4.6.2    Principal Observations x
* SE CTI ON                                                             PAGE 4.7           Copes-Vulcan Relief Valve (17-4PH Plug and Cage)   4-67 4.7.1    "As Tested" Test Matrices and Valve Performance Data 4.7.2    Principal Observations 4.8          MUESCO Controls Relief Valve                         4-75 4.8.1    "A~ Tested" Test Matrices and Valve Performance Data 4.8.2    Principal Observations 4.9          Fi~her  Controls Relief Valve                       4-83 4.9.1    "A~ Tested" Test Matrices and Valve Performance Data 4.9.2    Principal Observations 4.10        Garrett Relief Valve                                 4-91 4.10 .1  "A~ Testtid" Test Matrices and Valve Performance Data 4 .10. 2 Principal Observations 5... 0          RE I ERENCES                                         5-1 APFcNDIX A - Definition of Key Terms and Parameters   A-1 for Safety Valves xi


==SUMMARY==
==SUMMARY==
The U. S. Nuclear Regulatory Commission (NRC) in their report NUREG 0578, 11 TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations 11 , dated July, 1979, recommended in Section 2.1.2 that Utilities operating and constructing nuclear power pl ants develop a program for performance of power operated relief valves and self-ac.tivated safety valves which are used in the reactor primary coolant system. The requirement of NUREG 0578 was later incorporaL;d into the "NRC Task Action Plan", NUREG 0660 and it was further clarified in NUREG 0737, Item II.D.l.A.
 
At the request of Utilities with PWRs, EPRI developed and implemented a Test Program for pov1er operated relief valves and safety valves. The *primary objective of the EPRI PWR Safety and Relief Valve Test Program was to rrovide full scale test data confirming the functionability of primary system power cperated relief valves and safety valves for expected operating and accident ditions. The second objective of the program was to obtain sufficient piping thermal hydraulic load data to permit confirmation of models which may be utilized in plant unique analysis of safety and relief valve discharge piping systems. TJ obtain valve operability data for the wide variety of safety and relief valves used. or intended for use in PWR. plants, it was necessary to select a limited but fully representative set of valves for test purposes.
The U. S. Nuclear Regulatory Commission (NRC) in their report NUREG 0578, 11 TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations 11 , dated July, 1979, recommended in Section 2.1.2 that Utilities operating and constructing nuclear power pl ants develop a program for performance te~;ts of power operated relief valves and self-ac.tivated safety valves which are used in the reactor primary coolant system.
The criteria used for valve selections are presented below: * *
The requirement of NUREG 0578 was later incorporaL;d into the "NRC Task Action Plan",
* test each basic valve type (spring-loaded safety valves, pilot operated safety valves, air operated relief valves, pilot operated relief valves) test each different manufacturer's version of a type test design variations in internal guiding parts which might affect valve performance . S-1
NUREG 0660 and it was further clarified in NUREG 0737, Item II.D.l.A. At the request of Utilities with PWRs, EPRI developed and implemented a Test Program for pov1er operated relief valves and safety valves.
* The fina*1 valve evaluations resulted in the selection of ten power operated relief
The *primary objective of the EPRI PWR Safety and Relief Valve Test Program was to rrovide full scale test data confirming the functionability of primary system power cperated relief valves and safety valves for expected operating and accident con-ditions. The second objective of the program was to obtain sufficient piping thermal hydraulic load data to permit confirmation of models which may be utilized in plant unique analysis of safety and relief valve discharge piping systems.
* valves and seven safety v.1lves to be tested. Justification that the test valve results were applicable to all PWR plant safety and relief valves was developed by the manufacturers of the valves being tested. The tests performed covered a wide range of prototypical fluid conditions which may occur in PWR plants. ThE* tests included steam, water, steam-to-water transition and water seal fluid conditiJns at pressures of up to 2750 psia and flow rates of up to 670,000 lb/hr steam. Th2 fluid inlet conditions were based on of PWR plant FSAR, cold overpressurization, and extended high pressure liquid injection events.* All relief valve tests performed at the Marshall Steam Station test facility, Terrell, North Carolina (owned and operated by Duke Power Company) and the test facility located at Wyle Laboratories, Norco, California.
TJ obtain valve operability data for the wide variety of safety and relief valves used.
All safety valve tests were performed at the test facility located at Combustion Engineering, Windsor, Connecticut.
or intended for use in PWR. plants, it was necessary to select a limited but fully representative set of valves for test purposes.         The criteria used for valve selections are presented below:
Valve performance testing was completed in December, 1981. Documentation of the program is contained in four major program outputs.
* test each basic valve type (spring-loaded safety valves, pilot operated safety valves, air operated relief valves, pilot operated relief valves)
* test each different manufacturer's version of a type
* test design variations in internal guiding parts which might affect valve performance .
* S-1
 
The fina*1 valve evaluations resulted in the selection of ten power operated relief
* valves and seven safety v.1lves to be tested. Justification that the test valve results were applicable to all PWR plant safety and relief valves was developed by the manufacturers of the valves being tested.
The tests performed covered a wide range of prototypical fluid conditions which may occur in PWR plants. ThE* tests included steam, water, steam-to-water transition and water seal fluid conditiJns at pressures of up to 2750 psia and flow rates of up to 670,000 lb/hr steam. Th2 fluid inlet conditions were based on conside~ation of PWR plant FSAR, cold overpressurization, and extended high pressure liquid injection events.*
All relief valve tests ~ere performed at the Marshall Steam Station test facility, Terrell, North Carolina (owned and operated by Duke Power Company) and the test facility located at Wyle Laboratories, Norco, California. All safety valve tests were performed at the test facility located at Combustion Engineering, Windsor, Connecticut. Valve performance testing was completed in December, 1981.
Documentation of the program is contained in four major program outputs.
* Valve Selection/Justification Report
* Valve Selection/Justification Report
* Test Conditions Justification Report '.Including the three PWR NSSS Vendor "Plant .Condit-ion Justification Reports")
* Test Conditions Justification Report
          '.Including the three PWR NSSS Vendor "Plant .Condit-ion Justification Reports")
* Safety end Re 1 ief Valve Test Report
* Safety end Re 1 ief Valve Test Report
* Application of RELAP 5/MOD 1 for Calculation of Safety end Relief Valve Discharge Piping Hydrodyr amic loads. S-2 * 
* Application of RELAP 5/MOD 1 for Calculation of Safety end Relief Valve Discharge Piping Hydrodyr amic loads.
* ... This report entitled 11 Safety and Relief Valve Test Report 11 together with the other three major program outputs, documents the required information for the participating PWR utilities to use in responding to the above mentioned USNRC recommendations.
S-2
These. program outputs will provide the PWR Utilities with sufficient documentation and test' data to permit each PWR Licensee to develop plant specific submittals that demonstrate  
 
*the functionability of all PWR plant safety and relief valves and to comply with NUREG 0737, Item II.0.1.A . S-3
This report entitled 11 Safety and Relief Valve Test Report 11 together with the other three major program outputs, documents the required information for the participating PWR utilities to use in responding to the above mentioned USNRC recommendations. These.
*
program outputs will provide the PWR Utilities with sufficient documentation and test' data to permit each PWR Licensee to develop plant specific submittals that demonstrate
* Section 1 INTRODUCTION At the request of Utilities with pressurized water reactors (PWR's), the Electric Power Research Institute (EPRI) implemented a PWR Valve Test program responsive to the safety and relief valve test recommendations contained in NUREG 0578, Section 2.1.2 and as clarified in NUREli 0737, Item Il.D.l.A.
  *the functionability of all PWR plant safety and relief valves and to comply with NUREG 0737, Item II.0.1.A .
The objective of the EPRI PWR Safety and Relief Valve Test Program was to perform full scale operability tests on a set of primary system relief and safety valves representative of those utilized in or planned for use in PWRs and gather discharge piping data to permit the bench marking of charge piping analysis mE:thods.
* S-3
The test conditions were selected to be tive of those expected in participating PWRs based on consideration of limiting FSAR, cold overpressurization, and extended high pressure liquid injection events. This report presents the safety and relief valve test results generated as part of the Generic EPRI PWR Valve Test Program. The intent of the report is to provide the required valve performance information and data to permit PWR.licensees and applicants to demonstrate the functionability of power operated relief valves and safety valves utilized in the primary system of PWRs. The information presented includes key* information typically used to assess valve functionability such as valve opening and closing data, transient depressurization data and valve inspection results. In addition, other supplemental information related to valve performance for these tests has been included.
* Section 1 INTRODUCTION At the request of Utilities with pressurized water reactors (PWR's), the Electric Power Research Institute (EPRI) implemented a PWR Valve Test program responsive to the safety and relief valve test recommendations contained in NUREG 0578, Section 2.1.2 and as clarified in NUREli 0737, Item Il.D.l.A. The objective of the EPRI PWR Safety and Relief Valve Test Program was to perform full scale operability tests on a set of primary system relief and safety valves representative of those utilized in or planned for use in PWRs and gather discharge piping data to permit the bench marking of dis-charge piping analysis mE:thods. The test conditions were selected to be representa-tive of those expected in participating PWRs based on consideration of limiting FSAR, cold overpressurization, and extended high pressure liquid injection events.
All valve performance tests were completed in December 1981. This report is organized into five sections.
This report presents the safety and relief valve test results generated as part of the Generic EPRI PWR Valve Test Program. The intent of the report is to provide the required valve performance information and data to permit PWR.licensees and applicants to demonstrate the functionability of power operated relief valves and safety valves utilized in the primary system of PWRs. The information presented includes key*
Section 1 is the report introduction.
information typically used to assess valve functionability such as valve opening and closing data, transient depressurization data and valve inspection results. In addition, other supplemental information related to valve performance for these tests has been included. All valve performance tests were completed in December 1981.
Section 2 lists the relief and safety valves utilized in or planned for use in domestic participating PWRs and identifies the valves that were selected for testing. The basis for test valve selection and justification is documented in Reference 1 of this report. Sections 3 and 4 present the "as tested" test matrices, valve performance data and principal observations for the relief and safety valves tested as part of the program, respectively.
This report is organized into five sections. Section 1 is the report introduction.
The basis and justification of the valve test conditions are documented in Reference 1, 2, 3,4 and 5 of this report. Section 5 contains the list of references of this reJort. In addition to these five sections, an Appendix A entitled "Definition of K*?y Terms and Parameters" has been included . 1-1
Section 2 lists the relief and safety valves utilized in or planned for use in domestic participating PWRs and identifies the valves that were selected for testing. The basis for test valve selection and justification is documented in Reference 1 of this report. Sections 3 and 4 present the "as tested" test matrices, valve performance data and principal observations for the relief and safety valves tested as part of the program, respectively. The basis and justification of the valve test conditions are documented in Reference 1, 2, 3,4 and 5 of this report. Section 5 contains the list of references of this reJort. In addition to these five sections, an Appendix A entitled "Definition of K*?y Terms and Parameters" has been included .
*
* 1-1
* Section 2 2.0 PWR PRESSURlZER SAFETY AND RELIEF VALVES As part of the EPRI PWR Safety and Relief Valve Test Program, full-scale testing of pressurizer safety and relief valves representative of those in use or planned for use in PWR plants was performed.
* 2.0 Section 2 PWR PRESSURlZER SAFETY AND RELIEF VALVES As part of the EPRI PWR Safety and Relief Valve Test Program, full-scale testing of pressurizer safety and relief valves representative of those in use or planned for use in PWR plants was performed. In order to select a set of valves for testing, a com-plete list of valve types, models, and sizes used or intended for use in domestic participating PWR plants was compiled based on information provided by the PWR Utilities, l~SSS vendors, and valve manufacturers. From these lists, valves were selected for testing which represent the participating PWR plant valve population.
In order to select a set of valves for testing, a plete list of valve types, models, and sizes used or intended for use in domestic participating PWR plants was compiled based on information provided by the PWR Utilities, vendors, and valve manufacturers.
Justifiction of the selection was developed based on evaluations performed by the valve manufacturers. These evaluations considered the effects of differences in valve operational characteristics, materials, design details, and sizes.
From these lists, valves were selected for testing which represent the participating PWR plant valve population.
The purpose of this section is to:
Justifiction of the selection was developed based on evaluations performed by the valve manufacturers.
* present lists of safety and relief valves used or intended for use in domestic participating PWR plants and the PWR Utilities and plants which utilize these valves,
These evaluations considered the effects of differences in valve operational characteristics, materials, design details, and sizes. The purpose of this section is to: * *
* present lists of the safety and relief valves selected for testing, the valves represented by the test valves and a summary of the valve distribution in PWR plants,
* present lists of safety and relief valves used or intended for use in domestic participating PWR plants and the PWR Utilities and plants which utilize these valves, present lists of the safety and relief valves selected for testing, the valves represented by the test valves and a summary of the valve distribution in PWR plants, present a description of the valves selected for testing . 2.1 LIST OF VALVES IN PLANTS The valve manufacturer and valve model numbers of safety and relief valves used in PWR plants are in Tables 2-1 and 2-2. These tables provide the following information:
* present a description of the valves selected for testing .
* Table 2-1 provides a list of safety valves (identified by tiJrer and model number) and the PWR Utilities and plants which utilize these valves; 2-1
2.1   LIST OF VALVES IN PLANTS The valve manufacturer and valve model numbers of safety and relief valves used in PWR plants are ~;umrnarized in Tables 2-1 and 2-2. These tables provide the following information:
* Table 2-2 provides a list of relief valves (identified by f.1Jt"1*r anti 11111111*
* Table 2-1 provides a list of safety valves (identified by manufac-tiJrer and model number) and the PWR Utilities and plants which utilize these valves;
I nu111lir!t*)
* 2-1
arid 1111* l'Wli UI. i Ii I. it*s c111d p I wh icl1 uL i I i11! these valves. Table 2-2 has been updated since the Valve Selection/Justification Report (Reference 1), and it's list of relief valves was issued. The lists are identical except that the Commonwealth Edison Company, Zion 1 & 2 Plant Copes-Vulcan relief valve plug material has been changed from 17-4PH to 316 w/Stellite material.
* Table 2-2 provides a list of relief valves (identified by man1ifrir.-
The technical justification of Reference 1 is not effected by this change. 2.2 SELECTED TEST VALVES AND VALVES REPRESENTED As can be seen from Tables 2-1 and 2-2, a large number of safety and relief valve models are used in PWR plants. As a result, it was necessary to perform engineering evaluations in order to select a number of valve types, models and sizes for test purposes that provide generic results that are applicable to all of the plants involved.
f.1Jt"1*r anti 11111111* I nu111lir!t*) arid 1111* l'Wli UI. i Ii I. it*s c111d p I ant.~) wh icl1 uL i I i11!
These evaluations were performed by the valve manufacturers and they considered the effects of the differences in valve operation characteristics, terials, design details, and sizes on valve The criteria for valve selection that were used in conjunction with the above evaluations are presented below:
these valves.
* Include each basic valve type (e.g., spring-loaded safety valve, operated relief valve, etc.);
Table 2-2 has been updated since the Valve Selection/Justification Report (Reference 1), and it's list of relief valves was issued. The lists are identical except that the Commonwealth Edison Company, Zion 1 & 2 Plant Copes-Vulcan relief valve plug material has been changed from 17-4PH to 316 w/Stellite material. The technical justification of Reference 1 is not effected by this change.
2.2     SELECTED TEST VALVES AND VALVES REPRESENTED As can be seen from Tables 2-1 and 2-2, a large number of safety and relief valve models are used in PWR plants. As a result, it was necessary to perform engineering evaluations in order to select a number of valve types, models and sizes for test purposes that provide generic results that are applicable to all of the plants involved. These evaluations were performed by the valve manufacturers and they considered the effects of the differences in valve operation characteristics, ma-terials, design details, and sizes on valve operabil~ty. The criteria for valve selection that were used in conjunction with the above evaluations are presented below:
* Include each basic valve type (e.g., spring-loaded safety valve, air-operated relief valve, etc.);
* Include each different manufacturer's version of a given valve type (e.g., Dresser and Crosby spring-loaded safety valves);
* Include each different manufacturer's version of a given valve type (e.g., Dresser and Crosby spring-loaded safety valves);
* Include each design variation in internal guiding parts which could impact valve performance (e.g., Copes-Vulcan 17-4PH cage/plug versus 316 w/stellite plug with a 17-4PH cage). Utilizing the results of the above evaluations and valve selection criteria, a set of safety and relief valves were originally selected for testing. The types, models and PWR plant distribution of the valves selected for testing are presented in Tables 2-3 and 2-4. 2-2 * * 
* Include each design variation in internal guiding parts which could impact valve performance (e.g., Copes-Vulcan 17-4PH cage/plug versus 316 w/stellite plug with a 17-4PH cage).
* ..
Utilizing the results of the above evaluations and valve selection criteria, a set of safety and relief valves were originally selected for testing. The types, models and PWR plant distribution of the valves selected for testing are presented in Tables 2-3 and 2-4.
* Table 2-3 provides a list of the selected test safety valves, the *valves represented and the valve distribution in PWR plants;
2-2
* Table 2-4 provides a list of the selected test relief valves, the valves represented and the valve distribution in PWR plants. Table 2-4 has been updated since the Valve Selection/Justification Report and it's list of selected test relief valves was issued. The lists are identical except that the "Valves Represented, No. of Plants" column has been revised to include the previously noted change of Table 2-2. :n summary, nine safety valves and ten relief valves were originally selected for tests .. Based on valve vendor evaluations, the test results of the valves selected for testing (Tables 2-3 and 2-4) can be extended to the entire population of PWR valves represented by the selected test valves . 2-3
* Table 2-3 provides a list of the selected test safety valves, the
?.3 DESl.RIPTION OF TESl VALVES The following is a brief description of the specific safety and relief valves which were tested. 2.3.l Safety Valves 2.3.1.a Crosby Valve and Gage Company. All PWR plants which have Crosby safety valves utilize the same basic valve design. Model No. HB-BP-86.
            *valves represented and the valve distribution in PWR plants;
The Crosby model is a direct acting spring safety valve design. However, a variety of inlet, outlet and orifice sizes are utilized as listed in Table 2-3. Valves with the smallest and largest orifice sizes were selected for test, as well as a valve with an intermediate orifice size which is utilized in a large number of PWR plants. Also, the original selection included each of the three Crosby valves using two different sets of internals:
* Table 2-4 provides a list of the selected test relief valves, the valves represented and the valve distribution in PWR plants.
one set which represents valves which are installed in systems which use loop seals, and the second set which represents valves which are installed in non-loop seal plants. The original selection process resulted in a total of six Crosby safety valve designs selected for test. Once testing was initiated, the valve selection was re-evaluated and it was determined that the Crosby valve selection could be reduced from six safety valve variations to four safety valve variations and still obtain test results representative of all Crosby PWR plant safety valve designs. The tested valves included each of the three orifice sizes originally selected for testing and each of the internal valve seating and guiding material combinations originally selected for testing. The Crosby_ 3K6 safety valve was tested with both the steam and loop seal seating materials designed for their respective applications.
Table 2-4 has been updated since the Valve Selection/Justification Report and it's list of selected test relief valves was issued. The lists are identical except that the "Valves Represented, No. of Plants" column has been revised to include the previously noted change of Table 2-2.
These tests demonstrated the performance of the two different seat material combinations within a valve orifice size. With this test data and the assessment that the major effect of the variation in seat materials is on valve seat leakage and not overall valve performance, it was determined that the Crosby 6M6 and 6N8 safety valve designs could be tested utilizing 2-4 * * *
:n summary, nine safety valves and ten relief valves were originally selected for tests .. Based on valve vendor evaluations, the test results of the valves selected for testing (Tables 2-3 and 2-4) can be extended to the entire population of PWR valves represented by the selected test valves .
* one representative seating material combination in each valve, instead of both loop seal and non-loop seal seating maLerial combinations.
* 2-3
Loop seal internals were selected for test in the 6M6 valve (long inlet configuration with a loop seal) and steam internals were selected for test in the 6N8 valve (long inlet configuration with no loop seal). As a result, the total selection of Crosby safety valves which needed to be tested to provide data representative of all Crosby PWR plant safety valyes was reduced from three Crosby orifice sizes and two internal seat material combinations per orifice size to three Crosby orifice sizes with two seat material combinations in one orifice size (3K6) and one seat material combination in each of two orifice sizes (6M6, 6N8). The total number of safety valves finally selected for test became seven valves instead of the originally selected quantity of nine valves defined in Reference  
 
: 1. A description of the three Crosby designs selected for testing is presented below. *
  ?.3   DESl.RIPTION OF TESl VALVES The following is a brief description of the specific safety and relief valves which were tested.
* HB-BP-86, 3K6 This valve model has the smallest orifice size and therfore the smallest flow capacity of the Crosby safety valves. This valve size is utilized in three of the 67 pl ants which have Crosby safety valves. HB-BP-86, 6M6 This valve model was selected for testing because it is utilized in 38 of the 67 plants which have Crosby safety valves. Also, it provides test results with an intermediate orifice size which facilitates the extension of the Crosby valve test results to the other smaller Crosby safety valves.
2.3.l Safety Valves 2.3.1.a Crosby Valve and Gage Company. All PWR plants which have Crosby safety valves utilize the same basic valve design. Model No. HB-BP-86. The Crosby model is a direct acting spring lo~ded safety valve design. However, a variety of inlet, outlet and orifice sizes are utilized as listed in Table 2-3. Valves with the smallest and largest orifice sizes were selected for test, as well as a valve with an intermediate orifice size which is utilized in a large number of PWR plants. Also, the original selection included each of the three Crosby valves using two different sets of internals: one set which represents valves which are installed in systems which use loop seals, and the second set which represents valves which are installed in non-loop seal plants.
* HB-BP-86, 6N8 ' This valve model has the largest orifice size and flow capacity of the Crosby valves and is utilized in 6 of the 67 PWR plants which have Crosby safety valves. Note that the three Crosby valves selected for test directly represent valves in 47 of the 67 PWR plants which utilize Crosby safety valves. 2.3.1.b. Dresser Industries.
The original selection process resulted in a total of six Crosby safety valve designs selected for test. Once testing was initiated, the valve selection was re-evaluated and it was determined that the Crosby valve selection could be reduced from six safety valve variations to four safety valve variations and still obtain test results representative of all Crosby PWR plant safety valve designs.
The same basic valve design, Model No. 31700, is used in all PWR plants which have Dresser safety valves. The Dresser valve is a direct acting spring loaded safety valve design. Again, a variety of combinations of inlet, 2-5 outlet and orifice sizes are used in the various PWR plants, as shown in Table 2-3. For the tests, two Dresser safety valves were selected, a valve with a small orifice size, and a valve with a large orifice size. Also, the two valves selected for test are the same models and sizes as valves installed in 28 of the 37 PWR plants which have Dresser valves. *
The tested valves included each of the three orifice sizes originally selected for testing and each of the internal valve seating and guiding material combinations originally selected for testing.
* These valves are briefly described below: 31739A This valve model has a small orifice size and flow capacity and is utilized in 11 of the 37 PWR plants which have Dresser safety valves. 31709NA This valve model has the largest orifice size and flow capacity and is utilized in 17 of the 37 PWR plants which have Dresser safety valves. 2.3.1.c. Target Rock Corporation.
The Crosby_ 3K6 safety valve was tested with both the steam and loop seal seating materials designed for their respective applications. These tests demonstrated the performance of the two different seat material combinations within a valve orifice size. With this test data and the assessment that the major effect of the variation in seat materials is on valve seat leakage and not overall valve performance, it was determined that the Crosby 6M6 and 6N8 safety valve designs could be tested utilizing 2-4
There is only one PWR plant which uses Target Rock safety valves. The test valve, Model No. 69C, is representative of the valves installed in this plant. The Target Rock model is a pilot operated valve design actuated by the system inlet pressure 2.3.2 Relief Valves 2.3.2.a Control Components, Inc. The test valve is identical to the Control ponents relief valves which are installed in 4 PWR plants. The Control Components drag valve model is an air operated globe valve design. 2.3.2.b. Copes-Vulcan, Inc. The Copes-Vulcan model is an air operated globe valve design. As indicated in Table 2-4,two different sets of valve internals with different material combinations are utilized in the Copes-Vulcan relief valves. Also, the initial design valves utilized a two-inch valve body with three inch butt weld ends while the more recent valves utilized a three-inch valve body. For the test, the three-inch valve body was selected because it directly represents 25 of the 38 plants which utilize Copes-Vulcan relief valves. Also, the test valve was tested with the two different types of internals in order to obtain results which are representative of all of the Copes-Vulcan valves in PWR plant service. 2-6
* one representative seating material combination in each valve, instead of both loop seal and non-loop seal seating maLerial combinations.       Loop seal internals were selected for test in the 6M6 valve (long inlet configuration with a loop seal) and steam internals were selected for test in the 6N8 valve (long inlet configuration with no loop seal).
* I f .111 *
As a result, the total selection of Crosby safety valves which needed to be tested to provide te~t. data representative of all Crosby PWR plant safety valyes was reduced from three Crosby orifice sizes and two internal seat material combinations per orifice size to three Crosby orifice sizes with two seat material combinations in one orifice size (3K6) and one seat material combination in each of two orifice sizes (6M6, 6N8). The total number of safety valves finally selected for test became seven valves instead of the originally selected quantity of nine valves defined in Reference 1.
* 2.3.2.c. Crosby Valve and Gage Company. The Crosby model is an electrically actuated pilot operated valve.design.
A description of the three Crosby designs selected for testing is presented below.
As shown in Table 2-4, there is only one model Crosby relief valve used in PWR plants, Model No. HPV-SN. However, there are differences in the specific versions of this model utilized in the three PWR plants, e.g., differences in bore size and body configuration.
* HB-BP-86, 3K6 This valve model has the smallest orifice size and therfore the smallest flow capacity of the Crosby safety valves. This valve size is utilized in three of the 67 pl ants which have Crosby safety valves.
However, from a functional standpoint, the test valve is representative of both valve designs. 2.3.2.d. Dresser Industries.
* HB-BP-86, 6M6 This valve model was selected for testing because it is utilized in 38 of the 67 plants which have Crosby safety valves. Also, it provides test results with an intermediate orifice size which facilitates the extension of the Crosby valve test results to the other smaller Crosby safety valves.
The Dresser models are electrically actuated pilot operated valve designs. As indicated in Table 2-4, there are two different Dresser valve models utilized in PWR plants: Model 31533VX-30 which utilizes a bellows in the pilot valve section of the valve, and Model 31533VX which does not have a bellows. For the test, Model 31533VX-30 was selected since it directly represents 20 of the 21 PWR valves. Also, the results obtained from the model 31533VX-30 valve represent Model 31533VX valve performance.
* HB-BP-86, 6N8 This valve model has the largest orifice size and flow capacity of the Crosby valves and is utilized in 6 of the 67 PWR plants which have Crosby safety valves.
2.3.2.e. Fisher Controls.
Note that the three Crosby valves selected for test directly represent valves in 47 of the 67 PWR plants which utilize Crosby safety valves.
The Fisher Controls SS-103-SS-95 model is an air operated globe valve design. The test valve is identical to the Fisher Controls relief valves which are installed in three PWR plants . 2.3.2.f. Garrett Pneumatic Systems Division.
2.3.1.b. Dresser Industries. The same basic valve design, Model No. 31700, is used in all PWR plants which have Dresser safety valves. The Dresser valve is a direct acting spring loaded safety valve design. Again, a variety of combinations of inlet, 2-5
The Garrett valve model is an trically actuated pilot operated valve design. There are two different versions of the same basic Garrett relief valve model, one with an angle body and one with a straight-through body. However, from a functional standpoint, the two valves are virtually identical.
 
Accordingly, the results obtained with the straight-through test valve are representative of both Garrett valve models. 2.3.2.g. Masoneilan.
outlet and orifice sizes are used in the various PWR plants, as shown in Table 2-3. For the tests, two Dresser safety valves were selected, a valve with a small orifice size, and a valve with a large orifice size. Also, the two valves selected for test are the same models and sizes as valves installed in 28 of the 37 PWR plants which have Dresser valves. These valves are briefly described below:
The Masoneilan 20,000 Series model is an air operated globe valve design. The test valve is identical except for a variation in plug geometry to the Masoneilan relief valves-installed in the 8 PWR plants. The test valve results represent the performance of both plug designs and all Masoneilan PWR relief valves. 2.3.2.h. MUESCO .Controls, Inc. The MUESCO Controls 70-18-9 DRTX model is an air operated globe valve design. The test valve is identical to the MUESCO Controls relief valves installed in l PWR plant . 2-7 2.3.2.i.
* 31739A This valve model has a small orifice size and flow capacity and is utilized in 11 of the 37 PWR plants which have Dresser safety valves.
Rock_ Corporation.
* 31709NA This valve model has the largest orifice size and flow capacity and is utilized in 17 of the 37 PWR plants which have Dresser safety valves.
The Target Rock BOX-006 model valve is a pilot operated solenoid valve design. The test valve represents the Target Rock relief valves which are installed in 2 PWR plants. 2-8 * *
2.3.1.c. Target Rock Corporation. There is only one PWR plant which uses Target Rock safety valves. The test valve, Model No. 69C, is representative of the valves installed in this plant. The Target Rock model is a pilot operated valve design actuated by the system inlet pressure 2.3.2 Relief Valves 2.3.2.a Control Components, Inc. The test valve is identical to the Control Com-ponents relief valves which are installed in 4 PWR plants. The Control Components drag valve model is an air operated globe valve design.
* UTILITY PLANT Alabama Power Co. Farley l & 2 Arizona Public Palo Verde l. 2, & 3 Service Co. Arkansas Power & Arkansas Nuclear Ught Co. One-1 N I \.0 Arkansas Nuclear One-2 Baltimore Gas & Calvert Cliffs 1 & 2 Electric Co. Carolina Power & H.B. Robinson 2 Light Co. Shearon Harris 1,2,3,&4 Commonwealth Zion l & 2 Edi son Co. Byron l & 2 Braidwood l & 2 Connecticut Yankee Connecticut Yankee Atomic Power Co.
2.3.2.b. Copes-Vulcan, Inc. The Copes-Vulcan model is an air operated globe valve design. As indicated in Table 2-4,two different sets of valve internals with different material combinations are utilized in the Copes-Vulcan relief valves. Also, the initial design valves utilized a two-inch valve body with three inch butt weld ends while the more recent valves utilized a three-inch valve body. For the test, the three-inch valve body was selected because it directly represents 25 of the 38 plants which utilize Copes-Vulcan relief valves. Also, the test valve was tested with the two different types of internals in order to obtain results which are representative of all of the Copes-Vulcan valves in PWR plant service.
2-6
 
I f   . 111 2.3.2.c. Crosby Valve and Gage Company. The Crosby model is an electrically actuated pilot operated valve.design. As shown in Table 2-4, there is only one model Crosby relief valve used in PWR plants, Model No. HPV-SN. However, there are differences in the specific versions of this model utilized in the three PWR plants, e.g.,
differences in bore size and body configuration.         However, from a functional standpoint, the test valve is representative of both valve designs.
2.3.2.d. Dresser Industries. The Dresser models are electrically actuated pilot operated valve designs. As indicated in Table 2-4, there are two different Dresser valve models utilized in PWR plants: Model 31533VX-30 which utilizes a bellows in the pilot valve section of the valve, and Model 31533VX which does not have a bellows. For the test, Model 31533VX-30 was selected since it directly represents 20 of the 21 PWR valves. Also, the results obtained from the model 31533VX-30 valve represent Model 31533VX valve performance.
2.3.2.e. Fisher Controls. The Fisher Controls SS-103-SS-95 model is an air operated globe valve design. The test valve is identical to the Fisher Controls relief valves which are installed in three PWR plants .
* 2.3.2.f. Garrett Pneumatic Systems Division. The Garrett valve model is an elec-trically actuated pilot operated valve design. There are two different versions of the same basic Garrett relief valve model, one with an angle body and one with a straight-through body. However, from a functional standpoint, the two valves are virtually identical. Accordingly, the results obtained with the straight-through test valve are representative of both Garrett valve models.
2.3.2.g. Masoneilan. The Masoneilan 20,000 Series model is an         air operated globe valve design. The test valve is identical except for a variation     in plug geometry to the Masoneilan relief valves-installed in the 8 PWR plants. The       test valve results represent the performance of both plug designs and all Masoneilan     PWR relief valves.
2.3.2.h. MUESCO .Controls, Inc. The MUESCO Controls 70-18-9 DRTX model is an air operated globe valve design. The test valve is identical to the MUESCO Controls relief valves installed in l PWR plant .
* 2-7
 
2.3.2.i. Ta.!:..9_~ Rock_ Corporation. The Target Rock BOX-006 model valve is a pilot operated solenoid valve design. The test valve represents the Target Rock relief valves which are installed in 2 PWR plants.
* 2-8                                           *
 
    *
* TABLE 2-1 LIST OF PWR UTILITIES, PLANTS AND PRESSURIZER SAFETY VALVES (Participating Utilities)
* TABLE 2-1 LIST OF PWR UTILITIES, PLANTS AND PRESSURIZER SAFETY VALVES (Participating Utilities)
VALVE MANUFACTURER Crosby Valve & Gage Dresser Dresser Crosby Valve & Gage Dresser Crosby Valve & Gage Crosby Va 1 ve & Gage Crosby Valve & Gage Crosby Valve & Gage Crosby Valve & Gage Crosby Valve & Gage VALVE MODEL NO. AND DESCRIPTION*
UTILITY              PLANT                      VALVE MANUFACTURER     VALVE MODEL NO. AND DESCRIPTION*
Model No. Size Assembly No. HB-BP-86 6Ml 6 N56963-l 31709NA 31759A (forged body, forged bonnet) HB-BP-86 6M6 55605 31739A (cast body, forged bonnet) 31739A (forged body, forged bonnet) HB-BP-86 4K26 51249 HB'-BP-86 6M6 N56964 HB-BP-86 6M6 51688 & N56499 HB-BP-86 6M6 N56964 HB-BP-86 6M6 N56964 HB-BP-86 3K26 51185 TABLE 2-1 (Continued)
Model No. Size Assembly No.
UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*
Alabama Power Co. Farley l & 2                Crosby Valve & Gage   HB-BP-86    6Ml 6  N56963- l Arizona Public      Palo Verde l. 2,  & 3        Dresser                31709NA Service Co.
Model No. Size Assembl.z No. Consolidated Indian Point 2 Crosby Valve & Gage HB-BP-86 4M6 51250-1 Edison Company of New York, Inc. Consumers Power Co. Palisades Dresser 31739A (cast body, cast bonnet) 1 & 2 Dresser 31739A (forged body, forged bonnet) Duke Power Co. Oconee & 2 Dresser 31739A (cast body, cast bonnet) Oconee 3 Dresser 31739A (forged body, forged bonnet) McGuire & 2 Crosby Valve & Gage HB-BP-86 6M6 N56925 Catawba & 2 Dresser 31749A (forged body, forged bonnet) N Perkins 1
Arkansas Power  &   Arkansas Nuclear            Dresser                31759A (forged body, forged bonnet)
* 2, & 3 Dresser 31709NA I I--' 0 Cherokee 1, 2, & 3 Dresser 31709NA Duquesne Light Co. Beaver Valley 1 Target Rock 69C Beaver Valley 2 Crosby Valve & Gage HB-BP-86 6Ml6 N56963 Florida Power Corp. Crystal River 3 Dresser 31739A (forged body, forged bonnet) Florida Power Turkey Point 3 & 4 Crosby Valve & Gage HB-BP-86 4K26 51249 & Light Co. St. Lucie l Crosby Valve & Gage HB-BP-86 3K6 N54495 St. Lucie 2 Crosby Valve & Gage HB-BP-86 3K6 N59336 Georgia Power Co. Vogtle 1 & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 Houston Lighting South Texas l & 2 Crosby Valve & Gage HB-BP-86 6N8 N60491 & Power Co. Indiana & Michigan Donald C. Cook l & 2 Crosby Valve & Gage HB-BP-86 6M6 51688 Electric
Ught Co.        One-1 N
* TABL. (Continued)
I
* UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*
\.0                    Arkansas Nuclear            Crosby Valve & Gage    HB-BP-86     6M6   55605 One-2 Baltimore Gas &    Calvert Cliffs 1 &  2        Dresser                31739A (cast body, forged bonnet)
Model No. Size Assembly No. Kansas City Power and Light Wolf Creek Crosby *valve & Gage HB-BP-86 6M6 N60446 Kansas Gas & Electric Co. Louisiana Power Waterford 3 Oresser 31749A (forged body, forged bonnet) & Light Co. Ma i.ne Yankee Maine Yankee Dresser 31709KA (cast body, forged bonnet) Atomic Power Co. Metropolitan Three Mile Isl and 1 Dresser 31739A (cast body. cast bonnet and Edi son Co. forged body, forged bonnet) Three Mile Island 2 Dresser 31759A (forged body, forged bonnet) N Northeast Utilities Millstone 2 Dresser 3l739A *(forged body, forged bonnet) I ,_. ,_. Mi 11 stone 3 Crosby Valve & Gage HB-BP-86 6M6 N56964-4 Northern States Prairie Isl and 1 Crosby Valve & Gage HB-BP-86 6Ml 6 52137 & N57872 Power Company Prairie Island 2 Crosby Valve & Gage HB-BP-86 6Ml 6 52137 Omaha Public Fort Calhoun 1 Crosby Valve & Gage HB-BP-86 3K6 50646-1 Power District Paci fie Gas & Di abl o Canyon l & 2 Crosby Valve & Gage HB-BP-86 6M6 51688 Electric Co. Portland General Trojan Crosby Valve & Gage HB-BP-86 6M6 N55366 Electric Co.
Electric Co.                                                        31739A (forged body, forged bonnet)
* Pebble Springs l & 2 Dresser 31709NA Power Authority Indian Point 3 Crosby Valve & Gage HB-BP-86 6M6 51688-l of the State of New York Public Service Marble Hi 11 l & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 of Indiana TABLE 2-T (Continued)
Carolina Power  &  H.B. Robinson 2              Crosby Valve  & Gage  HB-BP-86     4K26   51249 Light Co.
UTILITY PLANT YALVE MANUFACTURER VALVE MODEL NO. AND Model No. Size Assembly No. Public Service Co. Seabrook 1 & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 of New Hampshire Public. Service Salem l & 2 Crosby Valve & Gage HB-BP-86 6M6 51688 Electric & Gas Rochester Gas and Ginna Crosby Valve & Gage HB-BP-86 4K26 51249 Electric Corp. Sacramento Municipal RANCHO-SECO l Dresser 3l 759A (forged body, forged bonnet) Utility District South Carolina Virgil C. Summer* Crosby Valve & Gage HB-BP-86 6M6 N56964-l Electric & Gas Southern California San Onofre Crosby Valve & Gage HB-BP-86 3K26 47469-1 & N51185-2 Edi son Company San Onofre 2 & 3 Dresser 31709NA N Tennessee Valley Sequoyah 1 & 2 Crosby Valve & Gage HB-BP-86 6M6 51688 I ,__. Authority N Watts Bar l & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 Bellefonte 1 & 2 Dresser 31709NA Yellow Creek 1 & 2 Crosby Valve & Gage HB-BP-86 6N8 N61894 Texas Utilities Commanche Peak 1 & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 Generating Co. Toledo Edison Co. Davis. Besse 1 Crosby Valve & Gage HB-BP-86 4Ml6 N54891 & N59303 Union Electric Co. Ca 11 away l & 2 Crosby Va 1 ve & Gage HB-BP-86 6M6 N60446 Virginia Electric Surry l & 2 Crosby Valve & Gage HB-BP-86 6K26 51689 & Power Co. North Anna & 2 Dresser 31759A (cast bod'" forged bonnet) -.) North Anna 3 & 4 Crosby Valve & Gage HB-BP-86 4Ml6 N56264 *
Shearon Harris              Crosby Va 1ve & Gage  HB'-BP-86   6M6   N56964 1,2,3,&4 Commonwealth        Zion l & 2                  Crosby Valve  & Gage  HB-BP-86     6M6 Edi son Co.                                                                              51688  &  N56499 Byron l & 2                  Crosby Valve  & Gage  HB-BP-86     6M6   N56964 Braidwood l  & 2            Crosby Valve  & Gage  HB-BP-86     6M6    N56964 Connecticut Yankee  Connecticut Yankee          Crosby Valve  & Gage  HB-BP-86    3K26  51185 Atomic Power Co.
* _J N I f--' w
 
* 2-1 (Continued)
TABLE 2-1 (Continued)
* UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. & DESCRIPTION*
UTILITY             PLANT                     VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*
Model No. Size Assembly No. Washington Public Power Supply System WPPSS 1 & 4 WPPSS 3 & 5 Dresser 31709NA 6N8 N60582 Wisconsin Electric Power Point Beach 1 & 2 Crosby Valve & Gage Crosby Valve & Gage HB-BP-86 HB-BP-86 4K26 51249 Wisconsin Public Service Corp. Kewaunee Crosby Valve & Gage HB-BP-86 6Ml6 52137
Model No. Size Assembl.z No.
* The assembly no. is a unique identifier for each hardware variation in the Crosby Valve & Gage Safety Valve model HB-BP-86.
Consolidated         Indian Point 2           Crosby Valve & Gage HB-BP-86     4M6   51250-1 Edison Company of New York, Inc.
The size of the Crosby Safety Valve covers the valve inlet size, (3" -6") orifice size (K, K2, Ml, M, N) and outlet size (6 11 , 8"). The only information required to uniquely identify the Target Rock Safety Valves is the model no. The model no. and any parenthetical information on the _body and bonnet uniquely identify the Dresser Safety Valves. : ......
Consumers Power Co. Palisades                 Dresser             31739A (cast body, cast bonnet)
N I ........ Ul / /
                          ~lidland 1 &2             Dresser             31739A (forged body, forged bonnet)
* UTILITY Al a bama Power Co. Arizona Public Service Co. Arkansas Power & Light Co. Bal ti more Gas & Electric Co. Carolina Power & Light Company Commonwea 1th Edi son Company Connecticut Yankee A to mi c Power Co. r," PLANT Farley l & 2* Palo Verdel, 2, & 3 Arkansas Nuclear One-1 Arkansas Nuclear One-2 Calvert Cliffs l & 2 H.B. Robinson 2 Shearon Harris l, 2, 3, & 4 Zion 1 & 2 Byron l & 2 Braidwood l & 2 Connecticut Yankee LIST OF PWR UTILITIES, PLANTS AND POWER OPERATED RELIEF VALVES {Participating Utilities)
Duke Power Co.       Oconee   &2             Dresser             31739A (cast body, cast bonnet)
VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*-
Oconee 3                 Dresser             31739A (forged body, forged bonnet)
MODEL NO. SIZE AND DESCRIPTION Copes-Vulcan Globe 3" NPS, 316 W/Stellite D-100-160 Plug and 17-4PH Cage No PORVs No PO RVs Dresser 31533VX-30 l 3/ 32" Bore No PORVs No PO RVs Dresser 31533VX-30 l 5/16" Bore Copes-Vulcan Globe 2" NPS, 17-4 PH Plug D-100-160 and Cage Copes-Vulcan Globe 3" NPS, 316 W/Stellite Plug . D-100-160 and 17-4PH Cage Copes-Vulcan Globe 2" NPS, 316 w/Stellite Plug D-100-160 l 7-4PH Cage Copes-Vulcan Globe 3" NPS, 316 W/Stellite D-100-160 Plug and 17-4 PH Cage Copes-Vulcan Globe 3" NPS, 316 W/Stellite D-100-160 Plug and 17-4 PH Cage Copes-Vulcan Globe 3" NPS, 316 W/Stell ite D-100-160 Plug and 17-4 PH Cage N I >-"' CJ) UTILITY Consolidated Edison Company of New York, Inc. Consumers Power Co. Duke Power Co. Duquesne Light Co. Florida Power Corp. Florida Power & Light Company
McGuire   &2             Crosby Valve & Gage HB-BP-86     6M6   N56925 Catawba   &2             Dresser             31749A (forged body, forged bonnet)
* PLANT Indian Point 2 Palisades Midland l & 2 Oconee & 2 Oconee 3 Mc Gui re & 2 Catawba & 2 Perkins l , 2, & 3 Cherokee l, 2, & 3 Beaver Valley l Beaver Valley 2 Crystal River 3 Turkey Point 3 & 4 St. Lucie St. Lucie 2 TABLE 2-2 (Continued)
N I                        Perkins 1
VALVE MANUFACTURER Copes-Vulcan Dresser Target Rock Dresser Dresser Control Components, Inc. Control Components, Inc. No PORVs No PORVs Masoneilan Fisher Controls Dresser Copes-Vulcan Dresser Garrett
* 2, & 3       Dresser             31709NA I--'
* VALVE MODEL NO. AND DESCRIPTION*
0 Cherokee 1, 2, & 3       Dresser             31709NA Duquesne Light Co. Beaver Valley 1           Target Rock         69C Beaver Valley 2           Crosby Valve & Gage HB-BP-86     6Ml6   N56963 Florida Power Corp. Crystal River 3           Dresser             31739A (forged body, forged bonnet)
MODEL NO. SIZE AND DESCRIPTION Globe D-100-160 3" NPS, 316 W/Stellite Plug and Haynes #25 Cage l 3/8" Bore 31533VX 80X006 Inlet, 4 11 Outlet 3l 533VX-30 3/32 11 Bore 31533VX-30 3/32 11 Bore Drag Valve 3 11 NPS Drag Valve 3 11 NPS No PORVs No PORVs 20,000 Series 2 11 NPS SS-103-SS-95 3 11 NPS 31533VX-30 5/32 11 Bore Globe 2" NPS, 17-4PH Plug D-100-160 and Cage 3l 533VX-30 5/32" Bore Angle Valve 3 inch inlet, 8 inch outlet *
Florida Power       Turkey Point 3 & 4       Crosby Valve & Gage HB-BP-86     4K26   51249
* UTILITY Georgia Co. Houston Lighting & Power Company Indiana & Michigan Electric Kansas City Power and Light Kansas Gas & Electric Company Louisiana Power r;v & Li g ht Co . Maine Yankee Atomic Power Co. Metropolitan Edi son Co. Northeast Utilities Northern States Omaha Public Power District PLANT Vogtl e l & 2 South Texas 1 & 2 Donald C. Cook l & 2 Ho l f Creek Waterford 3 Maine Yankee Three Mile Island Three Mile Island 2 Millstone 2 Millstone 3 Prairie Island 1 Prairie Island 2 Fort Calhoun l VALVE MANUFACTURER Garrett Copes-Vulcan Masoneilan Garrett No PORVs Dresser Dresser Dresser Dresser Garrett Copes-Vulcan Copes-Vulcan Dresser
        & Light Co.
* VALVE MODEL NO. AND DESCRIPTION*
St. Lucie l               Crosby Valve & Gage HB-BP-86     3K6   N54495 St. Lucie 2               Crosby Valve & Gage HB-BP-86     3K6   N59336 Georgia Power Co. Vogtle 1 & 2             Crosby Valve & Gage HB-BP-86     6M6   N56964 Houston Lighting     South Texas l & 2       Crosby Valve & Gage HB-BP-86     6N8   N60491
MODEL NO. SIZE AND DESCRIPTION Straight Through 3" inlet, 6 11 outlet Globe 3" NPS, 316 W/Stellite D-100-160 Plug and 17-4 PH Cage 20,000 Series 2 11 NPS Straight Through 3" inlet, 6" outlet 31533VX-30 31533VX-30 31533VX-30 31533VX-30 No PORVs 5/16" Bore 3/32" Bore 5/16" Bore 5/16" Bore Straight Through 3" inlet, 6" outlet Globe D-100-160 Globe D-100-160 31533VX-30 2" NPS, l 7-4PH Plug and Cage. 2" NPS, 17-4PH Plug and Cage l 3/32" Bore N I ,_. CXl UTILITY Paci fie Gas & Electric Co. Portland General Electric Co. Power Authority of the State of flew York Public Service of Indiana Public Service Co. of New Hampshire Public Service El ec tr i c & Gas Rochester Gas & E: i e ctr i c Corp . Sacramento Municipal Utility District South Carolina Gas & Electric Southern California Edi son Company Tennessee Va 11 ey Authority
        & Power Co.
* PLANT *Diablo Canyon l & 2 Trojan Pebble Springs l & 2 Indian Point 3 Marble Hill 1 & 2 Seabrook 1 & 2 Sal em l & 2 Ginna RANCHO-SECO l Virgil C. Summer San Onofre l San Onofre 2 & 3 Sequoyah Sequoyah 2 Watts Bar l & 2 Bellefonte l & 2 Yellow Creek l & 2 TABLE 2-2 (Continued)
Indiana &Michigan   Donald C. Cook l & 2     Crosby Valve & Gage HB-BP-86     6M6   51688 Electric
VALVE MANUFACTURER Masoneilan Copes-Vulcan Dresser Copes-Vulcan Co pes-Vul qi.n Copes-Vulcan Copes-Vulcan Copes-Vulcan Dresser Copes-Vulcan MUESCO Controls No PORVs Masonei la n Copes-Vulcan Fisher Controls Dresser No VALVE MODEL NO. AND DESCRIPTION*
 
MODEL NO. SIZE AND DESCRIPTION 20,000 Series 2" NPS* Globe 3 11 NPS, 316 W/Stellite D-100-160 Plug and l7-4PH Cage 31533VX-30 Globe D-100-160 Globe D-100-160 Globe 0-100-160 Globe 0-100-160 Globe D-100-160 31533VX-30 Globe D-100-160 l 5/16" Bore 3" NPS, 316 W/Stellite Plug and Haynes #25 Cage 3" NPS, 316 W/Stellite Plug and 17-4PH Cage 3" NPS, 316 W/Stellite Plug and 17-4PH Cage 2" NPS, 17-4PH Plug and Cage 3" NPS, 316 W/Stell ite Plug and 17-4PH Cage l 5/32" Bore 3" NPS, 316 W/Stellite Plug and 17-4PH Cage 70-18-9 DRTX 2 11 NPS No PORVs 20,000 series 2" NPS Globe 0100-160 3" NPS, 316 W/Stellite Plug and l7-4PH Cage SS-103-SS-95 31533VX-30 3" NPS l 5/16" No PORVs
UTILITY                PLANT TABL.       (Continued)
* TABLE (Continued)
VALVE MANUFACTURER Model No. Size VALVE MODEL NO. AND DESCRIPTION*
* UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*
Assembly No.
MODEL NO. SIZE AND DESCRIPTION Texas Utilities Commanche Peak l & 2 Copes-Vulcan Globe 3tt NPS, 316 W/Stellite Generating Co. D-1 00-1 60 Plug and 17-4PH Cage Toledo Edison Co. Davis Besse l Crosby Valve & Gage Co. HPV-SN l l/2tt Bore Union Electric Co. Ca 11 away l & 2 Garrett Straight 3" inlet, 6tt outlet Through Elertrir <;11rrv l & 2 Copes-Vulcan Globe 2 11 NPS, i 7-4PH Plug and . -.* J
Kansas City Power and Light Wolf Creek             Crosby *valve & Gage   HB-BP-86     6M6   N60446 Kansas Gas &
* Power Co. D-100-160 Cage North Anna & 2 Masoneil an 20,000 Series 2" NPS North Anna 3 & 4 Crosby Valve & Gage HPV-SN 3/Btt Bore Washington Public WPPSS 1 & 4 Dresser 31533VX-30 5/l 6tt Bore N Power Supply System I ........
Electric Co.
3 & 5 No PORVs No PO RVs \.Q Wisconsin Electric Point Beach l & 2 Copes-Vulcan Globe 2" NPS, l 7-4PH Plug and Power D-100-160 Cage Wisconsin Public Kewaunee Masoneil an 20,000 Series 2" NPS Service Corp. *NPS is the nominal pipe size of the valve N I N I-' I I i I I I I I I TABLE..
Louisiana Power         Waterford 3           Oresser               31749A (forged body, forged bonnet)
* EPRI S/RV TEST PROGRAM SELECTED VALVES, VALVES REPRESENTED.
          & Light Co.
VALVE DISTRIBUTION IN PARTICIPATING PWR'S Pressurizer Safety Valves ---*--. Valve Manufacturer Selected Test Valves Valves Model No. Size Model No. 1 ze Inlet Orifice Outlet Inlet Orifice Outlet -Crosby Valve & Gage HB-BP-86 3 K 6 HB-BP-86 3 K 6(small est) Company 6 M 6 3 V') c 1'.L u 6 N 8 4 K2 6 6 K2 6 4 Ml 6 6 Ml 6 4 M 6 6 M 6 6 N B(largest)
Ma i.ne Yankee         Maine Yankee           Dresser               31709KA (cast body, forged bonnet)
Dresser Industries 3l 739A 2.5 No.3 6 31709KA 2.5 K 6 ( s ma 11 est ) 31709NA 6 N 8 31739A 2.5 No.3 6 31749A 3 No.4 6 31759A 3 No.5 6 31709NA 6 N B(largest)
Atomic Power Co.
,,,! 3.513in 2 3.513in 2 Target Rock Corp. 69C 6 6 69C 6 6 Total Note: Inlet and outlet sizes are nominal pipe sizes in inches No. of Plants 3 ') '-6 2 3 6 l 38 6 l 11 3 5 ... 17 l --105 (1) I Inlet and outlet Sizes are nominal p_ipe sizes in inches. (2)
Metropolitan           Three Mile Isl and 1   Dresser               31739A (cast body. cast bonnet and Edi son Co.                                                             forged body, forged bonnet)
Three Mile Island 2   Dresser               31759A (forged body, forged bonnet)
N Northeast Utilities     Millstone 2           Dresser               3l739A *(forged body, forged bonnet)
,_.I
,_.                         Mi 11 stone 3         Crosby Valve & Gage   HB-BP-86     6M6   N56964-4 Northern States         Prairie Isl and 1     Crosby Valve & Gage   HB-BP-86     6Ml 6 52137 & N57872 Power Company Prairie Island 2       Crosby Valve & Gage   HB-BP-86     6Ml 6 52137 Omaha Public           Fort Calhoun 1         Crosby Valve & Gage   HB-BP-86     3K6   50646-1 Power District Paci fie Gas &         Di abl o Canyon l &2   Crosby Valve & Gage   HB-BP-86     6M6   51688 Electric Co.
Portland General       Trojan                 Crosby Valve & Gage   HB-BP-86     6M6   N55366 Electric Co.
* Pebble Springs l   &2 Dresser               31709NA Power Authority         Indian Point 3         Crosby Valve & Gage   HB-BP-86     6M6   51688- l of the State of New York Public Service         Marble Hi 11 l &2     Crosby Valve & Gage   HB-BP-86       6M6   N56964 of Indiana
 
TABLE 2- T (Continued)
UTILITY             PLANT               YALVE MANUFACTURER       VALVE MODEL NO. AND D~SCRIPTION*
Model No. Size     Assembly No.
Public Service Co. Seabrook 1 & 2       Crosby Valve & Gage     HB-BP-86     6M6     N56964 of New Hampshire Public. Service     Salem l & 2         Crosby Valve & Gage       HB-BP-86     6M6     51688 Electric & Gas Rochester Gas and   Ginna               Crosby Valve & Gage       HB-BP-86     4K26     51249 Electric Corp.
Sacramento Municipal RANCHO-SECO l       Dresser                 3l 759A (forged body, forged bonnet)
Utility District South Carolina       Virgil C. Summer*   Crosby Valve & Gage     HB-BP-86       6M6     N56964- l Electric & Gas Southern California San Onofre           Crosby Valve & Gage Edi son Company HB-BP-86       3K26     47469-1   &N51185-2 San Onofre 2 & 3     Dresser                 31709NA N
,__.I Tennessee Valley     Sequoyah 1   &2     Crosby Valve & Gage     HB-BP-86     6M6       51688 N        Authority Watts Bar l & 2     Crosby Valve & Gage     HB-BP-86     6M6       N56964 Bellefonte 1 & 2     Dresser                 31709NA Yellow Creek 1 & 2   Crosby Valve & Gage     HB-BP-86     6N8     N61894 Texas Utilities     Commanche Peak 1 & 2 Crosby Valve & Gage     HB-BP-86     6M6     N56964 Generating Co.
Toledo Edison Co. Davis. Besse 1       Crosby Valve & Gage     HB-BP-86     4Ml6     N54891 & N59303 Union Electric Co. Ca 11 away l & 2     Crosby Va 1 ve & Gage   HB-BP-86     6M6     N60446 Virginia Electric   Surry l & 2         Crosby Valve & Gage     HB-BP-86     6K26     51689
        & Power Co.
North Anna     & 2   Dresser                 31759A (cast bod'"   forged bonnet)
                                                                                          -.)
North Anna 3 & 4     Crosby Valve & Gage     HB-BP-86     4Ml6     N56264
          *
* _J
 
UTILITY                    PLANT
                                                              ~E 2-1       (Continued)
VALVE MANUFACTURER VALVE MODEL NO. & DESCRIPTION*
Model No. Size Assembly No.
Washington Public         WPPSS 1  & 4              Dresser                          31709NA Power Supply System WPPSS 3 & 5                 Crosby Valve & Gage              HB-BP-86    6N8         N60582 Wisconsin                 Point Beach 1 & 2         Crosby Valve & Gage               HB-BP-86     4K26       51249 Electric Power Wisconsin Public           Kewaunee                   Crosby Valve & Gage               HB-BP-86     6Ml6       52137 Service Corp.
* The assembly no. is a unique identifier for each hardware variation in the Crosby Valve   & Gage N
I          Safety Valve model HB-BP-86.
f--'
w The size of the Crosby Safety Valve covers the valve inlet size, (3" - 6") orifice size (K, K2, Ml, M, N) and outlet size (6 8").
11 The only information required to uniquely identify the Target Rock Safety Valves is the model no.
The model no. and any parenthetical information on the _body and bonnet uniquely identify the Dresser Safety Valves.
 
          /
        /
* LIST OF PWR UTILITIES, PLANTS AND POWER OPERATED RELIEF VALVES r,"
{Participating Utilities)
UTILITY               PLANT                    VALVE MANUFACTURER          VALVE MODEL NO. AND DESCRIPTION*-
MODEL NO.        SIZE AND DESCRIPTION Al a bama Power Co. Farley l & 2*            Copes-Vulcan                Globe          3" NPS, 316 W/Stellite Arizona Public         Palo Verdel, 2, & 3                                  D-100-160      Plug and 17-4PH Cage Service Co.                                 No PORVs                              No PO RVs Arkansas Power &       Arkansas Nuclear          Dresser Light Co.         One-1                                                31533VX-30        l 3/ 32" Bore N
I Arkansas Nuclear           No PORVs
........                            One-2                                                           No PO RVs Ul Bal ti more Gas &      Calvert Cliffs l & 2       Dresser                    31533VX-30 Electric Co.                                                                              l 5/16" Bore Carolina Power &      H.B. Robinson 2           Copes-Vulcan                Globe          2" NPS, 17-4 PH Plug Light Company D-100-160      and Cage Shearon Harris            Copes-Vulcan l, 2, 3, & 4                                          Globe          3" NPS, 316 W/Stellite Plug .
D-100-160     and 17-4PH Cage Commonwea 1th          Zion 1 & 2                Copes-Vulcan               Globe         2" NPS, 316 w/Stellite Plug Edi son Company D-100-160     l 7-4PH Cage Byron l & 2              Copes-Vulcan               Globe         3" NPS, 316 W/Stellite D-100-160     Plug and 17-4 PH Cage Braidwood l & 2          Copes-Vulcan               Globe         3" NPS, 316 W/Stellite D-100-160     Plug and 17-4 PH Cage Connecticut Yankee      Connecticut Yankee        Copes-Vulcan Ato mi c Power Co.                                                      Globe         3" NPS, 316 W/Stell ite D-100-160     Plug and 17-4 PH Cage
 
TABLE 2-2  (Continued)
UTILITY            PLANT                VALVE MANUFACTURER      VALVE MODEL NO. AND DESCRIPTION*
MODEL NO. SIZE AND DESCRIPTION Consolidated Edison Indian Point 2      Copes-Vulcan             Globe         3" NPS, 316 W/Stellite Company of                                                    D-100-160     Plug and Haynes #25 Cage New York, Inc.
Consumers Power Co. Palisades            Dresser                  31533VX      l 3/8" Bore Midland l & 2       Target Rock              80X006        2~"    Inlet, 4 Outlet 11 Duke Power Co.      Oconee   & 2       Dresser                  3l 533VX-30      3/32 Bore 11 Oconee 3            Dresser                  31533VX-30        3/32 Bore 11 Mc Gui re  &2       Control Components, Inc. Drag Valve    3 NPS 11 N
I Catawba    & 2      Control Components, Inc. Drag Valve    3 NPS 11 CJ)
Perkins l , 2, & 3   No PORVs                          No PORVs Cherokee l, 2, & 3   No PORVs                          No PORVs Duquesne Light Co. Beaver Valley l      Masoneilan              20,000 Series    2 NPS 11 Beaver Valley 2     Fisher Controls          SS-103-SS-95      3 NPS 11 Florida Power Corp. Crystal River 3      Dresser                 31533VX-30        5/32  11 Bore Florida Power &    Turkey Point 3 &4    Copes-Vulcan            Globe         2" NPS, 17-4PH Plug Light Company                                                  D-100-160    and Cage St. Lucie            Dresser                  3l 533VX-30       5/32" Bore St. Lucie 2          Garrett                  Angle Valve   3 inch inlet, 8 inch outlet
 
UTILITY                  PLANT                VALVE MANUFACTURER  VALVE MODEL NO. AND DESCRIPTION*
MODEL NO.        SIZE AND DESCRIPTION Georgia  Po1~er Co. Vogtl e l & 2        Garrett            Straight Through    3" inlet, 6 11 outlet Houston Lighting        South Texas 1 & 2    Copes-Vulcan
        & Power Company                                                Globe               3" NPS, 316 W/Stellite D-100-160           Plug and 17-4 PH Cage Indiana &Michigan       Donald C. Cook l & 2 Masoneilan Electric                                                      20,000 Series      211 NPS Kansas City Power and Light Ho l f Creek        Garrett            Straight Through    3" inlet, 6" outlet Kansas Gas   & Electric Company Louisiana Power         Waterford 3          No PORVs r;v     & Li ght Co .                                                               No PORVs Maine Yankee Atomic     Maine Yankee        Dresser            31533VX-30              5/16" Bore Power Co.
Metropolitan             Three Mile Island    Dresser            31533VX-30              3/32" Bore Edi son Co.
Three Mile Island 2  Dresser            31533VX-30              5/16" Bore Northeast Utilities     Millstone 2          Dresser            31533VX-30              5/16" Bore Millstone 3          Garrett            Straight Through    3" inlet, 6" outlet Northern States         Prairie Island 1     Copes-Vulcan        Globe              2" NPS, l 7-4PH Plug D-100-160          and Cage.
Prairie Island 2    Copes-Vulcan        Globe              2" NPS, 17-4PH Plug D-100-160          and Cage Omaha Public            Fort Calhoun l       Dresser            31533VX-30          l 3/32" Bore Power District
 
TABLE 2-2 (Continued)
UTILITY                  PLANT                  VALVE MANUFACTURER          VALVE MODEL NO. AND DESCRIPTION*
MODEL NO.     SIZE AND DESCRIPTION Paci fie Gas &          *Diablo Canyon l & 2  Masoneilan Electric Co.                                                            20,000 Series    2" NPS*
Portland General        Trojan                Copes-Vulcan Electric Co.                                                            Globe            311 NPS, 316 W/Stellite D-100-160         Plug and l7-4PH Cage Pebble Springs l & 2 Dresser                      31533VX-30       l 5/16" Bore Power Authority          Indian Point 3        Copes-Vulcan of the State of                                                          Globe            3" NPS, 316 W/Stellite flew York                                                                D-100-160         Plug and Haynes #25 Cage Public Service of        Marble Hill 1  & 2   Co pes-Vul qi.n Indiana                                                                  Globe            3" NPS, 316 W/Stellite D-100-160        Plug and 17-4PH Cage N
,_.I  Public Service Co.     Seabrook 1  & 2      Copes-Vulcan CXl    of New Hampshire                                                         Globe            3" NPS, 316 W/Stellite 0-100-160        Plug and 17-4PH Cage Public Service          Sal em l & 2          Copes-Vulcan El ec tr i c & Gas                                                       Globe            2" NPS, 17-4PH Plug 0-100-160        and Cage Rochester Gas      &    Ginna                  Copes-Vulcan E: i e ctr i c Corp .
Globe            3" NPS, 316 W/Stell ite D-100-160        Plug and 17-4PH Cage Sacramento Municipal    RANCHO-SECO l         Dresser Utility District                                                        31533VX-30        l 5/32" Bore South Carolina          Virgil C. Summer     Copes-Vulcan Gas & Electric                                                          Globe            3" NPS, 316 W/Stellite D-100-160        Plug and 17-4PH Cage Southern California      San Onofre l         MUESCO Controls Edi son Company                                                          70-18-9 DRTX      2 11 NPS San Onofre 2   & 3    No PORVs                              No PORVs Tennessee Va 11 ey      Sequoyah              Masonei la n Authority                                                                20,000 series    2" NPS Sequoyah 2            Copes-Vulcan                 Globe 0100-160  3" NPS, 316 W/Stellite Plug and l7-4PH Cage Watts Bar l & 2      Fisher Controls              SS-103-SS-95 Bellefonte l & 2                                                    3" NPS Dresser                     31533VX-30 l 5/16" Yellow Creek l & 2    No                                     No PORVs
 
UTILITY                  PLANT TABLE          (Continued)
VALVE MANUFACTURER      VALVE MODEL NO. AND DESCRIPTION*
MODEL NO.         SIZE AND DESCRIPTION Texas Utilities          Commanche Peak l & 2   Copes-Vulcan            Globe Generating Co.                                                                          3tt NPS, 316 W/Stellite D-1 00-1 60      Plug and 17-4PH Cage Toledo Edison Co.        Davis Besse l          Crosby Valve & Gage Co. HPV-SN            l l/2tt Bore Union Electric Co.      Ca 11 away l    & 2    Garrett                  Straight          3" inlet, 6tt outlet Through Virgini~ Elertrir  ~    <;11rrv  l* & 2        Copes-Vulcan            Globe Power Co.
                                  . - .* J 2 11 NPS, i 7-4PH Plug and D-100-160         Cage North Anna        &2    Masoneil an              20,000 Series    2" NPS North Anna 3       & 4  Crosby Valve & Gage      HPV-SN                3/Btt  Bore N
Washington Public        WPPSS 1      & 4        Dresser                  31533VX-30            5/l 6tt Bore I
Power Supply System
\.Q                              l~PPSS    3 &5           No PORVs                            No PO RVs Wisconsin Electric      Point Beach l & 2        Copes-Vulcan            Globe Power                                                                                    2" NPS, l 7-4PH Plug and D-100-160        Cage Wisconsin Public        Kewaunee                Masoneil an              20,000 Series Service Corp.                                                                          2" NPS
        *NPS is the nominal pipe size of the valve
 
TABLE..
EPRI S/RV TEST PROGRAM SELECTED VALVES, VALVES REPRESENTED. VALVE DISTRIBUTION IN PARTICIPATING PWR'S Pressurizer Safety Valves Valve Manufacturer              Selected Test Valves                              Valves Re~resented                  No. of Model No.                 Size              Model No.             1 ze                    Plants Inlet  Orifice    Outlet                Inlet    Orifice  Outlet Crosby Valve & Gage      HB-BP-86        3        K      6        HB-BP-86    3        K      6(small est)        3 Company                                6        M      6                      3        V')
1'.L c
u
                                                                                                                                  ')
II                                            6        N      8                      4        K2    6                    6 i                                                                                      6        K2    6                    2 I                                                                                      4        Ml    6                    3 6        Ml    6                    6 I
N I
N I-'                                                                                        4        M      6                    l I                                                                                      6        M      6                  38 I
I                                                                                      6                B(largest)
N                          6 Dresser Industries      3l 739A          2.5      No.3    6        31709KA    2.5        K      6 ( s ma 11 est )    l I                            31709NA          6        N      8        31739A      2.5      No.3    6                  11 31749A      3       No.4     6                    3 31759A      3       No.5    6                    5..
31709NA      6        N      B(largest)          17 2                                        2 Target Rock Corp.       69C              6      3.513in    6        69C          6    3.513in    6                    l Total  105 Note:     Inlet and outlet sizes are nominal pipe sizes in inches
 
(1) I Inlet and outlet Sizes are nominal p_ipe sizes in inches.
(2)
* Crosby valves selected for test include both loop seal internals (3K6, 6M6) and non-loop seal internals (3K6, 6N8)
* Crosby valves selected for test include both loop seal internals (3K6, 6M6) and non-loop seal internals (3K6, 6N8)
* The tested valves with loop seal internals represent plants with Crosby valves installed on a loop seal. The tested valves with non-loop seal internals represent plants with Crosby valves installed without a loop seal. 2-22 *
* The tested valves with loop seal internals represent plants with Crosby valves installed on a loop seal. The tested valves with non-loop seal internals represent plants with Crosby valves installed without a loop seal.
* N I N w * -4 EPRI S/RV TEST PROGRAM SELECTED VALVES, VALVES REPRESENTED, VALVE DISTRIBUTION IN PARTICIPATING PWR'S Power Operated Relief Valves Valve Manufacturer Selected Test Valves Valves Represented Model No. Size Model No. Size Control Components, Inc. Drag Valve -3" NPS Drag Valve 3" NPS Copes-Vulcan Globe 0-100-160 3" NPS Globe D-100-160 2" NPS with 17-4PH cage
2-22                                     *
* with 17-4PH cage and plug and plug Globe D-100-1 60 3" NPS Globe D-100-160 3" NPS with 316 w/stellite with 316 plug and 17-4PH cage w/stell ite plug and 17-4PH cage Globe 0-100-160 3" NPS with 316 w/stell ite plug & Haynes #25 cage Crosby Valve & Gage Co. HPV-SN l 3/8" bore HPV-SN 1 3/8" bore 1 1I2" bore Note: NPS is the valve nominal pipe size No. of Plants 4 I 11 I I I I I 25 2 I j I I : 2 1 N I N TABLE 2-4 (Continued)
 
EPRI S/RV TEST PROGRAM SELECTED TEST VALVES, VALVES REPRESENTED, VALVE DISTRIBUTION IN PARTICIPATING PWR 1 S Operated Relief Valves ----Valve Manufacturer Selected Test Valves Valves Represented Model No. Size Model No. Size Dresser Industries 3l 533VX-30 l 5/16" bore 31533VX-30 l 3/32" bore l 5/32 11 bore l 5/16 11 bore 31533VX l 3/8 11 bore Fisher Controls Co. SS-103-SS-95 3" NPS SS-103-SS-95 3 11 NPS Garrett Pneumatic Straight Through 3" inlet Angle 3" inlet Systems Division 6" outlet 811 outlet Straight Through 311 inlet 511 outlet Masonei l an 20,000 Series 211 NPS 20,000 Series 2" NPS MUES CO Cont ro 1 s, . Inc. 70-18-9 DRTX 211 NPS 70-18-9 DRTX 2" NPS Target Rock Corp.
      *                                                             -4 EPRI S/RV TEST PROGRAM SELECTED VALVES, VALVES REPRESENTED, VALVE DISTRIBUTION IN PARTICIPATING PWR'S Power Operated Relief Valves Valve Manufacturer                   Selected Test Valves                     Valves Represented Model No.                     Size       Model No.           Size       No. of Plants Control Components, Inc.       Drag Valve               -
* 80X-006 inlet 80X-006 inlet 4" outlet 4 11 outlet Total Note: llPS is the valve nominal pjpe size *
3" NPS     Drag Valve         3" NPS           4 Copes-Vulcan                   Globe 0-100-160             3" NPS     Globe D-100-160   2" NPS           11 II with 17-4PH cage
* tlo. of Pl ants 6 3 11 l 3 l 6 9 l 2 --88 Section 3 3.0  
* with 17-4PH cage                             I N
I and plug                                 and plug                                     II N
w                                                                                                                        I Globe D-100-1 60             3" NPS     Globe D-100-160   3" NPS         25 with 316 w/stellite                       with 316 plug and 17-4PH cage                     w/stell ite plug and 17-4PH cage Globe 0-100-160   3" NPS           2 with 316                                     I w/stell ite plug                             j
                                                                          &Haynes #25 cage                             I I
Crosby Valve & Gage Co.       HPV-SN                       l 3/8" bore HPV-SN             1 3/8" bore       2 1 1I2" bore       1 Note: NPS is the valve nominal pipe size
 
TABLE 2-4 (Continued)
EPRI S/RV TEST PROGRAM SELECTED TEST VALVES, VALVES REPRESENTED, VALVE DISTRIBUTION IN PARTICIPATING PWR 1 S Po~~r  Operated Relief Valves Valve Manufacturer                     Selected Test Valves                             Valves Represented Model No.                   Size         Model No.               Size           tlo. of Pl ants Dresser Industries                     3l 533VX-30             l 5/16" bore       31533VX-30       l 3/32" bore                 6 l 5/32 11 bore               3 l 5/16 11 bore           11 31533VX           l 3/8 11 bore                 l N
I  Fisher Controls Co.                     SS-103-SS-95           3" NPS           SS-103-SS-95     311 NPS N                                                                                                                                    3
~
Garrett Pneumatic                       Straight Through       3" inlet         Angle             3"     inlet Systems Division                                                                                                             l 6" outlet                           811   outlet Straight Through 311     inlet                 6 511   outlet Masonei l an                           20,000 Series         211 NPS           20,000 Series     2" NPS                     9 MUES CO Cont ro 1s, . Inc.             70-18-9 DRTX           211 NPS           70-18-9 DRTX     2" NPS                       l Target Rock Corp.
* 80X-006                 2~
11 inlet       80X-006         2~
11 inlet               2 4" outlet                           4 11 outlet Total     88 Note:   llPS is the valve nominal pjpe size
 
Section 3 3.0  


==SUMMARY==
==SUMMARY==
OF SAFETY VALVE OPERABILITY DATA A total of seven PWR pressurizer safety valve designs were tested under steam, water, steam-to-water transition and loop seal conditions.
OF SAFETY VALVE OPERABILITY DATA A total of seven PWR pressurizer safety valve designs were tested under steam, water, steam-to-water transition and loop seal conditions.
The seven safety valves selected for testing in the EPRI program and the safety valves represente'd by the valves tested are identified in Section 2.0 of this report. All safety valve testing as part of the EPRI PWR Safety and Relief Valve Test Program is complete.
The seven safety valves selected for testing in the EPRI program and the safety valves represente'd by the valves tested are identified in Section 2.0 of this report.
The purpose of this section is to present the valve description and inlet piping configurations, "as tested" test matrices, valve performance data and principal for all safety valves tested. To assist in understanding the overall performance of each of the three manufacturer's safety valve clesigns, refer to the Valve Description Section of the "Valve Selection/
All safety valve testing as part of the EPRI PWR Safety and Relief Valve Test Program is complete. The purpose of this section is to present the valve description and inlet piping configurations, "as tested" test matrices,       valve performance data   and principal obst~rvations for all safety valves tested.
To assist in understanding the overall performance of each of the three manufacturer's safety valve clesigns, refer to the Valve Description Section of the "Valve Selection/
Justification Report" (Reference l)as well as Appendix A, "Definition of Key Terms and Parameter::".
Justification Report" (Reference l)as well as Appendix A, "Definition of Key Terms and Parameter::".
3-1
3-1
*. 3.1 DRESSE.R S/\FUY VALVE MO!JEL 31739A
 
* 3 .1.1 Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Dresser 317.39A safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility.
* . 3.1   DRESSE.R S/\FUY VALVE MO!JEL 31739A 3 .1.1   Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Dresser 317.39A safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The valve was tested on both a short (test series 300 and 1100, configuration C) and a long (test series 1000, configuration D) inlet piping configuration. The following is the list of tables that contain the safety valve information/data for these tests:
The valve was tested on both a short (test series 300 and 1100, configuration C) and a long (test series 1000, configuration D) inlet piping configuration.
Table Description                                 Table Number Safety Valve Description and Inlet Piping Configuration                                     3.1.l.a "As Tested" Test Matrix                             3.1.l.b Valve Transient and Leakage Performance Data         3.1.l.c Valve Flow Rate Performance Data                     3.1.l.d
The following is the list of tables that contain the safety valve information/data for these tests: Table Description Safety Valve Description and Inlet Piping Configuration "As Tested" Test Matrix Valve Transient and Leakage Performance Data Valve Flow Rate Performance Data 3.1.2 Principal Observations Table Number 3.1.l.a 3.1.l.b 3.1.l.c 3.1.l.d 3.1.2.a. Short Inlet Configuration (Configuration C). A total of nineteen tests were performed with the valve mounted on a short inlet pipe configuration.
* 3.1.2 Principal Observations 3.1.2.a. Short Inlet Configuration (Configuration C). A total of nineteen tests were performed with the valve mounted on a short inlet pipe configuration. Of these tests, fifteen were steam tests performed with ring positions representative of those utilized in typical PWR plant installations and with ring position adjustments meant to improve the valve test performance. The final steam test ring position used (test no. 1104) was then maintained during the remaining non-steam test conditions. The principal observations for these tests are as fQllows:
Of these tests, fifteen were steam tests performed with ring positions representative of those utilized in typical PWR plant installations and with ring position adjustments meant to improve the valve test performance.
Steam Tests Tests nos. 302 through 308 were steam tests performed at high and low ramp rates, high and low back pressures and with a ring position established by Dresser as a po~ition representative of typical PWR plant ring positions.
The final steam test ring position used (test no. 1104) was then maintained during the remaining non-steam test conditions.
For these test~., the valve opened with.in +3% of the valve design set 3-3
The principal observations for these tests are as fQllows: Steam Tests Tests nos. 302 through 308 were steam tests performed at high and low ramp rates, high and low back pressures and with a ring position established by Dresser as a representative of typical PWR plant ring positions.
 
For these the valve opened with.in +3% of the valve design set 3-3 prt'ssure, but the valve did not.
prt'ssure, but the valve did not. achiev(~ rated lift at an accumulation pressure of 6% above the valve design set point. In one low back pressure test (no. 306), rated flow was achieved at an accumulation pressure of 6%
rated lift at an accumulation pressure of 6% above the valve design set point. In one low back pressure test (no. 306), rated flow was achieved at an accumulation pressure of 6% above the valve design set pressure.
above the valve design set pressure. Rated flow was not achieved at 6%
Rated flow was not achieved at 6% -0ccumulation pressure for the other tests. For the remaining steam tests, nos. 310 through 328 and no. 1104, the tests were performed at a high ramp rate with high and low back pressures and various ring positions.
-0ccumulation pressure for the other tests.
The purpose of these tests was to achieve and maintain the valve rated lift position or the valve rated flow rate. In all of the 300 series tests and the first actuation in test no. 1104, the valve opened within of the valve design set pressure and had stable behavior.
For the remaining steam tests, nos. 310 through 328 and no. 1104, the tests were performed at a high ramp rate with high and low back pressures and various ring positions. The purpose of these tests was to achieve and maintain the valve rated lift position or the valve rated flow rate. In all of the 300 series tests and the first actuation in test no. 1104, the valve opened within ~3% of the valve design set pressure and had stable behavior.
Valve rated lift was achieved and maintained at both high and low back pressures for the latter 300 series tests (nos. 324 and 326). For the final steam test ring position used in test no. 1104 (selection based on 1000 series long inlet pipe configuration tests), rated lift was not maintained at a pressure 6% above the valve design set pressure but rated fl ow was maintained.
Valve rated lift was achieved and maintained at both high and low back pressures for the latter 300 series tests (nos. 324 and 326). For the final steam test ring position used in test no. 1104 (selection based on 1000 series long inlet pipe configuration tests), rated lift was not maintained at a pressure 6% above the valve design set pressure but rated fl ow was maintained. The valve closed with 11.0% blowdown.           Immediately after closing, the valve re-opened at 2240 psia to a partial lift position and closed at 2227 psia.
The valve closed with 11.0% blowdown.
Transition Test During the high back pressure, steam-to-water transition test, the valve opened within !3% of the valve design set pressure, had stable performance and closed with 19.1% blowdown.
Immediately after closing, the valve re-opened at 2240 psia to a partial lift position and closed at 2227 psia. Transition Test During the high back pressure, steam-to-water transition test, the valve opened within !3% of the valve design set pressure, had stable performance and closed with 19.1% blowdown.
Water Tests Three high back pressure water tests were performed at nominal water tem-peratures of 650, 550 and 400&deg;F. The valve had stable behavior for all of the tests. During the 65QOF water test, the valve opened within +3~
Water Tests Three high back pressure water tests were performed at nominal water peratures of 650, 550 and 400&deg;F. The valve had stable behavior for all of the tests. During the 65QOF water test, the valve opened within of design set pressure and closed with blowdown.
of design set pressure and closed with 16.8~ blowdown.
For the 5500 water tE'st, the valve opened at 2387 psi a and closed with 12. 3?:0 blowdown.
For the 5500 water tE'st, the valve opened at 2387 psi a and closed with 12. 3?:0 blowdown. During the 4QQOF water test, the valve opened to a partial lift 3-4
During the 4QQOF water test, the valve opened to a partial lift 3-4
 
* position within +/-_3% of design set pressure.
position within +/-_3% of design set pressure. The system pressure continued to accumulate while the valve remained in a partial lift position. The test was terminated when the tank 1 pressure reached 2749 psia.
The system pressure continued to accumulate while the valve remained in a partial lift position.
Valve Inspection Results The valve was disassembled and inspected during the test series. On inspection, the typical wear pattern observed as scratches or marks on the seat surfaces. To minimize seat leakage, the seats were lapped prior to reassembly and continued testing.
The test was terminated when the tank 1 pressure reached 2749 psia. Valve Inspection Results The valve was disassembled and inspected during the test series. On inspection, the typical wear pattern observed as scratches or marks on the seat surfaces.
3.1.2.b. Long Inlet Pipe Configuration (Configuration D). A total of twelve tests were performed on the Dresser 31739A safety valve mounted on a long inlet pipe configuration. The principal observations for these tests are as follows:
To minimize seat leakage, the seats were lapped prior to reassembly and continued testing. 3.1.2.b. Long Inlet Pipe Configuration (Configuration D). A total of twelve tests were performed on the Dresser 31739A safety valve mounted on a long inlet pipe configuration.
Steam Tests Six drained loop seal steam tests were performed at test initiation ramp rates of 2.3 - 309 psi/sec and with a back pressure range of 220 to 617 psia. The first ring position selected (-48, -60, O) resulted in chatter in test No. 100!:*. The te!;t was terminated after the valve was manually opened to stop the chattering. Following this test, four ring adjustments were made in order to improve the valve test performance. For all of the subsequent tests, the valve opened within +/-_3% of the design set pressure, had stable performance and closed with a bl6wdown range of 10.7 to 14.2%.
The principal observations for these tests are as follows: Steam Tests Six drained loop seal steam tests were performed at test initiation ramp rates of 2.3 -309 psi/sec and with a back pressure range of 220 to 617 psia. The first ring position selected (-48, -60, O) resulted in chatter in test No. 100!:*. The te!;t was terminated after the valve was manually opened to stop the chattering.
For those tests when the system pressure accumulated to 6% above the valve design set pressure, rated lift was achieved.
Following this test, four ring adjustments were made in order to improve the valve test performance.
Loop Se~l - Steam Tests Three loop seal - steam tests were performed with the two fina*1 ring po-sitions of the steam testing. For two of the tests, the valve lift ini-tiation pressure was within +3% of the valve design set pressure. For the other test, the lift initiation pressure was 2595 psia. During two of the loop seal discharges, the valve fluttered and/or chattered at partial lift positions, then the valve popped open on steam at system 3-5
For all of the subsequent tests, the valve opened within +/-_3% of the design set pressure, had stable performance and closed with a bl6wdown range of 10.7 to 14.2%. For those tests when the system pressure accumulated to 6% above the valve design set pressure, rated lift was achieved.
 
Loop  
pressures of 2594 to 2678 psia, stabilized, and closed with 10.0 to 13.9% blowdown. The second ring position used in the loop seal steam tests (-48, -40, +11) was also used for all of the subsequent trans-ition and water tests.
-Steam Tests Three loop seal -steam tests were performed with the two fina*1 ring sitions of the steam testing. For two of the tests, the valve lift tiation pressure was within +3% of the valve design set pressure.
While the loop seal was being discharged during two of the loop seal tests and one transition test, the valve fluttered and/or chattered through partial lift positions at frequences of approximately 170-260 Hz. The valve oscillations during the water discharge caused water-hammer type pressure oscillations in the valve inlet piping. Pressure oscillations measured in the pressure transducers immediately upstream of the valve inlet indicated pressures ranging from 0 psia to a pressure which over-ranged the transducer at 3400-3600 psia. These pressure oscillations were not observed in Tank 1.
For the other test, the lift initiation pressure was 2595 psia. During two of the loop seal discharges, the valve fluttered and/or chattered at partial lift positions, then the valve popped open on steam at system 3-5 pressures of 2594 to 2678 psia, stabilized, and closed with 10.0 to 13.9% blowdown.
Transition Test One high back pressure, loop seal, steam-to-water transition test was performed. The valve lift initiation occurred at a pressure within ~3% of the valve design set pressure. The valve then fluttered and/or chattered at partial lift positions during the loop seal discharge and subsequently popped open on steam at 2535 p~ia. Valve performance was stable on steam and the valve closed on water with 14.0% blowdown.
The second ring position used in the loop seal steam tests (-48, -40, +11) was also used for all of the subsequent ition and water tests. While the loop seal was being discharged during two of the loop seal tests and one transition test, the valve fluttered and/or chattered through partial lift positions at frequences of approximately 170-260 Hz. The valve oscillations during the water discharge caused water-hammer type pressure oscillations in the valve inlet piping. Pressure oscillations measured in the pressure transducers immediately upstream of the valve inlet indicated pressures ranging from 0 psia to a pressure which ranged the transducer at 3400-3600 psia. These pressure oscillations were not observed in Tank 1. Transition Test One high back pressure, loop seal, steam-to-water transition test was performed.
The pressure oscillation description in the Loop Seal-Steam Tests section also applies to the transition test.
The valve lift initiation occurred at a pressure within of the valve design set pressure.
Water Tests Two high back pressure water tests were performed at nominal water temp-eratures of 650 and 550&deg;F. The first test was a fi!10&deg;F water test. ThP valve opened, had stable performance and closed with a 19.3% blowdown.
The valve then fluttered and/or chattered at partial lift positions during the loop seal discharge and subsequently popped open on steam at 2535 Valve performance was stable on steam and the valve closed on water with 14.0% blowdown.
During the 550GF water test, the valve opened and chattered. The. test was terminated after the valve was manually opened to stop chattering .
The pressure oscillation description in the Loop Seal-Steam Tests section also applies to the transition test. Water Tests Two high back pressure water tests were performed at nominal water eratures of 650 and 550&deg;F. The first test was a fi!10&deg;F water test. ThP valve opened, had stable performance and closed with a 19.3% blowdown.
3-6
During the 550GF water test, the valve opened and chattered.
* y_aJ..~_e_ }!1 spe_c ti on .~-es ul ~-s After the water test which was terminated by manually opening and closing the valve to stop chattering, the valve was disassembled and inspected.
The. test was terminated after the valve was manually opened to stop chattering . 3-6 * * 
Galled guiding surfaces and several damaged internal parts were found.
* *
For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage .
* y_aJ ..  
* 3-7
}!1 s pe_c ti on . u l After the water test which was terminated by manually opening and closing the valve to stop chattering, the valve was disassembled and inspected.
* EPRI/CE             VE TEST PROGRAM TABLE 3.1.1 .a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION DRESSER 31739A SAFETY VALVE Valve Descrietion Inlet Piein9 Configuration     11011 Length, in.      I.D., in.
Galled guiding surfaces and several damaged internal parts were found. For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces.
Manufacturer       Dresser Industries Type                                                            Nozzle                   17             6.813 Spring Loaded Safety Valve Model No.         31739 A Serial No.         BN-04372                                     Venturi                  38              6.813 Drawing No.        4CP-2432   Rev. 9                           Pipe                     11             6.813 Body Size (inlet/outlet)     2~    in./     6     in.         Reducer Bore Area 2.545 in.2                                                                     6              6.813/3.152 Orifice Designation*       3                                   Loop Seal Design Set Point Pressure
The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage . 3-7
* 2500                                   Stra *j ght          60              3.152 w                                          psig                         Bends                 4-90&deg;           6 in. radius I
* w I \.0 EPRI/CE VE TEST PROGRAM TABLE 3.1.1 .a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION DRESSER 31739A SAFETY VALVE Valve Descrietion Inlet Piein9 Configuration Length, Manufacturer Dresser Industries Nozzle 17 Type Spring Loaded Safety Valve Model No. 31739 A Venturi 38 Serial No. BN-04372 Drawing No. 4CP-2432 Rev. 9 Pipe 11 Body Size (inlet/outlet) in./ 6 in. Reducer 6 Bore Area 2.545 in.2 Orifice Designation*
\.0 Design Blowdown     5   percent                               Reducer                   4             3 . 152/ 2. 125 Rated Flow   297845 lb/hr. Rated Lift     0. 45. in.         Inlet Flange             6             2.125 Internals Type:       Not applicable Ring Setting Reference Position:                             Inlet Pieing Configuration     11c" The ring setting positions refer to the number of                                   Length, in.      I. D., in.
3 Loop Seal Stra *j ght 60 Design Set Point Pressure
notches relative to the followinq surfaces; Nozzle                   17             6.813 Upper Ring - top holes in the guide Middle Ring- seat plane                                                       38             6.813 Lower Ring - seat plane                             Venturi Pipe                     11             6.813 Reducer                 10             6.813/2.125 Inlet Flange              6             2.125
* 2500 psig Bends 4-90&deg; Design Blowdown 5 percent Reducer 4 Rated Flow 297845 lb/hr. Rated Lift 0. 45. in. Inlet Flange 6 Internals Type: Not applicable Ring Setting Reference Position:
* EPRI/CE              VE TEST DATA "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE DRESSER 3l739A SAFETY VALVE TEST      TEST                                                      CONDITIONS AT VALVE OPENING                              TRANSIENT CONDITIONS VAL VE RING        INLET NO.       TYPE          SETTINGS        PIPING                      IN TANK 1                    AT VALVE INLET  PEAK    PEAK    INDUCED ( 2)    MAX. STEADY UPPER    MIDDLE  LOWER CONFIG.                                                                     TANK 1  BACK- BENDING MOMENT    LIQUID FLOW FLUID    PRESS. TEMP. PRESS. RATE      FLUID    TEMP. PRESS. PRESS. OPENING/CLOSING (PSIA)    (OF)      {PSI/SEC)                                                            (GPM)
Inlet Pieing Configuration The ring setting positions refer to the number of Length, notches relative to the followinq surfaces; Nozzle 17 Upper Ring -top holes in the guide Middle Ring-seat plane Venturi 38 Lower Ring -seat plane Pipe 11 Reducer 10 Inlet Flange 6
(OF)    (PSIA)  (PSIA)      (IN. LBS.)
* 11011 in. I.D., in. 6.813 6.813 6.813 6.813/3.152 3.152 6 in. radius 3 . 152/ 2 . 125 2.125 11c" in. I. D., in. 6.813 6.813 6.813 6.813/2.125 2.125 w I ,_.. ,_..
      *302    STEAM    -48      0      -13      c      STEAM      2483        (l)             3.7      STEAM      (1)   2483 304    STEAM     -48                                                                                                           87        94,250        N/A 0     -13     c     STEAM     2526        (1 )         300        STEAM     (l)   2638 306   STEAM     -48                                                                                                         132        94,250        N/A 0     -13     c       STEAM     2557       (1)         320         STEAM     (l )   2680 308   STEAM     -48                                                                                                         160        84,825        N/A 0     -13     c       STEAM     2547       (1)         329         STEAM     (1)   2677 310     STEAM     -48                                                                                                        477        98,963        N/A
* EPRI/CE VE TEST DATA "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE DRESSER 3l739A SAFETY VALVE TEST TEST VAL VE RING INLET CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS NO. TYPE SETTINGS PIPING IN TANK 1 AT VALVE INLET PEAK PEAK TANK 1 BACK-UPPER MIDDLE LOWER CONFIG. FLUID PRESS. TEMP. PRESS. RATE FLUID TEMP. PRESS. PRESS. (PSIA) (OF) {PSI/SEC) (OF) (PSIA) (PSIA) *302 STEAM -48 0 -13 c STEAM 2483 (l) 3.7 STEAM (1) 2483 87 304 STEAM -48 0 -13 c STEAM 2526 ( 1 ) 300 STEAM (l) 2638 132 306 STEAM -48 0 -13 c STEAM 2557 ( 1 ) 320 STEAM ( l ) 2680 160 308 STEAM -48 0 -13 c STEAM 2547 (1) 329 STEAM (1) 2677 477 310 STEAM 9 c STEAM 2557 ( 1 ) 343 STEAM (l) 2680 170 *312 STEAM -48 0 -13 c STEAM 2524 ( l ) 360 STEAM (l) 2684 485 314 STEAM 20 (3) c STEAM 2537 ( l ) 333 STEAM (l) 2680 177 316 STEAM 40 11 c STEAM 2590 ( l ) 320 STEAM ( 1 ) 2703 195 318 STEAM 40 11 c STEAM 2483 (l) 285 STEAM (l) 2685 195 320 STEAM 40 11 c STEAM 2580 (1) 316 STEAM ( 1) 2667 866 322 STEAM 40 11 c STEAM 2530 (1) 311 STEAM (1) 2670 609 324 STEAM 60 11 c STEAM 2570 (1) 325 STEAM (l) 2693 664 326 STEAM 60 11 c STEAM 2500 ( 1 ) 333 STEAM ( 1 ) 2697 196 *328 STEAM +48 -60 11 c STEAM 2527 (l) 311 STEAM (1 ) 269D 676 N/A Not applicable NOTES: (1) (2) (3) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests, the initiation temperature was the saturation temperature.
                                            -9   c     STEAM       2557       (1)         343         STEAM     (l)   2680
The re&#xb5;orted values are the maximum induced bending monents on the valve discharge flange during opening or closing. The lower ring setting was intended to be -6. The actual setting was between -13 and +11.
      *312     STEAM   -48                                                                                                         170        103,675        N/A 0     -13     c     STEAM       2524       (l )         360         STEAM     (l)   2684 314     STEAM   -48                                                                                                          485        98,963        N/A
                                  -20     (3)     c     STEAM       2537       (l )         333         STEAM     (l)   2680 316   STEAM     -48                                                                                                          177        94,250        N/A
                                -40        11    c      STEAM       2590       (l )         320         STEAM     (1)   2703 w 318         STEAM                                                                                                                 195        89,538        ~II A
                        -48    -40       11     c     STEAM       2483
,_..I                                                                            (l)         285         STEAM     (l)   2685     195         94,250        N/A
,_.. 320       STEAM     -48    -40       11     c     STEAM       2580       (1)         316         STEAM     (1)   2667     866       103,675 322   STEAM     -48                                                                                                                                    N/A
                                -40       11     c     STEAM       2530       (1)         311         STEAM     (1)   2670 324   STEAM     -48                                                                                                          609        103,675        N/A *
                                -60       11     c     STEAM     2570       (1)         325         STEAM     (l)   2693     664 326   STEAM     -48                                                                                                                      89,538        N/fl
                                -60       11     c     STEAM     2500       (1 )         333         STEAM     (1)   2697
      *328     STEAM     +48                                                                                                         196        98,963        N/A
                                -60       11     c     STEAM       2527       (l)         311         STEAM     (1 )   269D     676         89,538        N/A N/A Not applicable NOTES:
(1)
All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests, the initiation temperature was the saturation temperature.
(2)
(3)
The re&#xb5;orted values are the maximum induced bending monents on the valve discharge flange during opening or closing.
The lower ring setting was intended to be -6. The actual setting was between -13 and +11.
* The valve was disassembled, inspected, and refurbished as required for representative test performance.
* The valve was disassembled, inspected, and refurbished as required for representative test performance.
INDUCED ( 2) BENDING MOMENT OPENING/CLOSING (IN. LBS.) 94,250 94,250 84,825 98,963 103,675 98,963 94,250 89,538 94,250 103,675 103,675 89,538 98,963 89,538
 
* MAX. STEADY LIQUID FLOW (GPM) N/A N/A N/A N/A N/A N/A N/A A N/A N/A N/A
EPRl/CE   SAF~VE TEST DATA TABLE 3.1.l.b (Con't)
* N/fl N/A N/A w I ...... w TEST TEST VJ.L VE R JNG NO. TYPE UPPER 1003 . STEAM -48 *1005 STEAM -48 *1008 STEAM -48 1011 STEAM -48 1012 STEAM -48 *1016 LS -48 l 017 LS -48 *1018 STEAM -48 *1021 LS -48 1025 LS -48 TRAJlS 1027 WATER -48 *1030 WATER -48 *ll04a STEAM -48 b 1107 TRANS -48 1110 WATER -48 1112 WATER -48 *1114 WATER -48 N/A Not applicable NOTES: SETTINGS MIOOLE 60 60 40 40 40 40 40 40 -40 PI PING LOWER CONFIG. 0 D 0 D 11 D 5 D 3 D 3 D 3 D 11 D 11 D 11 D 11 D 11 D 11 c 11 c 11 c 11 c 11 c EPRl/CE TEST DATA TABLE 3.1.l.b (Con't) "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE DRESSER.31739A SAFETY VALVE CONDITIONS AT VALVE OPENING IN TANK 1 AT VP1LVE INLET FLUID PRESS. TEMP. PRESS. RATE FLUID TEMP. ( PSIA) (OF) (PSI/SEC) (OF) STEAM 2460 (l) 2.3 STEAM ( l ) STEAM 2425 (l) 248 STEAM ( l ) STEAM 2446 ( l ) 275 STEAM (l) STEAM 2478 ( l ) 286 STEAM ( l ) STEAM 2490 ( l) 309 STEAM ( l ) STEAM 2595 ( l ) 3.4 WATER 300 STEAM 2531 (l) 315 WATER 84 STEAM 2455 (l) 308 STEAM (1) STEAM 2582 ( l ) 329 WATER 104 STEAM/ 2525 (1) 2.0 WATER 104 WATER 2350 621 2.4 WATER 618 WATER 2408 522 l.8 l4ATER 515 STEAM 2550. (1) 316. STEAM (l) STEAM 2240 0.1 STEAM ( l ) STEAi!/ 2489 (l) 2.8 STEAM ( l ) WATER WATER 2521 608 2.3 WATER 570 WATER 2387 513 3.1 493 WATER 2470 414 3.2 WATER 407
                                                              "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE DRESSER.31739A SAFETY VALVE CONDITIONS AT VALVE OPENING                               TRANSIENT CONDITIONS TEST      TEST        VJ.L VE RJNG        :~LET NO. TYPE          SETTINGS          PI PING                    IN TANK 1                     AT VP1LVE INLET PEAK    PEAK    INDUCED (2)    MAX. STEADY TANK 1  BACK- BENDING MOMENT    LIQUID FLOW UPPER    MIOOLE    LOWER CONFIG. FLUID     PRESS.     TEMP.       PRESS. RATE FLUID         TEMP. PRESS. PRESS. OPENING/CLOSING      (GPM)
* TRANSIENT CONDITIONS PEAK PEAK INDUCED (2) MAX. STEADY TANK 1 BACK-BENDING MOMENT LIQUID FLOW PRESS. PRESS. OPENING/CLOSING (GPM) (PSIA) (PSIA) (IN. LBS.) 2460 220 145,625 N/A 2665 550 163, 100 N/A 2680 617 64,075 N/A 2676 596 241,738 N/A 2665 564 69,900 N/A 2595 392 186,400 N/A 2685 191 186 ,400 N/A 2657 570 87,375 N/A 2698 586 157,275 N/A 2536 781 157,275 2008 2363 580 131'063 2492 2458 640 87,375 (3) 2720 600 230,913 N/A 2240 94 2489 725 226,200 2040 2521 500 169,650. 1506 2393 290 158,340 1130 2749 211 84,825 1243 (1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and initiation the saturation temrerature.  
( PSIA)     (OF)         (PSI/SEC)                 (OF)   (PSIA)  (PSIA)      (IN. LBS.)
(2) The reported values are the induced bending moments on the valve discharqe flange during ooen1ng or (3) Unstable conditions precluded reliable measurement.
1003  . STEAM    -48    -60        0      D  STEAM       2460         (l)             2.3       STEAM       (l ) 2460      220      145,625        N/A
      *1005    STEAM    -48      -60        0      D  STEAM       2425         (l)           248         STEAM       (l ) 2665      550      163, 100      N/A
      *1008    STEAM    -48      -80      11      D  STEAM       2446         (l )         275         STEAM       (l)   2680      617        64,075      N/A 1011    STEAM    -48    -60        5      D  STEAM       2478         (l )         286         STEAM       (l ) 2676      596      241,738        N/A 1012    STEAM    -48      -40        3      D  STEAM       2490         ( l)         309         STEAM       (l ) 2665      564        69,900      N/A
      *1016    LS      -48      -40        3      D  STEAM       2595         (l )           3.4     WATER       300   2595      392      186,400        N/A l 017  LS      -48      -40        3      D  STEAM       2531         (l)           315       WATER         84   2685      191      186 ,400      N/A
      *1018    STEAM    -48      -40      11      D    STEAM       2455       (l)           308       STEAM       (1)   2657      570        87,375        N/A w      *1021    LS      -48      -40      11 I                                                  D    STEAM       2582       (l )           329       WATER       104   2698      586      157,275        N/A
...... 1025    LS w                        -48      -40      11      D    STEAM/     2525       (1)             2.0     WATER       104   2536      781      157,275 TRAJlS                                  ~!ATER 2008 1027 WATER        -48      -40      11      D    WATER       2350       621             2.4     WATER       618   2363      580      131'063      2492
      *1030 WATER        -48    -40      11      D    WATER     2408         522             l.8     l4ATER       515   2458      640        87,375        (3)
      *ll04a STEAM      -48    -40      11      c    STEAM     2550.       (1)           316.       STEAM       (l)   2720      600      230,913        N/A b                                          STEAM     2240                         0.1     STEAM       (l ) 2240      94 1107    TRANS    -48      -40      11      c    STEAi!/   2489         (l)             2.8     STEAM       (l ) 2489      725      226,200      2040 WATER 1110 WATER       -48    -40      11      c    WATER     2521         608             2.3     WATER       570   2521      500      169,650. 1506 1112 WATER        -48    -40      11      c    WATER     2387         513             3.1     !~ATER      493   2393      290      158,340      1130
      *1114 WATER        -48    -40      11      c    WATER     2470         414             3.2     WATER       407   2749     211       84,825     1243 N/A Not applicable NOTES:
(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steanVw~tPr tr~nsitio~ test~ t~e initiation te~~er~ture w~s the saturation temrerature.
(2) The reported values are the ~aximum induced bending moments on the valve discharqe flange during ooen1ng or closin~.
(3) Unstable conditions precluded reliable measurement.
* The valve was disassembled, inspected, and refurbished as required f
* The valve was disassembled, inspected, and refurbished as required f
* or representative test performance.
* or representative test performance.
EPR!/CE SAF VE TEST DAT.:. T/lllLE 3.1.1.c VALVE TRANSIENT ANO LEAKAGE PERFORMANCE OATA FOP DRESSER 31739A SAFETY VALVE PRE-TEST VALVE LEAKAGE VALVE OPENING ANO CLOSING POST-TEST VALVE LEAKAGE NOMINAL NOMINAL TANK 1 NOMINAL NOMINAL LEAKAGE VALVE VALVE LEAKAGE INITIAL OPENING OPENING OPENING PRESS. VALVE V.OLVE TEST TEST MEDIA INLET INLET RATE OPEN ING "POP" SIMMER "POP" AT VALVE % BLOWOOWN VALVE MEDIA INLET HILET RATE NO. TYPE PRESS. TEMP. (GPM) PRESS. PRESS. TIME TIME CLOSURE STABILITY PRESS. TEMP. (GPM) (PS IA) (OF) (PSIA) (PSIA) (SEC) (SEC) (PSIA) (PSIA) (OF) 302 STEAM STEAM 2325 SAT 0.0 2483 2482 .0088 .029 2340 7.0 Stable STEAM 2298 SAT 0.0 304 STEAM STEAM 2300 SAT 2526 2526 .0034 .040 2370 5.8 Stable STEAM 2310 SAT 0.0 306 STEAM STEAM 2292 SAT o.o 2557 2557 .004 .026 2352 6.5 Stable STEAM 2296 SAT 0.0 308 STEAM STEAM 2300 SAT 0.0 2547 2549 .004 .034 2393 4.9 Stable STEAM 2296 SAT 0.75 310 STEAM STEAM 2300 SAT 0.0 2557 2557 .005 .025 2337 7. l Stable STEAM 2300 SAT 0.0 312 STEAM STEAM 2311 SAT 0.0 2529 2533 .003 .034 2393 4.9 Stable STEAM 2319 SAT o.o 314 STEAM STEAM 2308 SAT 0.0 2537 2542 .007 .024 2320 7.8 Stable STEAM 2321 SAT o.o w 316 STEAM STEAM 2300 SAT 0.0 2590 2590 .005 .012 2187 13. l Stable STEAM 2300
 
* SAT 0.0 I I--' 318 STEAM STEAM 2300 SAT 0.0 2483 2485 .006 .021 2164 14.0 Stable STEAM 2310 SAT o.o U1 320 STEAM STEAM 2301 SAT 0.0 2580 2582 .005 .015 2340 7.0 Stable STEAM 2303 SAT 0.05 322 STEAM STEAM 2300 SAT o.o 2530 2535 .005 . 015 2237 11 . 1 Stable STEAM 2345 SAT (). 17 324 STEAM STEAM 2300 SAT 0.0 2570 2572 .006 .013 2200 12.6 Stable STEAM 2304 S."T 0.0 326 STEAM STEAM 2300 SAT 0.0 2500 2502 .006 .012 2092 16.9 Stable STEAM 2300 SAT 0.0 328 STEAM STEAM 2300 SAT 0.0 2527 2530 .007 .016 2260 10.2 Stable STEAM 2300 SAT 0.0 w I I-' '-J PRE-TEST VALVE LEAKAGE EPRl/CE '.> LVE TEST DATA .1.1.c (Can't) VALVE TRANSIENT ANO LEAKAGE PERFORMANCE DATA FOR THE DRESSER 31739A SAFETY VALVE VALVE NOMINAL VALVE INLET PRESS. { P) r A I NOMINAL VALVE INLET TEMP. fOF\ LEAKAGE INITIAL OPENING "POP" PRESS. 'PSiA' OPENING ANO CLOSING TANK 1:-'----'--------
EPR!/CE SAF           VE TEST DAT.:.
POST-TEST VALVE LEAKAGE NOMINAL NOMINAL TEST NO. 1003 1005 1008 1011 1012 1016 1017 1018 1021 1025 1027 1030 1104a b 1107 lllO 1112 1114 TEST TYPE STEAM STEAM STEAM STEAM STEAM MEDIA STEAM STEAM STEAM STEAM STEAM LS WATER LS WATER STEAM STEAM LS WATER LS TRANS WATER WATER WATER WATER WATER STEAM STEAM TRAl1S srn HATE'l WATER l*IATER WATER WATER N/A Not Applicable NOTES: 2300 2285 2287 2300 2285 2284 2300 2300 2303 2285 2295 2280 2300 2280 2298 2287 2275 SAT SAT SAT SAT SAT 101 96 SAT 290 172 317 515 SAT SAT 610 544 411 RATE OPENING (GPM) PRESS. 0.5 0.5 0.23 0.0 0.0 o.o 0.0 0. 15 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ,,,,.,."'
T/lllLE 3.1.1.c VALVE TRANSIENT ANO LEAKAGE PERFORMANCE OATA FOP         T&#xb5;~
r.)11-\ 2460 2425 2446 2478 2490 2595 2531 2455 2582 2525 2350 2408 2550 2240 2489 2521 2387 2470 2460 2431 2450 2482 2495 2594 2678 2458 2656 2535 2.150 2382 2550 2489 2521 2391 2551 OPENING SIMMER TIME s1:c* . 011 .014 .0076 .008 .008 0.368 .632 .008 .279 5.37 .010 .128 .004 .009 . 01 2.00 37 OPENING "POP" TIME SEC . 015 . 016 . 014 .016 .021 .007 .024 .024 .007 .011 .026 N/A .013 .)ll 8 .043 N/11 N/A PRESS. AT VALVE % BLOWDOWN CLOSURE (PSIA) 2323 (4) 2160 2191 2248 2266 2168 2211 2177 2166 2032 (4) 2238 2227 2038 2096 2208 ( 5) 7.7 (4) 14;2 13.0 10.7 10.0 13. 9 12.2 13. 5 14.0 19.3 (4) 11 .0 11. 5 19. 1 16.8 12.3 (5) (1) The value experienced low amplitude chatter for approximately 5 sec following each closure. ( 2) No measurement was taken. * (3) The valve fluttered and/or chattered during loop seal discharge.
DRESSER 31739A SAFETY VALVE PRE-TEST VALVE LEAKAGE                                 VALVE OPENING ANO CLOSING NOMINAL  NOMINAL                                                                                            POST-TEST VALVE LEAKAGE VALVE    VALVE LEAKAGE                                                  TANK 1                                 NOMINAL NOMINAL TEST    TEST                                    INITIAL     OPENING     OPENING     OPENING       PRESS.
The valve stabilized on steam. (4) The test was terminated the valve Has manually opened to stop chatter, interfering with this measurement.  
MEDIA     INLET   INLET   RATE OPEN ING     "POP"                                                                       VALVE V.OLVE LEAKAGE NO. TYPE            PRESS. TEMP.                                  SIMMER        "POP"     AT VALVE % BLOWOOWN   VALVE   MEDIA   INLET HILET       RATE (GPM)   PRESS. PRESS.         TIME         TIME   CLOSURE (PS IA)   (OF)           (PSIA)                                                             STABILITY            PRESS. TEMP.      (GPM)
(5) This test was terminated when the valve did not relieve the inlet pressure.  
(PSIA)       (SEC)       (SEC)     (PSIA)                                 (PSIA)   (OF) 302   STEAM STEAM     2325     SAT   0.0     2483         2482         .0088       .029 304    STEAM  STEAM                                                                              2340         7.0   Stable   STEAM   2298 2300      SAT            2526        2526                                                                                  SAT   0.0 306                                                                        .0034       .040     2370         5.8     Stable STEAM   STEAM    2292    SAT     o.o                                                                                    STEAM   2310      SAT   0.0 2557         2557         .004         .026     2352 308  STEAM  STEAM    2300                                                                                  6.5     Stable   STEAM   2296       SAT SAT     0.0     2547         2549         .004                                                                           0.0 310                                                                                    .034     2393         4.9     Stable STEAM   STEAM    2300    SAT     0.0                                                                                    STEAM   2296      SAT   0.75 2557         2557         .005         .025     2337 312  STEAM  STEAM    2311                                                                                  7. l   Stable     STEAM   2300       SAT SAT   0.0     2529         2533         .003                                                                           0.0 314    STEAM                                                                            .034       2393         4.9   Stable     STEAM STEAM    2308    SAT   0.0     2537                                                                                     2319      SAT    o.o w                                                                  2542       .007         .024     2320         7.8 316    STEAM  STEAM    2300      SAT                                                                                  Stable     STEAM   2321       SAT   o.o I                                            0.0     2590         2590         .005         .012 I--'
(6) The valve chattered on closure. VALVE STAB rt. ITV VALVE VALVE LEAKAGE MEDIA INLET INLET RATE TEMP. (GPM) (PSIA) (OF) Stahle STEAM Chatter (6) STEAM Stable STEAM Stable STEAM Stable STEAM Stable STEAM Stable (3) STEAM Stable STEAM Stable (3) STEAM Stable (3) WATER Stable WATER Chatter (2) 2285 2285 2290 2302 2280 2300 2278 2300 2300 2295 2000 (2) Stable {l) STEAM <2230 Stable (l) STEAM Stable Stable Stable Stable 2280 l4ATER 2285 WATER 2290 WATER 2285 SAT SAT SAT SAT SAT SAT SAT SAT SAT 317 (2) (2) SAT SAT 615 535 410 0.5 0.0 2.5 0.18 0.36 0.32 0.17 0.28 0.0 0.0 0.0 (2) 1. 3 l. 3 .15 'L '1 0.0 0.0
318  STEAM  STEAM                                                                              2187        13. l   Stable   STEAM   2300
* EPR l /CE VE TEST DATA TABLE 3.1.1.d 'ML Vt Rf,il Uf\ If\ t UK IHt. DRESSER 31739A SAFETY VALVE CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ( 1) BASED ON BASED ON BASED Of: tl/\SED ON TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE TEST TEST % RATED % RATED % RATED % RATED % RATED rRATrD -ntATED % RATED NO. TYPE LIFT STEAM LI FT STEAM LIFT STEAM LIFT STEAM FLOW FLOW FLOW FLOW 302 STEAM N/A N/A N/A N/A N/A N/A N/A N/A 304 STEAM 56 78 44 60 ( 2) (2) 59 83 306 60 84 61 86 73 l 07 73 107 308 STEAM 30 114 30 44 45 67 (2) (2) 310 STEAM 69 98 72 103 77 114 (2) (2) 312 STEAM 18 27 18 27 40 60 41 61 314 STEAM 79 110 80 113 82 118 (2) (2) 316 STEAM 110 122 110 124 110 128 111 130 318 STEAM lll 122 110 124 111 128 (2) (2) w I 320 STEAM 44 64 44 64 104 127 (2) (2) ,_. l.O 322 STEAM 78 113 104 122 110 129 (2) (2) 324 STEAM 110 122 111 125 112 129 112 130 326 STEAM lll 122 112 124 112 129 112 130 328 STEAM 93 118 l 04 122 112 129 117 131 NOTES: (1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.  
* SAT U1                          2300     SAT     0.0     2483         2485                                                                                         0.0 320                                                                        .006         .021     2164       14.0     Stable STEAM   STEAM    2301    SAT     0.0                                                                                    STEAM   2310      SAT   o.o 2580         2582         .005         .015 322  STEAM  STEAM 2340         7.0   Stable   STEAM   2303       SAT 2300     SAT     o.o     2530         2535       .005         . 015     2237       11 . 1 0.05 324  STEAM  STEAM     2300    SAT                                                                                   Stable    STEAM    2345      SAT  (). 17 0.0     2570         2572       .006         .013 326  STEAM                                                                                      2200       12.6     Stable   STEAM   2304 STEAM    2300    SAT    0.0    2500                                                                                                S."T 0.0 2502       .006         .012       2092       16.9 328  STEAM  STEAM    2300    SAT                                                                                  Stable   STEAM   2300       SAT   0.0 0.0     2527         2530       .007         .016       2260       10.2     Stable   STEAM   2300       SAT   0.0
 
EPRl/CE '.>             LVE TEST DATA
                                                                                                  .1.1.c (Can't)
VALVE TRANSIENT ANO LEAKAGE PERFORMANCE DATA FOR THE DRESSER 31739A SAFETY VALVE PRE-TEST VALVE LEAKAGE                                    VALVE OPENING ANO CLOSING NOMINAL NOMINAL                                                                                                           POST-TEST VALVE LEAKAGE VALVE      VALVE                                                            TANK 1 : - ' - - - - ' - - - - - - - -
TEST       TEST                                LEAKAGE INITIAL    OPENING      OPENING        OPENING                                                    NOMINAL NOMINAL MEDIA      INLET      INLET  RATE    OPENING                                            PRESS.                                           VALVE VALVE LEAKAGE NO.        TYPE             PRESS.                                "POP"        SIMMER        "POP"    AT VALVE % BLOWDOWN          VALVE TEMP.  (GPM)    PRESS. PRESS.                                                                          MEDIA     INLET  INLET      RATE
{ P) rAI    fOF\            ,,,,.,."'                   TIME          TIME  CLOSURE                    STAB rt. ITV r.)11-\  'PSiA'          s1:c*          SEC                                                      PP~SS. TEMP. (GPM)
(PSIA)                                          (PSIA)    (OF) 1003        STEAM  STEAM      2300       SAT     0.5      2460      2460          . 011          . 015 1005      STEAM  STEAM                                                                                      2323          7.7        Stahle        STEAM  2285 2285      SAT    0.5     2425      2431                                                                                            SAT    0.5
                                                                                            .014          . 016        (4) 1008        STEAM  STEAM        2287      SAT (4)        Chatter (6)  STEAM  2285      SAT    0.0 0.23    2446      2450          .0076        . 014 1011        STEAM  STEAM                                                                                      2160        14;2          Stable      STEAM    2290 2300      SAT      0.0     2478      2482                                                                                              SAT    2.5 1012                                                                                  .008          .016      2191        13.0 STEAM  STEAM      2285      SAT                                                                                          Stable      STEAM    2302    SAT      0.18 0.0      2490      2495          .008 1016                                                                                                .021      2248        10.7        Stable        STEAM LS      WATER      2284      101    o.o      2595                                                                                               2280    SAT      0.36 2594       0.368            .007      2266        10.0 1017        LS      WATER      2300        96                                                                                          Stable      STEAM    2300    SAT      0.32 0.0      2531      2678          .632          .024 1018      STEAM    STEAM                                                                                    2168        13. 9        Stable (3)  STEAM    2278    SAT 2300        SAT    0. 15    2455      2458                                                                                                      0.17 1021                                                                                .008           .024      2211        12.2        Stable        STEAM w                LS    WATER      2303      290      0.0      2582                                                                                              2300      SAT    0.28 I                                                                          2656          .279          .007      2177        13. 5 I-' 1025    LS TRANS  WATER      2285      172 Stable (3)    STEAM  2300    SAT      0.0
'-J                                                    0.0      2525      2535        5.37            .011 1027      WATER    WATER                                                                                      2166        14.0          Stable (3)  WATER    2295    317 2295      317      0.0    2350        2.150                                                                                                    0.0
                                                                                          .010          .026       2032        19.3 1030      WATER    WATER      2280      515                                                                                          Stable      WATER    2000      (2)    0.0 0.0    2408      2382          .128          N/A         (4)         (4)         Chatter        (2) 1104a                                                                                                                                                            (2)   (2)     (2)
STEAM  STEAM      2300      SAT      0.0     2550      2550          .004          .013      2238        11 .0         Stable {l) STEAM    <2230 b                                                                                                                                                                SAT      1. 3 2240                                              2227        11. 5         Stable (l) STEAM                        l. 3 1107      TRAl1S  srn        2280      SAT    0.0      2489      2489          .009          .)ll 8     2038        19. 1        Stable                2280 lllO      HATE'l  WATER      2298                                                                                                                                    SAT        .15 610      0.0    2521      2521          . 01          .043      2096        16.8          Stable      l4ATER  2285    615 1112      l*IATER  ~IATER      2287      544                                                                                                                                  'L '1 0.0      2387      2391        2.00            N/11 1114                                                                                                          2208        12.3        Stable        WATER    2290    535    0.0 WATER    WATER      2275      411    0.0      2470      2551    37                  N/A          ( 5)        (5)       Stable        WATER    2285    410    0.0 N/A Not Applicable NOTES:
(1) The value experienced low amplitude chatter for approximately 5 sec following each closure.
( 2) No measurement was taken.       *
(3) The valve fluttered and/or chattered during loop seal discharge. The valve stabilized on steam.
(4) The test was terminated ~ihen the valve Has manually opened to stop chatter, interfering with this measurement.
(5) This test was terminated when the valve did not relieve the inlet pressure.
(6) The valve chattered on closure.
* EPR l /CE            VE TEST DATA TABLE 3.1.1.d
                                                                    'ML Vt ~L0W Rf,il rEKtUKMfl~Lt Uf\ If\ t UK IHt.
DRESSER 31739A SAFETY VALVE CONDITIONS AT 3% ACCUMULATION (1)                         CONDITIONS AT 6%    .~CCUMULATION ( 1)           LIQUID FLOW MEASUREMENT BASED ON                  BASED ON                      BASED Of:
TANK PRESSURE                                                                          tl/\SED ON VALVE INLET PRESSURE              TANK PRESSURE          VALVE INLET PRESSURE TEST    TEST    %RATED        %RATED      %RATED      %RATED                                                              TANK CONDITIONS      STEADY NO. TYPE                                                            % RATED      rRATrD    -ntATED            %RATED  PRESS. TEMP.
LIFT          STEAM      LI FT        STEAM            LIFT          STEAM                                                    LIQUID  % RATED FLOW                                                                LIFT          STEAM    (PSIA)    (OF)       FLOW    LIFT FLOW                            FLOW                        FLOW                      (GPM) 302  STEAM      N/A            N/A      N/A          N/A              N/A            N/A        N/A              N/A 304  STEAM      56                                                                                                          N/A        N/A      N/A        N/A 78          44          60              ( 2)           (2) 306                                                                                                  59                83    N/A        N/A      N/A        N/A STE1~M      60            84          61          86              73            l 07        73 308  STEAM                                                                                                          107      N/A       N/A     N/A       N/A 30            114          30          44              45              67      (2)              (2)      N/A       N/A     N/A 310  STEAM      69            98          72                                                                                                            N/A 103                77          114        (2)             (2) 312  STEAM      18                                                                                                          N/A      N/A      N/A      N/A 27        18            27              40              60 314                                                                                                  41              61     N/A        N/A      N/A      N/A STEAM     79            110          80        113                82          118        (2)             (2)     N/A 316    STEAM     110           122                                                                                                     N/A      N/A      N/A 110         124               110           128       111 318   STEAM                                                                                                         130      N/A        N/A      N/A        N/A w                          lll            122        110         124               111           128       (2)             (2)     N/A
,_.I       320   STEAM       44             64                                                                                                     N/A      N/A        N/A 44          64              104            127 l.O 322                                                                                                 (2)             (2)     N/A        N/A      N/A        N/A STEAM       78            113        104          122               110            129       (2)              (2)      N/A 324    STEAM     110            122                                                                                                     N/A      N/A        N/A 111          125              112           129 326                                                                                                  112              130      N/A        N/A      N/A        N/A STEAM    lll            122        112          124              112            129        112              130      N/A 328    STEAM      93                                                                                                                    N/A      N/A        N/A 118        l 04        122              112            129        117              131      N/A        N/A      N/A        N/A NOTES:
(1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.
(2) The appropriate measurement conditions were not achieved.
(2) The appropriate measurement conditions were not achieved.
LIQUID FLOW MEASUREMENT TANK CONDITIONS STEADY PRESS. TEMP. LIQUID % RATED (PSIA) (OF) FLOW LIFT (GPM) N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A w I N ......
* EPR!/CE se,ALVE TEST DATA TABLE 3.1.1.d (Can't)
* EPR!/CE se,ALVE TEST DATA TABLE 3.1.1.d (Can't) VALVE FLOW RATE PERFORMANr.F OATA FOR THE DRESSER 31739A SA.FETY VALVE CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ACCUMULATION ( 1) BASED ON BASED N: BASED or: BASED ON TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE TEST TEST % RATED % RATED % RATED % RATED % RATED % RATED % RA1ED % RATED NO. TYPE LIFT STEAM LIFT STEAM LIFT LIFT )TEAM FLOW FLOW FLOW FLOW 1003 STEAM N/A N/A N/A N/A rl/A N/A N/A N/A 1005 STEAM 63 87 74 104 106 121 (3) (3) 1008 STEAM 88 111 112 1a 120 124 (3) ( 3) 1011 STEAM 87 111 98 123 118 124 (3) (3) 1012 STEAM 72 99 109 122 119 125 (3) (3) 1016 LS N/A N/A N/A N/A N/A N/A N/A N/A 1017 LS 120 120 115 116 120 126 (3) (3) 1018 STEAM 80 107 114 116 (3) (3) (3) (3) 1021 LS 89 110 111 115 121 124 (3) (3) 1025 LS TRANS N/A N/A N/A N/A N/A N/A N/A N/A 1027 WATER N/A N/A N/A N/A N/A N/A N/A N/A 1030 WATER N/A N/A N/A N/A N/A N/A N/A N/A l 104a STEAM 77 107 80 112 90 121 112 129 1107 N/A N/A N/A N/A N/A N/A N/A N/A lllO WATER N/A N/A N/A N/A N/A N/A N/A N/A lll 2 WATER N/A N/A N/A N/A N/A N/A N/A N/A 1114 WATER N/A N/A N/A N/A N/A N/A N/A N/A N/A Not Applicable NOTES: g\ (3) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.
VALVE FLOW RATE PERFORMANr.F OATA FOR THE DRESSER 31739A SA.FETY VALVE CONDITIONS AT 3% ACCUMULATION (1)                     CONDITIONS AT 6% ACCUMULATION ( 1)           LIQUID FLOW MEASUREMENT BASED ON                 BASED N:                   BASED or:               BASED ON TANK PRESSURE       VALVE INLET PRESSURE           TANK PRESSURE         VALVE INLET PRESSURE   TANK CONDITIONS      STEADY TEST     TEST     %RATED       % RATED     % RATED     % RATED       % RATED       % RATED     %RA1ED     % RATED  PRESS. TEMP.      LIQUID  % RATED NO. TYPE     LIFT         STEAM     LIFT       STEAM           LIFT           ~TEAM    LIFT       )TEAM     (PSIA)    (OF)        FLOW   LIFT FLOW                   FLOW                         FLOW                   FLOW                        (GPM) 1003       STEAM   N/A           N/A         N/A         N/A           rl/A           N/A      N/A          N/A      N/A      N/A       N/A       N/A 1005       STEAM   63             87         74         104           106             121       (3)           (3)     N/A      N/A      N/A      N/A 1008       STEAM   88           111       112           1a           120             124       (3)           ( 3)   N/A      N/A      N/A      N/A 1011       STEAM   87           111         98           123         118             124     (3)           (3)     N/A      N/A      N/A      N/A 1012       STEAM   72             99       109           122           119             125       (3)           (3)     N/A      N/A        N/A      N/A 1016       LS     N/A            N/A        N/A          N/A          N/A             N/A     N/A           N/A     N/A       N/A       N/A       N/A 1017       LS     120           120       115           116           120             126       (3)           (3)     N/A      N/A        N/A      N/A 1018       STEAM   80           107       114           116           (3)           (3)       (3)           (3)     N/A      N/A        N/A      N/A w          1021       LS       89           110       111           115         121             124     (3)           (3)     N/A      N/A        N/A      N/A I
N
......      1025     LS TRANS N/A           N/A       N/A           N/A           N/A             N/A     N/A           N/A   2382      649    2492        97 1027       WATER   N/A           N/A         N/A           N/A         N/A             N/A       N/A           N/A   2307      622      2350        99 1030       WATER   N/A           N/A       N/A           N/A           N/A             N/A     N/A           N/A       (2)      (2)      (2)      (2) l 104a     STEAM     77           107         80         112             90           121     112           129     N/A        rl/A    N/A      N/A 1107               N/A           N/A       N/A           N/A           N/A             N/A     N/A           N/A   2346      647      2040        84 lllO       WATER   N/A           N/A         N/A           N/A         N/A             N/A     N/A           N/A   2302      603      1506        39 lll 2     WATER   N/A           N/A         N/A           N/A         N/A             N/A     N/A           N/A   2254        539    1130        28 1114       WATER   N/A           N/A         N/A           N/A           N/A             N/A     N/A           N/A   2619        401    1243        26 N/A   Not Applicable NOTES:
g\
(3)
During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.
Unstable conditions precluded reliable measurement.
Unstable conditions precluded reliable measurement.
The appropriate measurement conditions were not achieved.
The appropriate measurement conditions were not achieved.
LIQUID FLOW MEASUREMENT TANK CONDITIONS STEADY PRESS. TEMP. LIQUID % RATED (PSIA) (OF) FLOW LIFT (GPM) N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 2382 649 2492 97 2307 622 2350 99 (2) (2) (2) (2) N/A rl/A N/A N/A 2346 647 2040 84 2302 603 1506 39 2254 539 1130 28 2619 401 1243 26
 
* 3.2 DRESSER SAFETY VALVE MODEL 31709NA 3.2.l Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Dresser 31709NA safety valve model at the EPRI/CE PWR Safety* and Relief Valve Test Facility.
3.2  DRESSER SAFETY VALVE MODEL 31709NA 3.2.l    Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Dresser 31709NA safety valve model at the EPRI/CE PWR Safety* and Relief Valve Test Facility. The valve was tested on both a short (test series 600 and 1300, configuration B) and a long (test series 200, configuration A) inlet piping configuration. The following is the list of tables that contain the safety valve information/data for these tests:
The valve was tested on both a short (test series 600 and 1300, configuration B) and a long (test series 200, configuration A) inlet piping configuration.
Jable Description                                Table Number Safety Valve Description and Inlet Piping Configuration                                    3. 2. 1. a "As Tested" Text Matrix                            3. 2. l. b Valve Transient and Leakage Performance Data        3.2. l.c Valve Flow Rate Performance Data                    3.2. l.d 3.2.2   Principal Observations 3.2.2.a. Short Inlet Pipe Configuration (Configuration B). A total of fourteen tests was performed on the Dresser 31709NA safety valve with a short inlet pipe configuration. Each of the tests were performed with the valve middle and lower ring positions established by Dresser based on previous EPRI/CE test experience obtained on the Dresser 31739A safety valve. The valve ring positions were not necessarily typical of PWR plant ring p0sitions. The principal observations for these tests are as fo 11 ows:
The following is the list of tables that contain the safety valve information/data for these tests: Jable Description Safety Valve Description and Inlet Piping Configuration "As Tested" Text Matrix Valve Transient and Leakage Performance Data Valve Flow Rate Performance Data 3.2.2 Principal Observations Table Number 3. 2. 1. a 3. 2. l. b 3.2. l.c 3.2. l.d 3.2.2.a. Short Inlet Pipe Configuration (Configuration B). A total of fourteen tests was performed on the Dresser 31709NA safety valve with a short inlet pipe configuration.
Steam Tests A total of eight steam tests was performed with high and low ramp rates, varying back pressures from 174 to 530 psia and three different middle ring positions. Neither the valve upper or lower ring positirn was changed during these tests. For all of these tests, the valve opened 3-23
Each of the tests were performed with the valve middle and lower ring positions established by Dresser based on previous EPRI/CE test experience obtained on the Dresser 31739A safety valve. The valve ring positions were not necessarily typical of PWR plant ring p0sitions.
 
The principal observations for these tests are as fo 11 ows: Steam Tests A total of eight steam tests was performed with high and low ramp rates, varying back pressures from 174 to 530 psia and three different middle ring positions.
within  +3%  of  the V<ilvl~ i-Jesi~111 *s1~t presstffe und exhibited ~lable performance. In tests wilere the inlet pressure accumulated to 6% above the valve design set pressure, the valve achieved rated lift. Valve bJowdown varied depending on the position of the middle ring and the back pressure.
Neither the valve upper or lower ring positirn was changed during these tests. For all of these tests, the valve opened 3-23 within +3% of the presstffe und exhibited performance.
Generally, the valve blowdown decreased as the back pressure increased and as the middle ring was adjusted to higher test positions. Slowdown ranged from a maximum of 14.2% to a minimum of 7.5%.
In tests wilere the inlet pressure accumulated to 6% above the valve design set pressure, the valve achieved rated lift. Valve bJowdown varied depending on the position of the middle ring and the back pressure.
Transition Tests Two steam-to-:water transition tests with an intermediate back pressure (approximately 400 psia) were performed using the highest and lowest middle ring positions of the steam tests. For both tests, the valve opened within +3% of the valve design set pressure and exhibited stable performance. The valve blowdown ranged from 17.0% to 18.5%.
Generally, the valve blowdown decreased as the back pressure increased and as the middle ring was adjusted to higher test positions.
Water Tests Four water tests were performed with an intermediate back pressure at nom-inal water temperatures of 650, 550 and 400&deg;F.
Slowdown ranged from a maximum of 14.2% to a minimum of 7.5%. Transition Tests Two steam-to-:water transition tests with an intermediate back pressure (approximately 400 psia) were performed using the highest and lowest middle ring positions of the steam tests. For both tests, the valve opened within +3% of the valve design set pressure and exhibited stable performance.
* During the two 650&deg; water tests performed which used the highest and lowest middle ring positions of the steam tests, the valve opened at system pressures of 2393-2412 psia and exhibited stable performance.           Valve blowdowns ranged from 16.3 to 22.6%.
The valve blowdown ranged from 17.0% to 18.5%. Water Tests Four water tests were performed with an intermediate back pressure at inal water temperatures of 650, 550 and 400&deg;F. During the two 650&deg; water tests performed which used the highest and lowest middle ring positions of the steam tests, the valve opened at system pressures of 2393-2412 psia and exhibited stable performance.
The two -subsequent water tests (550, 4000F) were performed using the highest middle ring position. For both tests, the valve opened at a system pressure within ~3% of the valve design s~t pressure. During the 550&deg;F water test, the valve opened, had stable behavi6r and closed with 4.0%
Valve blowdowns ranged from 16.3 to 22.6%. The two -subsequent water tests (550, 4000F) were performed using the highest middle ring position.
blowdown.
For both tests, the valve opened at a system pressure within of the valve design pressure.
Dllring the 400&deg;F water test, the valve opened at 2558 psia and exhibited five partial lift cycles over a period of three seconds. The valve then 3-24
During the 550&deg;F water test, the valve opened, had stable behavi6r and closed with 4.0% blowdown.
 
Dllring the 400&deg;F water test, the valve opened at 2558 psia and exhibited five partial lift cycles over a period of three seconds. The valve then 3-24 * 
opened and chattered. Three seconds later in the transient, the valve stopped chattering without manual actuation and then closed. After the transient, a ste~m leakage test was attempted. The valve partially
' ' *
                                    *opened at which p9int the leak test was terminated.
* opened and chattered.
Valve Inspection Results After the 4000F test, the valve was disassembled and inspected.                 Galled guiding surfaces and several damaged internal parts were found.
Three seconds later in the transient, the valve stopped chattering without manual actuation and then closed. After the transient, a leakage test was attempted.
For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage.
The valve partially
:.:.2.2.b. Long Inlet Pipe Configuration (Configuration A). A high ramp rate, low back 1*ressure steam test was performed with the valve mounted on a loop seal configuration
*opened at which p9int the leak test was terminated.
        *            .. nd the loop seal drained. The safety valve opened within .:'.:.3% of the valve design set rjressure and the transient continued for a total time of 122 seconds. The valve chattered during most of the test duration and then closed at a pressure of 2010 psi a.
Valve Inspection Results After the 4000F test, the valve was disassembled and inspected.
                    ~*everal minutes after closure, the valve re-opened at a pressure noted by the loop ciperator of approximately 2150 psi a.                                 The valve chattered during the 10 second duration of the transient and then closed at a pressure just below 2150 psia.
Galled guiding surfaces and several damaged internal parts were found. For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces.
Mter the test, a leak test was performed at an inlet pressure of about 2100 psia. The valve leakage measured was J.54 gpm. The valve was then dissassemb.led and inspec-ted. Galled guiding surfaces and several damaged internal parts were found .
The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage. :.:.2.2.b.
* 3-25
Long Inlet Pipe Configuration (Configuration A). A high ramp rate, low back 1*ressure steam test was performed with the valve mounted on a loop seal configuration
**'' ,.*    ,' ,j,  ,,*,. * *, }'lt*_'.,* __:_,*~-~\;,*1l_ *. _L'.''.:_ '.~*'II *~ ,**
.. nd the loop seal drained. The safety valve opened within .:'.:.3% of the valve design set rjressure and the transient continued for a total time of 122 seconds. The valve chattered during most of the test duration and then closed at a pressure of 2010 psi a.
 
minutes after closure, the valve re-opened at a pressure noted by the loop ciperator of approximately 2150 psi a. The valve chattered during the 10 second duration of the transient and then closed at a pressure just below 2150 psia. Mter the test, a leak test was performed at an inlet pressure of about 2100 psia. The valve leakage measured was J.54 gpm. The valve was then dissassemb.led and ted. Galled guiding surfaces and several damaged internal parts were found . 3-25 **'' ,.* ,' ,j, ,,*,. * *, }'lt*_'.,*
EPRI/CE SAFET1    _VE TEST PROGRAM TABLE 3. 2 . 1. a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION DRESSER 31709NA Valve Descripiion Inlet Piping Configuration        "Au Length, in. I. D., in.
_
Manufacturer        Dresser Industries Type                                                                Nozzle                17            6.813 Spring Loaded Safety Valve Model No.           31709A Serial No.                                                          Venturi                38            6.813 BQ07681 Drawing No.         4CP-2332    Rev 11                              Pipe                    6            6.813 Body Size (inlet/outlet)        6      in./- -in.
*. _L'.''.:_ ,**
Bore Area    4.34  in.2                                          Reducer                  6            6.813/4.897 Orifice Designation        N Loop Sea*!
w I N '-J EPRI/CE SAFET1 _VE TEST PROGRAM TABLE 3. 2 . 1. a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION DRESSER 31709NA Valve Descripiion Manufacturer Type Dresser Industries Model No. Serial No. Drawing No. Spring Loaded Safety Valve 31709A BQ07681 4CP-2332 Rev 11 Body Size (inlet/outlet) 6 Bore Area 4.34 in.2 in./ 8 in. ----Orifice Designation N Design Set Point Pressure 2500 psig Design Bl owdown __ 5 __ -'percent Rated Flow 507918 1 b/hr. Rated Lift 0.588 in. Internals Type: Not Applicable Ring Setting Reference Position The ring setting positions refer to the number of notches relative to the following surfaces:
w I
Upper Ring -top holes in the guide Middle Ring-seat plane Lower Ring -seat plane Inlet Piping Configuration Length, in. Nozzle Venturi Pipe Reducer Loop Sea*! Straight Bends Inlet Flange 17 38 6 6 48 2 Bends 180&deg; 11 Inlet Piping Configuration Length, in. Nozzle Venturi Pipe Reducer Inlet Flange 17 38 6 6 11 "Au I. D., in. 6.813 6.813 6.813 6.813/4.897 4.897 9" radius 4.897 "B" I.D., in. 6 .813 6.813 6.813 6.813/4.897 4.897 w I N \.0 EPRI/CE SAFETY TEST DATA TABLE 3.2. l.b "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE DRESSER 31709NA SAFETY VALVE
Design Set Point Pressure    2500                                    Straight            48            4.897 N                                          psig                            Bends        2 Bends 180&deg;
* CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST NO. TYPE UPPER STEAM -48 *603 STEAM -48 *606 STEAM -48 611 STEAM -48 614 STEAM -48 615 STEAM -48 618 STEAM -48 *620 STEAM -48 623 TRANS -48 625 WATER -48 628 TRANS -48 *630 WATER -48 *1305 STEAM -48 1308 WATER -48 *1311 WATER -48 N/A Not applicable NOTES: VALVE RING INLET SETTINGS PIPING MIDDLE LOWER CONFIG. FLUID +34 -20 A STEAM -60 0 B STEAM -60 0 B STEAM -60 0 B STEAM -40 0 B STEAM -20 0 B STEAM -60 0 B STEAM -20 0 B STEAM -60 0 B STEAM/ WATER -60 . 0 B WATER -20 0 B STEAM/ WATER -20 0 B WATER -20 0 B STEAM -20 0 B WATER -20 0 B WATER IN TANK l AT VALVE INLET PEAK PEAK TANK 1 BACK-PRESS. TEMP. PRESS. RATE FLUID TEMP. PRESS. PRESS. (PSIA) (oF) (PSI/SEC)  
'-J                                                                                                      9" radius Design Bl owdown __5_ _-'percent Inlet Flange            11            4.897 Rated Flow 507918      1b/hr.     Rated Lift 0.588      in.
("F) (PSIA) {PSIA) 2486 (1) 400 STEAM (1) 2680 (3) 2505 (1) 2.9 STEAM ( 1) 2505 174 2503 ( 1 ) 296 STEAM ( 1 ) 2695 195 2530 { 1) 322 . STEAM ( 1 ) 2697 358 2546 (1) 317 STEAM ( 1) 2686 354 2568 (l) 317 STEAM (1) 2639 326 2536 (l) 288 STEAM ( 1 ) 2680 530 2540 ( l ) 317 STEAM (l) 2667 194 2545 (1) 3.0 STEAM ( 1 ) 2545 418 2412 603 3.0 WATER 573 2420 338 2530 (l) 2.7 STEAM (1) 2530 386 2393 625 2.5 WATER 589 2393 336 2530 ( 1 ) 308 STEAM (1) 2652 345 2487 562 1.8 WATER 535 2513 145 2558 415 2.6 WATER 429 2558 100 (1) All tests were initiatP.d at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests, the initiation temperature was the saturation temperature.  
Internals Type:   Not Applicable Inlet Piping Configuration          "B" Length, in.      I.D., in.
(2) The reporteti values are the maximum bending moments on the valve discharqe flange during opening or closinq. (3) Unstable conditions precluded reliable measurement.
Ring Setting Reference Position The ring setting positions refer to the number of                  Nozzle                17            6 .813 notches relative to the following surfaces:
Venturi                38            6.813 Upper Ring - top holes in the guide                      Pipe Middle Ring- seat plane                                                            6          6.813 Lower Ring - seat plane Reducer                  6          6.813/4.897 Inlet Flange          11            4.897
 
EPRI/CE SAFETY TABLE 3.2. l.b TEST DATA "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE DRESSER 31709NA SAFETY VALVE CONDITIONS AT VALVE OPENING                            TRANSIENT CONDITIONS TEST      TEST        VALVE RING          INLET NO.                                                               IN TANK l                    AT VALVE INLET  PEAK  PEAK    INDUCED (2)
TYPE        SETTINGS          PIPING                                                                                                    MAX. STEADY UPPER MIDDLE LOWER      CONFIG.                                                                 TANK 1  BACK-  BENDING MOMENT LIQUID FLOW FLUID    PRESS. TEMP. PRESS. RATE    FLUID    TEMP. PRESS.
(oF)                                            PRESS. OPEN ING/ CLOS ING    (GPM)
(PSIA)              (PSI/SEC)              ("F)  (PSIA)  {PSIA)      (IN. LBS.)
      *~01        STEAM  -48    +34    -20      A      STEAM    2486        (1)        400        STEAM      (1)    2680    (3)    137,500              N/A
      *603        STEAM  -48    -60      0       B      STEAM    2505          (1)        2.9        STEAM      ( 1)  2505      174    CJl ,000
      *606        STEAM                                                                                                                                        N/A
                          -48     -60      0      B      STEAM   2503          (1 )      296        STEAM       (1 )  2695    195      91,000            N/A 611      STEAM   -48     -60      0      B      STEAM   2530          {1)        322 .      STEAM     (1)    2697    358      95,550            N/A 614      STEAM  -48     -40      0      B      STEAM    2546 w                                                                                (1)        317        STEAM      ( 1)  2686    354    100, 100            N/A I
615      STEAM  -48   -20      0      B      STEAM   2568          (l)
N
\.0 317        STEAM      (1)    2639    326    100, 100            N/A 618      STEAM   -48    -60       0       B       STEAM   2536        (l)        288        STEAM     (1 )  2680    530      91,000            N/A
      *620      STEAM   -48    -20       0       B       STEAM   2540        (l )        317        STEAM      (l)    2667    194      95,550            N/A 623      TRANS  -48    -60       0       B       STEAM/   2545        (1)        3.0       STEAM     (1 )  2545    418    100, 100            3801 WATER 625      WATER   -48    -60 . 0       B       WATER   2412        603        3.0         WATER      573    2420    338      91 ,000          2715 628      TRANS  -48    -20      0      B     STEAM/    2530        (l)        2.7        STEAM      (1)   2530    386    81, 900          3305 WATER
    *630        WATER  -48    -20        0      B      WATER    2393        625        2.5        WATER    589    2393    336    100, 100          3735
    *1305        STEAM  -48    -20        0      B      STEAM   2530          (1)       308        STEAM     (1)   2652    345    200,200              N/A 1308        WATER  -48    -20        0      B      WATER    2487        562        1.8        WATER    535    2513    145    473,200            1436
    *1311        WATER  -48    -20        0      B      WATER    2558        415        2.6        WATER    429    2558    100    445,900              (3)
N/A Not applicable NOTES:
(1) All tests were initiatP.d at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests, the initiation temperature was the saturation temperature.
(2) The reporteti values are the maximum bending moments on the valve discharqe flange during opening or closinq.
(3) Unstable conditions precluded reliable measurement.
* The valve was disassembled, inspected, and refurbished as required for representative test performance.
* The valve was disassembled, inspected, and refurbished as required for representative test performance.
INDUCED (2) MAX. STEADY BENDING MOMENT LIQUID FLOW OPEN ING/ CLOS ING (IN. LBS.) (GPM) 137,500 N/A CJl ,000 N/A 91,000 N/A 95,550 N/A 100, 100 N/A 100, 100 N/A 91,000 N/A 95,550 N/A 100, 100 3801 91 ,000 2715 81, 900 3305 100, 100 3735 200,200 N/A 473,200 1436 445,900 (3) w I w I-'
* EPRl/CI:. S         ALVI:. 11:.ST UAIJl1 TABLE 3.2.1.c VALVE TRANSIENT AND LEAKAGE PERFORMANCE DllTA FOR THE DRESSER 31709NA SAFETY VALVE
* PRF-TF5T LEAKAG[ ---* NOMiNAL NOMI NA-L ----VALVE VALVE LEAKAGE TEST TEST MEDIA INLET INLET RATE EPRl/CI:.
* NOMiNAL VOLV~
S ALVI:. 11:.ST UAIJl1 TABLE 3.2.1.c VALVE TRANSIENT AND LEAKAGE PERFORMANCE DllTA FOR THE DRESSER 31709NA SAFETY VALVE VALVE OPENING AND CLOSING TANK I INITIAL OPENING OPENING OPENING PRESS. OPENING "POP" S!MMFR nofJp" .nT V/\L VE % BLOWDDHN VALVE NO.
                          - - -PRF-TF5T                  LEAKAG[
IEi*i?. (GPMj PRESS. PRESS. TIME (PSIA) 201 STEAM STEAf.1 603 STEAM STEAM 606 STEAM STEAM 611 STEAM STEAM 614 STEAM STEAM 615 STEAM STEAM 618 STEAM STEAM 620 STEAM STEAM 623 TRANS STEAM 625 WATER WATER 628 TRANS STEAM 630 WATER WATER 1303 STEAM STEAM l30G WATER WATER 1311 WATER WATER. N/A Not applicable HOTES: 2300 2298 2283 2285 2293 2294 2300 2300 2286 2300 2281 2296 2280 2300 2300 OF) PSIA 660 < 0. l 2486 Sat 0.9 2505 Sat o.o 2503 Sat 0.0 2530 Sat . 0.0 2546 Sat o.o 2568 Sat 0.0 2486 Sat 0.0 2540 Sat 0.0 2545 Sat 0.37 2412 Sat 0. l 2530 Sat 0.36 2393 Sat 0.0 2530 544 0.0 2487 429 o.o 2558 TIME CLOSURE STABILITY PSIA SEC SEC (PSIA) 2489 0.0ll 0.013 2010 20.2 chatter 2505 0.004 0.012 2160 14.2 s table 2509 0.005 0.015 2166 14.0 stable 2538 0.007 0.017 2290 9.0 stable 2551 0.007 0.016 2294 8.8 stable 2575 0.006 0.018 2327 7.5 stable 2486 0.007 0.015 2277 9.5 stable 2540 0.005 0.017 2227 11. 5 stable 2545 0.006 0.015 2052 18.5 stable 2412 0.010 0.035 2108 16. 3 stable. 2530 0.006 0.017 2090 17. 0 stable 2393 0.011 0.037 1950 22.6 stable 2535 0.008 0.023 2301 8.6 stable 2487 0.011 0.059 2398 4.7 stable 2558 <O.Ol (1). (2) (2) chatter (3) (1) Unstable conditions precluded reliable measurement.  
NOMI NA-L- - - -                                  VALVE OPENING AND CLOSING VALVE      VALVE    LEAKAGE                                                            TANK I                                   POST-TEST VALVE LEAKAGE TEST      TEST    MEDIA        INLET                            INITIAL     OPENING     OPENING       OPENING                                                       NOMINAL NOMINAL NO.                                       INLET      RATE      OPENING     "POP"                                     PRESS.
TVD~
:-'~[~~. IEi*i?.                                          S!MMFR       nofJp"       .nT V/\L VE % BLOWDDHN                           VALVE VALVE LEAKAGE (GPMj     PRESS.     PRESS.                                                               VALVE      MEDIA    INLET INLET            RATE (PSIA)        OF)                                            TIME          TIME       CLOSURE PSIA        PSIA        SEC                                                STABILITY              PRESS. TEMP.      (GPM)
SEC          (PSIA) 201     STEAM   STEAf.1                                                                                                                                               (PSIA)    (OF) 2300        660     < 0. l     2486         2489         0.0ll         0.013         2010         20.2         chatter 603                                                                                                                                                            STEAM    2091    646      fl.54 STEAM    STEAM        2298        Sat          0.9    2505        2505         0.004 606      STEAM    STEAM      2283                                                                      0.012         2160         14.2 611 Sat          o.o    2503        2509         0.005 s table        STEAM    2286      Sat      l.O STEAM    STEAM      2285        Sat                                                          0.015         2166         14.0 0.0    2530        2538                                                                stable       STEAM    2200      Sat 614    STEAM    STEAM                                                                    0.007         0.017         2290                                                                 l. l 2293        Sat        . 0.0    2546                                                                  9.0       stable       STEAM 615    STEAM                                                                2551         0.007         0.016                                                           2290      Sat      l.O STEAM        2294        Sat          o.o                                                            2294           8.8       stable 618                                                            2568        2575         0.006                                                               STEAM    2300    Sat      l. 8 w            STEAM    STEAM        2300                                                                      0.018         2327           7.5 I                                              Sat          0.0      2486        2486                                                              stable         STEAM    2285    Sat w    620      STEAM    STEAM                                                                    0.007         0.015         2277                                                                 1.5 I-'                                2300        Sat          0.0    2540                                                                  9.5       stable         STEAM 623      TRANS                                                              2540         0.005                                                                         2285      Sat      2.1 STEAM      2286                                                                      0.017         2227         11. 5 Sat          0.0    2545        2545                                                                stable       STEAM    2300      Sat 0.006         0.015                                                                             l. 7 2052         18.5       stable 625      WATER    WATER                                                                                                                                        STEAM    2285      Sat      0.67 2300        Sat        0.37    2412 628    TRANS                                                                2412          0.010       0.035 STEAM        2281        Sat                                                                        2108         16. 3       stable.
: 0. l    2530        2530         0.006                                                               !~ATER    2300      Sat      o.o 0.017         2090         17. 0 630    WATER                                                                                                                                  stable       WATER      2290    Sat WATER      2296        Sat                                                                                                                                              0.47 0.36    2393         2393          0.011         0.037         1950         22.6       stable       HATER    2300      Sat 1303      STEAM    STEAM                                                                                                                                                                      0.09 2280        Sat        0.0      2530 l30G      WATER                                                              2535         0.008       0.023         2301 WATER      2300        544        0.0                                                                            8.6       stable 2487         2487          0.011                                                               STEAM    1800      Sat      0.66 1311      WATER    WATER.      2300                                                                      0.059         2398           4.7 429        o.o      2558        2558         <O.Ol         (1).
stable      l*IATER    2300      544      0.0 (2)           (2)     chatter (3)     (2)        (2)      (2)      (2)
N/A Not applicable HOTES:
(1) Unstable conditions precluded reliable measurement.
(2) These data were not available (3) The valve opened, chattered for approximately 3 seconds and then stopped chattering for the remainder of the test.
(2) These data were not available (3) The valve opened, chattered for approximately 3 seconds and then stopped chattering for the remainder of the test.
* POST-TEST VALVE LEAKAGE NOMINAL NOMINAL VALVE VALVE LEAKAGE MEDIA INLET INLET RATE PRESS. TEMP. (GPM) (PSIA) (OF) STEAM 2091 646 fl.54 STEAM 2286 Sat l.O STEAM 2200 Sat l. l STEAM 2290 Sat l.O STEAM 2300 Sat l. 8 STEAM 2285 Sat 1.5 STEAM 2285 Sat 2.1 STEAM 2300 Sat l. 7 STEAM 2285 Sat 0.67 2300 Sat o.o WATER 2290 Sat 0.47 HATER 2300 Sat 0.09 STEAM 1800 Sat 0.66 l*IATER 2300 544 0.0 (2) (2) (2) (2) w I w w TEST TEST NO. TYPE .201 STEAM .603 STEAM 606 STEAM 611 STEAM 614 STEAM 615 STEAM 618 STEAM 620 STEAM 623 TRANS 625 WATER 628 TRANS 630 WATER 1305 STEAM 1308 WATER 1311 WATER N/A Not applicable NOTES: EPRI/CE SAFE VE TEST DATA TABLE 3.2.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE DRESSER 31709NA SAFETY VALVE CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ACCUMULATION (1) BASED ON BASED ON BASED BASi:.D uii TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE % RATED % RATED % RATED % RATED % RATED % RATED -nm TED % RATED LIFT STEAM LIFT STEAM LIFT ,_ STEAM LIFT STEAM FLOW FLOW FLOW FLOW (2) (2) (2) (2) (2) (2) (2) (2) N/A N/A N/A N/A N/A N/A N/A N/A 109 125 109 125 109 130 109 131 104 124 105 124 107 130 107 130 98 123 99 124 107 130 107 132 83 117 84 119 (3) (3) (3) (3) 101 123 100 123 108 130 108 130 107 124 107 126 107 130 (3) (3) N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A. N/A N/A N/A N/A N/A N/A 79 114 81 116 (3) (3) (3) (3) N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A NIA (l) During the valve closing cycle. The valve inlet pressure corresponds to stagnation press.ure.  
 
(2) Unstable conditions preclude reliable measurement.  
EPRI/CE SAFE         VE TEST DATA TABLE 3.2.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE DRESSER 31709NA SAFETY VALVE CONDITIONS AT 3% ACCUMULATION (1)                     CONDITIONS AT 6% ACCUMULATION (1)                 LIQUID FLOW MEASUREMENT BASED ON               BASED ON                   BASED O~:                BASi:.D uii TANK PRESSURE       VALVE INLET PRESSURE           TANK PRESSURE                                                           MAX.
TEST    TEST    %RATED       %RATED     %RATED                                             VALVE INLET PRESSURE      TANK CONDITIONS      STEADY .
NO.                                                  %RATED         % RATED       %RATED   -nm TED         %RATED     PRESS. TEMP.
TYPE      LIFT         STEAM     LIFT       STEAM           LIFT ,_       STEAM                                                     LIQUID 1: RATED FLOW                                                          LIFT         STEAM       (PSIA)    (Of)        FLOW     LIFT FLOW                           FLOW                     FLOW                         (GPM) .
    .201    STEAM    (2)             (2)       (2)         (2)           (2)             (2)       (2)           (2)         N/A       N/A         N/A       N/A
    .603    STEAM    N/A             N/A       N/A         N/A           N/A            N/A        N/A          N/A 606    STEAM    109             125                                                                                       N/A        N/A        N/A      N/A 109         125           109             130       109 611    STEAM    104                                                                                          131         N/A        N/A        N/A      N/A 124       105         124           107             130 614    STEAM                                                                                    107           130         N/A        N/A        N/A      N/A 98           123         99       124           107 615                                                                                  130         107           132         N/A        N/A STEAM      83           117         84                                                                                                   N/A      N/A 119           (3)             (3)       (3) 618      STEAM    101                                                                                          (3)         N/A        N/A        N/A      N/A w                                    123       100         123           108           130 I  620      STEAM                                                                                    108           130         N/A        N/A        N/A      N/A w                      107           124       107         126 w                                                                          107           130         (3)           (3)         N/A 623    TRANS      N/A            N/A                                                                                                  N/A         N/A       N/A N/A         N/A           N/A           N/A         N/A           N/A       2372        653      3801    105 625    WATER      N/A           N/A       N/A         N/A           N/A           N/A         N/A           N/A 628    TRANS    N/A                                                                                                    2320          603      2715      38 N/A       N/A         N/A           N/A           N/A         N/A           N/A     2343          647      3304      73 630    WATER    N/A           N/A.       N/A         N/A           N/A           N/A         N/A           N/A     2335          62S      3735      62 1305      STEAM      79           114         81       116           (3)           (3)         (3)           (3) 1308      WATER    N/A                                                                                                      II/A      N/A        N/A      N/A N/A       N/A         N/A           N/A           N/A 1311      WATER                                                                                    N/A           N/A     2429          562      1436      26 N/A           N/A       N/A         N/A           N/A           N/A         N/A           NIA         (2)        (2) .      (2)      (2)
N/A Not applicable NOTES:
(l) During the valve closing cycle. The valve inlet pressure corresponds to stagnation press.ure.
(2) Unstable conditions preclude reliable measurement.
(3) The appropriate measurement conditions were not achieved.
(3) The appropriate measurement conditions were not achieved.
* LIQUID FLOW MEASUREMENT MAX. TANK CONDITIONS STEADY . PRESS. TEMP. LIQUID 1: RATED (PSIA) (Of) FLOW LIFT (GPM) . N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 2372 653 3801 105 2320 603 2715 38 2343 647 3304 73 2335 62S 3735 62 II/A N/A N/A N/A 2429 562 1436 26 (2) (2) . (2) (2)
 
I I I * * !.J CROSL3Y Hl3-L3P-86, JKG (SHl\M INTERNl\LS) 3.3.l Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Crosby HB-BP-86 3K6 (Steam Internals) safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility.
I I ~    I
The valve was tested on both a short (test series 400, configuration E) and a long (test series 500, configuration F) inlet piping configuration.
*       !.J 3.3.l CROSL3Y Hl3-L3P-86, JKG (SHl\M INTERNl\LS)
The following is the list of tables that contain the safety valve information/data for these tests: Table Description Safety Valve Description and Inlet Piping Configuration "As Tested" Test Matrix Valve Transient and Leakage Performance Data Valve Flow Rate Performance Data 3.3.2 Principal Observations Table Number 3. 3. l. a 3. 3. l. b 3. 3. l .c 3. 3. l .d 3.3.2.a. Short Inlet Pipe Configuration (Configuration E). Fourteen tests were performed on the Crosby 3K6 (Steam Internals) safety valve mounted on a short inlet pipe configuration.
Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Crosby HB-BP-86 3K6 (Steam Internals) safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The valve was tested on both a short (test series 400, configuration E) and a long (test series 500, configuration F) inlet piping configuration. The following is the list of tables that contain the safety valve information/data for these tests:
The principal observations for each type of test are as follows: Steam Tests Tests 406 through 411 were high and low ramp rate and high back pressure steam tests. In all of these tests, one set of valve ring positions was maintained which was the manufacturer's recommended ring position.
Table Description                                Table Number Safety Valve Description and Inlet Piping Configuration                                    3. 3. l. a "As Tested" Test Matrix                            3. 3. l. b Valve Transient and Leakage Performance Data        3. 3. l .c Valve Flow Rate Performance Data                    3. 3. l .d 3.3.2 Principal Observations 3.3.2.a. Short Inlet Pipe Configuration (Configuration E). Fourteen tests were performed on the Crosby 3K6 (Steam Internals) safety valve mounted on a short inlet pipe configuration. The principal observations for each type of test are as follows:
With this ring position the valve opened within !3% of the valve design set pressure, achieved a lift position which was 96% of rated lift when the pressure accumulated to 6% above the valve design set pressure and closed with 10.1-10.9%
Steam Tests Tests 406 through 411 were high and low ramp rate and high back pressure steam tests. In all of these tests, one set of valve ring positions was maintained which was the manufacturer's recommended ring position. With this ring position the valve opened within !3% of the valve design set pressure, achieved a lift position which was 96% of rated lift when the pressure accumulated to 6% above the valve design set pressure and closed with 10.1-10.9% blowdown. Following these tests, rinq adjustment tests
blowdown.
* 3-35
Following these tests, rinq adjustment tests 3-35 415 through 425 were performed to decrease blowdown.
 
The final adjustment resulted in decreasing the blowdown to 8.4% with the va*lve performance maining stable. In addition, the valve achieved 99 to 100% of rated lift when the pressure accumulated to 6% above the valve design set pressure.
415 through 425 were performed to decrease blowdown. The final adjustment resulted in decreasing the blowdown to 8.4% with the va*lve performance re-maining stable. In addition, the valve achieved 99 to 100% of rated lift when the pressure accumulated to 6% above the valve design set pressure.
The final ring position was maintained for the non-steam tests. Two other steam tests, nos. 441 and 442 were perfcrmed after the water tests were completed and the valve had been refurbished.
The final ring position was maintained for the non-steam tests.
The of the tests was to re-establish va'lve performance simi"lar to the performance obtained on steam prior to valve refurbishment.
Two other steam tests, nos. 441 and 442 were perfcrmed after the water tests were completed and the valve had been refurbished. The purpo~e of the tests was to re-establish va'lve performance simi"lar to the performance obtained on steam prior to valve refurbishment. lhe r'ing positions of test No. 442 were then used for the initial long ~ipe configuration tests of the Crosby 3K6 safety valve.
lhe r'ing positions of test No. 442 were then used for the initial long configuration tests of the Crosby 3K6 safety valve. Transition Test During the high back pressure, steam-to-water transition test, the valve opened within of the valve design set pressure, had stable performance and closed with 8% blowdown.
Transition Test During the high back pressure, steam-to-water transition test, the valve opened within ~3% of the valve design set pressure, had stable performance 1
1 Water Tests ' ' Three high back pressure water tests were performed at nominal water eratures of 650&deg;F and 550&deg;F. For the 650&deg;F water test, the valve cycled twice. The valve opened at pressures of 2342 and 2278 psia; For the first cycle, the valve had stable performance and closed with 13.0% blowdown.
and closed with 8% blowdown.
Two 550&deg;F water tests were performed.
Water Tests Three high back pressure water tests were performed at nominal water temp-eratures of 650&deg;F and 550&deg;F. For the 650&deg;F water test, the valve cycled twice. The valve opened at pressures of 2342 and 2278 psia; For the first cycle, the valve had stable performance and closed with 13.0% blowdown.
In the first test, no. 435, the valve opened within of the valve design set pressure to a partial lift position.
Two 550&deg;F water tests were performed. In the first test, no. 435, the valve opened within ~3/i. of the valve design set pressure to a partial lift position. The system pressure continued to accumulate while the valve remained in a partial lift position. The test was terminated be-cause the valve did not relieve the pressure in tank 1. In the second 550&deg;F water test performed at similar. conditions, the valve opened and chattered. The test was terminated after the valve was manually opened to stop chattering.
The system pressure continued to accumulate while the valve remained in a partial lift position.
3-36
The test was terminated cause the valve did not relieve the pressure in tank 1. In the second 550&deg;F water test performed at similar. conditions, the valve opened and chattered.
* Valve Inspection Results After each test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected. Galled guid-ing surfac1~s and several *damaged internal parts were found.
The test was terminated after the valve was manually opened to stop chattering.
For all other inspections, the typical wear pattern observed was scratches or marks .011 the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to miminize seat leakage.
3-36 
3.:l.2.b. Long Inlet Pipe Configuration (Configuration F). Six tests were performed on the Crosby HB-BP-86 3K6 (Steam Internals) safety valve mounted on a long inlet pipe co11figuration. Four of the tests were self actuation steam tests performed with a dr<~ined loop seal. The other two tests were manual actuation tests. The principal observations for the self actuation tests are as follows:
' . *
Foi three of four steam tests, the valve opened at a syst~m pressure within .:::_3% of the valve design set pressure. In test No. 506, the valve set point was established on a portable air bench device and the valve subsequently opened at a pressure of 2708 psi a.
* Valve Inspection Results After each test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected.
For the tests performed with ring positions resulting in 15.6 - 15.9% blowdown, valve operation was stable and 99% of rated lift was achieved when the pressure was 6% above the valve design set point. During one test (No. 508) performed with ring positions which had resulted in 10.5% blowdown on the last Crosby 3K6 (St~am Inter-nals) short inlet piping configuration test, the valve opened and chattered. The test was terminated after the valve was manually opened to stop chattering.
Galled ing and several *damaged internal parts were found. For all other inspections, the typical wear pattern observed was scratches or marks .011 the seat surfaces.
Valve Inspection Results After each test which was terminated by manually open_ing the valve to stop chattering, the valve was disass~mbled and inspected. Galled guid-ing surfaces and several damaqed internal parts were found.
The seat surfaces were lapped prior to reassembly and continued testing in order to miminize seat leakage. 3.:l.2.b.
For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage .
Long Inlet Pipe Configuration (Configuration F). Six tests were performed on the Crosby HB-BP-86 3K6 (Steam Internals) safety valve mounted on a long inlet pipe co11figuration.
* 3-37
Four of the tests were self actuation steam tests performed with a loop seal. The other two tests were manual actuation tests. The principal observations for the self actuation tests are as follows: Foi three of four steam tests, the valve opened at a pressure within .:::_3% of the valve design set pressure.
* EPRI/CE SAFE~VE      TEST PROGRAM TABLE 3.3. l .a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 3K6 (STEAM INTERNALS)
In test No. 506, the valve set point was established on a portable air bench device and the valve subsequently opened at a pressure of 2708 psi a. For the tests performed with ring positions resulting in 15.6 -15.9% blowdown, valve operation was stable and 99% of rated lift was achieved when the pressure was 6% above the valve design set point. During one test (No. 508) performed with ring positions which had resulted in 10.5% blowdown on the last Crosby 3K6 nals) short inlet piping configuration test, the valve opened and chattered.
Valve  Descri~tion Inlet  Pi~in9 Configuration ''F" Length, in. I.D., in.
The test was terminated after the valve was manually opened to stop chattering.
Manufacturer      Crosby Valve and Gage Type              Spring Loaded Safety                      Nozzle                    17        6.813 Model No.        HB-BP-86 3K6 Serial No.       None                                      Ventur-i                  38        6.813 Drawing No.      SK-3658-V                                  Pipe                        6        6.813 Body Size (inlet/outlet)      3    in./    6  in.
Valve Inspection Results After each test which was terminated by manually open_ing the valve to stop chattering, the valve was and inspected.
Bore Area l. 841 in.2                                        Reducer                    6        6.813 Orifice Designation      K                                  Loop Seal w    Design Set Point Pressure                                      Straight                54        3. 152 w
Galled ing surfaces and several damaqed internal parts were found. For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces.
I 2485  psig                        Bends                  4-900    6 inches radius
The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage . 3-37
"&deg;  Design Blowdown          percent 5                                      Reducer                    ti        3. 152/2.624 Rated Flow 212,182 lb/hr. Rated Lift 0.382    in.         Inlet Flange                7        2.624 Internals Type:    Steam Ring Setting Reference Position:                            Inlet  Pi~ing  Configuration 11E11 The ring setting position refers to the number of                                  Length, in. I.D., in.
* w I w "&deg; EPRI/CE TEST PROGRAM TABLE 3.3. l .a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 3K6 (STEAM INTERNALS)
notches relative to the bottom of the ring disc.           Nozzle                      17        6.813 Venturi                    38        6.813 Pipe                        6        6.813 Reducer                    10        6. 813/ 2. 624 Pipe                        4        2.624 Inlet Flange                7        2.624
Valve Manufacturer Crosby Valve and Gage Type Spring Loaded Safety Model No. HB-BP-86 3K6 Serial No. None Drawing No. SK-3658-V Body Size (inlet/outlet) 3 in./ 6 in. Bore Area l. 841 in.2 Orifice Designation K Design Set Point Pressure 2485 psig Design Blowdown 5 percent Rated Flow 212,182 lb/hr. Rated Lift 0.382 in. Internals Type: Steam Ring Setting Reference Position:
* 11r1r
The ring setting position refers to the number of notches relative to the bottom of the ring disc. Inlet Configuration
                                                                .""'\~
''F" Length, in. Nozzle 17 Ventur-i 38 Pipe 6 Reducer 6 Loop Seal Straight 54 Bends 4-900 Reducer ti Inlet Flange 7 Inlet Configuration 11E11 Length, in. Nozzle 17 Venturi 38 Pipe 6 Reducer 10 Pipe 4 Inlet Flange 7
TLC'Trnn
* I.D., in. 6.813 6.813 6.813 6.813 3. 152 6 inches radius 3. 152/2.624 2.624 I.D., in. 6.813 6.813 6.813 6. 813/ 2. 624 2.624 2.624 w I ......
                                                                      , :_...)IL l.J Ef'RI/CC SAFE.E T.EST DATA COM3U~Tror:
* TEST TEST NO. TYPE UPPER 406 Steam -55 408 Steam -55 411 Steam -55 415 Steam -35 416 Steam -45 419 Steam -38 422a Steam -38 b -38 c -38
TABLE 3.3.l.b
* 425 Steam -45
[NGIN((RING TEST MATRIX ror:: ... c.
* 428 Trans -45 431 a Water -45 b -45 435 Water -45 *438 Water -45 H/A Not applicable NOTES: VALVE RING INLET SETTINGS PIPING MIDDLE LOWER CONFIG. N/A -14 E N/A -14 E N/A -14 E N/A -14 E N/A -14 E N/A -14 E N/A -14 E N/A -14 E N/A -14 E N/A -14 E N/A -14 E N/A -14 E
CROSBY HB-BP-B6 3K6 (STEAM INTERNALS)
-14 E N/A -14 E tl/A -14 E 11r1r TLC'Trnn , :_...)IL l.J Ef'RI/CC SAFE.E T.EST DATA TABLE 3.3.l.b
CONDITIONS AT VALVE OPENING                                    TRANSIENT CONDITIONS TEST    TEST        VALVE RING          INLET                                IN TANK 1                                          PEAK      PEAK          INDUCED ( 2)    MAX. STEADY NO. TYPE          SETTINGS          PIPING                                                              AT VALVE INLET TANK 1    BACK-         BENDING MOMENT  LIQUID FLOW UPPER MIDDLE LOWER      CONFIG. FLUID            PRESS.           TEMP.     PRESS. RATE    FLU ID    TEMP. PRESS. PRESS. - OPENING/CLOSING          (GPM)
[NGIN[[RING TEST MATRIX ror:: ... c. CROSBY HB-BP-B6 3K6 (STEAM INTERNALS)
( PSIA)          (OF)        (PSI/SEC)              (OF)        (P<;TA)    f P<: ! n \
CONDITIONS AT VALVE OPENING IN TANK 1 AT VALVE INLET FLUID PRESS. TEMP. PRESS. RATE FLU ID TEMP. ( PSIA) (OF) (PSI/SEC) (OF) Steam 2456 {l) 2.7 Steam (1) Steam 2462 (l) 2.5 Ste;im (1) Steam 2502 (l) 286 Steam (l) Steam 2545 (1) 300 Steam ( l) Steam 2487 ( l ) 311 Steam (l) Steam 2510 (1) 271 Steam (l) Steam . 2507 {l) 335 Steam (1) Steam 2417 1.6 Steam (l) Steam (3) (3) Steam ( l ) Steam 2505 (l) 325 Steam (l) Steam/ 2548 ( l ) 2.7 Steam ( l) Water Water 2342 631 l.8 Water 622 Water 2273 l. 6 616 Water 2454 520. l. 7 Water 510 Water 2447 554 2.3 Water 532 TRANSIENT CONDITIONS PEAK PEAK INDUCED ( 2) TANK 1 BACK-BENDING MOMENT PRESS. PRESS. -OPENING/CLOSING (P<;TA) f P<: ! n \ ( LBS.) ' * *'I 2456 662 123,500 2462 !;7J'. 123,500 2683 60(: 114 ,000 2660 860 28,500 2700 705 19,000 2717 700 19,000 2710 690 19,000 2417 .586 (3) (3) 2730 140 14,250 2548 854 2349 .. 5f4 32,300 (4) (4) (3) (3) 24,700 2490 700 19,000 (1) All tests were initiated at a nomir.al pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation temperature.  
                                                                                                                                                      '  * *'I        ( l~L LBS.)
(2) reported values are the maximum induced bending moments on the valve discharge flange during opening or closing. (3) These data were not available.  
406    Steam  -55      N/A    -14        E    Steam            2456              {l)            2.7      Steam      (1)      2456        662            123,500          N/A 408     Steam   -55     N/A    -14        E    Steam             2462            (l)            2.5      Ste;im    (1)      2462        !;7J'.        123,500          N/A 411    Steam   -55      N/A    -14        E    Steam             2502            (l)            286      Steam     (l)      2683        60(:          114 ,000          N/A 415    Steam  -35      N/A    -14        E    Steam            2545            (1)            300      Steam      ( l)    2660        860            28,500          N/A 416    Steam  -45     N/A   -14       E     Steam            2487              (l )          311      Steam      (l)      2700        705            19,000          N/A 419    Steam  -38      N/A   -14       E     Steam            2510              (1)            271      Steam      (l)      2717        700            19,000          N/A 422a    Steam  -38      N/A   -14       E     Steam . 2507                      {l)            335      Steam      (1)      2710        690            19,000          N/A w            b          -38      N/A   -14       E     Steam            2417                            1.6      Steam      (l)      2417      .586                              N/A I
~            c          -38      N/A   -14       E     Steam            (3)                            (3)      Steam      (l )      (3)          (3)                            N/A
......
* 425                                                                                                                                          140 Steam  -45      N/A   -14       E     Steam            2505              (l)            325      Steam      (l)      2730                        14,250          N/A
* 428    Trans  -45      N/A    -14        E    Steam/ 2548                        (l )          2.7      Steam      ( l)    2548        854              (~)           1616 Water 431 a  Water  -45      N/A  -14        E    Water            2342            631            l.8      Water      622      2349      . 5f4            32,300            1370 b            -45      :~/A  -14        E    Water            2273                            l. 6      ~later    616      (4)           (4)                           'I/A 435    Water  -45      N/A  -14        E    Water            2454            520.          l. 7     Water      510      (3)           (3)         24,700            493
        *438    Water  -45      tl/A  -14        E    Water            2447            554            2.3      Water      532      2490        700          19,000            (4)
H/A Not applicable NOTES:
(1) All tests were initiated at a nomir.al pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation temperature.
(2) Th~ reported values are the maximum induced bending moments on the valve discharge flange during opening or closing.
(3) These data were not available.
(4) Unstable conditions precluded reliable measurement.
(4) Unstable conditions precluded reliable measurement.
* The valve was disassembled, inspected, and refurbished as required for representative test performance.
* The valve was disassembled, inspected, and refurbished as required for representative test performance.
* MAX. STEADY LIQUID FLOW (GPM) N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1616 1370 'I/A 493 (4) w I ""'" w
* EPRI/CE SAF.VE TESTDATA TABLE 3.3.l.b (Can't)
* TEST TEST NO. TYPE 441 Steam 442 Steam
                                                              "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE CROSBY HB-BP-86 3K6 (STEAM INTERNALS)
* 506 Steam
CONDITIONS AT VALVE OPENING                              TRANSIENT CONDITIONS TEST   TEST         VALVE RING          INLET                      IN TANK 1                    AT VALVE INLET    PEAK    PEAK    INDUCED (2)    MAX. STEADY NO. TYPE          SETTINGS          PIPING                                                                      TANK 1  BACK-  BENDING MOMENT  LIQUID FLOW UPPER MIDDLE LOWER      CONFIG. FLUID    PRESS. TEMP.      PRESS. RATE    FLUID    TEMP .. PRESS. PRESS. OPEN ING/CLOSING    (GPM)
* 508 Steam 516 Steam
(PSIA)     (OF).      (PSI/SEC)              (Of)      (PSIA)  (PSIA)     (IN. LBS.)
* 517 Steam 503 Manual 512 Manual EPRI/CE SAF.VE TESTDATA TABLE 3.3.l.b (Can't) "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE CROSBY HB-BP-86 3K6 (STEAM INTERNALS)
                                                ~~-------
CONDITIONS AT VALVE OPENING VALVE RING INLET IN TANK 1 AT VALVE INLET SETTINGS PIPING UPPER MIDDLE LOWER CONFIG. FLUID PRESS. TEMP. PRESS. RATE FLUID TEMP .. (PSIA) (OF). (PSI/SEC) (Of)  
441    Steam    -45   N/A       -14       E     Steam     2473       (l )         289         Steam   (l)   . 2700    632      161,500          N/A 442    Steam    -55  N/A      -14       E     Steam     2487       (l)           314         Steam   (l)       2670    626      133,000          N/A
-45 N/A -14 E Steam 2473 ( l ) 289 Steam (l) -55 N/A -14 E Steam 2487 (l) 314 Steam (l) -55 N/A -14 F Steam 2708 (1) 4.1 Steam (l) -55 N/A -14 F Steam 2507 ( l ) 2.6 Steam (l) -115 N/A -14 F Steam 2435 ( 1 ) 2.9 Steam ( l) -115 N/A -14 F Steam 2465 (l) 222 . Steam (l) Actuation.
* 506    Steam    -55   N/A       -14       F     Steam     2708       (1)           4.1       Steam   (l)       2709    455        59,000          N/A
Valve perfonnance data are not applicable.
* 508    Steam    -55   N/A       -14       F     Steam     2507       (l )           2.6       Steam   (l)       2508    515        5,900          N/A 516    Steam    -115 N/A       -14       F     Steam     2435       (1)           2.9       Steam   ( l)     2436    507        56,050          N/A
Actuation.
* 517    Steam    -115  N/A      -14       F     Steam     2465       (l)           222 .       Steam   (l)       2725    582        59,000          N/A w      503    Manual Actuation. Valve perfonnance data are not applicable.
Valve performance data are not applicable.
I 512    Manual Actuation. Valve performance data are not applicable.
TRANSIENT CONDITIONS PEAK PEAK INDUCED (2) TANK 1 BACK-BENDING MOMENT PRESS. PRESS. OPEN I NG/CLOSING (PSIA) (PSIA) (IN. LBS.) . 2700 632 161,500 2670 626 133,000 2709 455 59,000 2508 515 5,900 2436 507 56,050 2725 582 59,000 NOTES: (1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests l'lnd steam/water transition tests the initiation temnE>rature was the saturation temperature.
""'w" NOTES:
(2) The re&#xb5;orted values are the maximum induced bending moments on the valve discharge flange during opening or closing.
(1) All  tests were initiated at a nominal pressure of 2300 PSIA. For steam tests l'lnd steam/water transition tests the initiation temnE>rature was  the saturation temperature.
* The valve was disassembled, inspected, and refurbished as required for representative test perfonnance.
(2) The  re&#xb5;orted values are the maximum induced bending moments on the valve discharge flange during opening or closing.
MAX. STEADY LIQUID FLOW (GPM) N/A N/A N/A N/A N/A N/A w I .;:::, CJ1 ** l:.i'Hl/LI:_
* The  valve was disassembled, inspected, and refurbished as required for representative test perfonnance.
SML I Ui\ 111 VAL'*E TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE CROSBY HB-BP-86-3K6 (STEAM INTERNALS)
 
PRE-TEST VALVE LEAKAGE V d I_ V[. 0 PEN ING AND CL C '.:.: :: :; ----NOMINAL NOMINAL VALVE VALVE LEAKAGE INITIAL OPENING TEST TEST MEDIA INLET INLET RATE OPEi! ING "POP" NO. TYPE PRESS. TEMP. (GPM) PRESS. PRESS. I nr r,., \ 1r...-\ \r:>li'\}
                **                                                                l:.i'Hl/LI:_ SML I                  Ui\ 111 VAL'*E TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE CROSBY HB-BP 3K6 (STEAM INTERNALS)
\l'SlA) ,, .JJ.t'l/ I r J 406 Steam Steam 2315 Sat 0.0 2456 2456 408 Steam Steam 2306 Sat 0.81 2462 2462 411 Steam Steam 2319 Sat 0.58 2502 2505 415 Steam Steam 2310 Sat 0.03 2545 2547 416 Steam Steam 2322 Sat 0.0 2487 2490 419 Steam Steam 2295 Sat 0.0 2510 (2) 422a Steam Steam 2288 Sat 0.0 2507 2511 b 2417 2417 c (5) ( 5) 425 Steam Steam 2285 Sat 0.0 2505 2508 428 Trans Steam 2297 Sat 0.0 2548 2548 431 a Water Steam 2284 Sat . 0.03 2, * .., 2342 b 2278 435 Water Steam 2210 550 8.4 2454 2454 438 Water Steam 2321 Sat 0.0 2447 (3) (l) Valve stability was inferred from the inlet pressure stability.
PRE-TEST VALVE LEAKAGE                                              Vd I_ V[. 0 PEN ING AND CL C'.:.: :: :;                          POST-TEST VALVE cEAKAGE
(2) No measurement was taken. (3) Unstable conditions precluded reliable measurement.
                          ----NOMINAL          NOMINAL                                                                        TANK 1                                      NOM!tlAL NOP.: '*.~L VALVE          VALVE    LEAKAGE INITIAL        OPENING      OPENING        OPENING        PRESS.                                     VALVE VA~,~ LEAKAGE TEST      TEST    MEDIA    INLET        INLET      RATE  OPEi! ING        "POP"        SIMMER        "POP"        AT VALVE    % BLOWDOWN    VALVE      MEDIA  INLET. INL~T              RATE NO.      TYPE            PRESS.        TEMP.      (GPM) PRESS.          PRESS.        TT~ff        T!'-1E      Cl n<;11[1E            STABILITY            PRESS. T;'.HI""'
TANK 1 OPENING OPENING PRESS. SIMMER "POP" AT VALVE % BLOWDOWN T!'-1E Cl n<;11[1E (SEC) (SEC} (PSII\) .008 .009 2250 10. l .009 .006 2243 l 0.3 .009 .006 2228 10.9 .006 .007 (4) (4) .01 .006 2298 8. 1 (2) (2) 2370 5.2 . 011 .006 2408 3.7 2364 5.5 (5) (5) .008 .006 2292 8.4 . 005 .007 2300 8.0 .005 .010 2177 13.0 ( 5) (5) .010 N/A ( 5) (5) (3) NJA (3) (3) (4) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.  
                                                                                                                                                                                        ;.. r.      (GPM)
(5) These data were not available.
I n r r,., \
(6) The valve chattered on closure. POST-TEST VALVE cEAKAGE NOM!tlAL NOP.:
                                  , , .JJ.t'l/  I 1r...-\
VALVE LEAKAGE VALVE MEDIA INLET.
r J            \r:>li'\}        \l'SlA)    (SEC)         (SEC}          (PSII\)                                    (PSIA)    (0:)
RATE STABILITY PRESS. T;'.HI""' (GPM) ;... r. (PSIA) (0:) Flutter (l) Steam 2302 Sat 0.0 Stable Steam 2305 Sat 0. 74 Stable Steam (2) (2; (2) Chatter (6) Steam 2310 Sa't 0.05 Stable Steam 2322 Sat fl.O <;t;ible (1) Steam 2301 Sat 1.2 Flutter Steam 2320 Sat 0.0 Flutter (5) Stable Steam 2300 Sat 0.0 Stable Steam 2296 Sat 0.08 Stable Steam 2278 Sat 0.05 (5) ( 5) Steam 2300 52Z >15 Chatter (2) (2) (2) (2) w I ..,. -....J TEST TEST NO. TYPE 441 Steam Steam 506 Steam 508 Steam 516 Steam 517 Steam 503 Manual 512 Manua 1 ll'I< I/ Lt L VI:. I b I UI\ 11\ .3.1.c (Con't) VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE CROSBY HB-BP-86-3K6 (STEAM INTERNALS)
406      Steam  Steam    2315          Sat        0.0    2456              2456          .008        .009          2250          10. l    Flutter (l) Steam  2302      Sat       0.0 408     Steam   Steam   2306           Sat       0.81   2462               2462         .009        .006          2243          l 0.3    Stable      Steam 2305      Sat       0. 74 411      Steam   Steam   2319          Sat       0.58  2502              2505          .009        .006          2228          10.9      Stable      Steam  (2)      (2;        (2) 415      Steam   Steam   2310          Sat       0.03  2545              2547          .006        .007          (4)          (4)       Chatter (6) Steam 2310      Sa't      0.05 416      Steam  Steam   2322          Sat         0.0   2487              2490          .01          .006          2298          8. 1      Stable      Steam 2322      Sat       fl.O 419      Steam  Steam    2295          Sat        0.0   2510              (2)           (2)         (2)           2370          5.2      <;t;ible (1) Steam  2301      Sat        1.2 422a    Steam  Steam    2288          Sat        0.0    2507              2511          . 011        .006          2408          3.7      Flutter    Steam  2320      Sat        0.0 w            b                                                    2417              2417                                      2364          5.5      Flutter I
DD!::-TEST VALVE LEAVAGE VAL VE OPENING AND CLOSING NOMINAL NOMI NA[ TANK 1 VALVE VALVE LEAKAGE INITIAL OPENING OPENING OPENING PRESS. MEDIA INLET INLET RATE OPENING "POP" SIMMER "POP" AT VALVE % SLOWDOWN PRESS. TEMP. (GPM) PRF<;<;. ppr:-<:<;
CJ1          c                                                    (5)               ( 5)                                     (5)           (5)       (5) 425      Steam  Steam    2285          Sat        0.0    2505              2508          .008        .006           2292          8.4      Stable      Steam 2300      Sat        0.0 428      Trans  Steam    2297          Sat        0.0    2548              2548          . 005       .007           2300         8.0      Stable      Steam 2296      Sat        0.08 431 a    Water  Steam    2284          Sat      . 0.03  2, * ..,
TIME CL0'.:!.!RE (PSIA) (UF) (PSIA) (PSIA} (SEC} (SEC} (PSIA) Steam 2320 Sat 0.0 2473 2476 .011 .008 2407 3.7 Steam ]2238 Sat 0.0 2487 2489 .007 .008 2240 10.5 Steam 2302 Sat 0.0 2708 2708 .007 .006 2330 6.8 Steam 2276 Sat .74 2507 2506 .009 .008 (1) (1) Steam 2270 Sat .05 2435 2435 .0070 .007 2106 15.9 Steam 2285 Sat 0.0 2465 2465 .008 .008 2113 15.6 Actuation.
                                                                    ~"'-
Valve performance data are not applicable.
2342          .005        .010          2177          13.0      Stable      Steam 2278      Sat        0.05 b                                                    2278                                                        ( 5)         (5)       (5) 435      Water  Steam    2210          550        8.4    2454              2454          .010        N/A            ( 5)         (5)      ( 5)       Steam 2300        52Z >15 438      Water  Steam    2321          Sat        0.0    2447              (3)          (3)          NJA            (3)           (3)      Chatter    (2)    (2)      (2) (2)
Actuation.
(l)   Valve stability was inferred from the inlet pressure stability.
Valve performance data are not applicable . (1) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.  
(2)   No measurement was taken.
(3)   Unstable conditions precluded reliable measurement.
(4)   The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.
(5)   These data were not available.
(6)   The valve chattered on closure.
 
ll'I< I/ Lt  ~/\I        L VI:. I b I UI\ 11\
                                                                                                    .3.1.c (Con't)
VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE CROSBY HB-BP 3K6 (STEAM INTERNALS)
DD!::-TEST VALVE LEAVAGE                                        VAL VE OPENING AND CLOSING                                  POST-TEST VALVE LEAKAGE NOMINAL NOMI NA[                                                                        TANK 1                                NOMINAL NOMINAL VALVE    VALVE LEAKAGE    INITIAL        OPENING          OPENING        OPENING        PRESS.                                VALVE VALVE LEAKAGE TEST    TEST    MEDIA      INLET  INLET    RATE    OPENING          "POP"          SIMMER          "POP"      AT VALVE % SLOWDOWN    VALVE    MEDIA  INLET INLET        RATE NO. TYPE              PRESS. TEMP.   (GPM)    PRF<;<;.        ppr:-<:<;        T!~E              TIME    CL0'.:!.!RE        STABILITY          PRESS. TEMP.    (GPM)
(PSIA)  (UF)              (PSIA)          (PSIA}          (SEC}            (SEC}      (PSIA)                                (PSIA)  (OF) 441    Steam    Steam    2320    Sat    0.0      2473              2476            .011          .008        2407        3.7    flutter    Steam  2325    Sat    0.0
        ~~2    Steam    Steam    ]2238    Sat    0.0      2487              2489            .007          .008        2240        10.5  stable      Steam 2314    Sat   0.24 506    Steam    Steam    2302    Sat    0.0      2708              2708            .007          .006        2330        6.8    flutter    Steam 2300    Sat   0.0 508    Steam    Steam    2276    Sat    .74      2507              2506            .009            .008       (1)        (1)    chatter (2) Steam  1897    Sat    .6 516    Steam    Steam     2270    Sat     .05      2435              2435            .0070          .007       2106      15.9    stable      Steam  2255    Sat    .02 517    Steam    Steam     2285    Sat   0.0      2465              2465            .008            .008       2113      15.6    stable      Steam 2309    Sat   0.0 503    Manual  Actuation. Valve performance data are not applicable.
w I    512    Manua 1 Actuation. Valve performance data are not applicable .
-....J (1) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.
(2) The valve chattered on closure.
(2) The valve chattered on closure.
* POST-TEST VALVE LEAKAGE NOMINAL NOMINAL VALVE VALVE LEAKAGE VALVE MEDIA INLET INLET RATE STABILITY PRESS. TEMP. (GPM) (PSIA) (OF) flutter Steam 2325 Sat 0.0 stable Steam 2314 Sat 0.24 flutter Steam 2300 Sat 0.0 chatter (2) Steam 1897 Sat .6 stable Steam 2255 Sat .02 stable Steam 2309 Sat 0.0 EPRI/CE LVE TEST DATA TABLE 3.3. l.d VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86-3K6 (STEAM INTERNALS)
 
CONDITIONS AT 3% ACCUMULATION ( 1) CONDITIONS AT 6% ACCUMULATION ( 1) s;;sEJ ot: BASED LJN ___ --... BASED-ON _____ -* BASED ON TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE TEST TEST % RATED % RATED % RATED % RATED %-RATED % RATED % RATED % RATED NO. TYPE LIFT STEAM LIFT STEAM LIFT STEAM LIFT STEAM FLOW FLOW FLOW FLOW 406 Steam N/A N/A N/A N/A N/A M/A N/A N/A 408 Steam N/A N/A N/A N/A N/A N/A N/A N/A 411 Steam 96 122 g5 122 96 128 96 129 415 Steam 101 118 102 121 1')4 125 104 127 416 Steam 109 120 109 122 110 126 110 127 419 Steam (2) 117 (2) 119 (2) 123 (2) 124 422<! Steam 99 120 99 120 99 126 99 126 b NA NA NA NA NA NA NA NA w I NA NA NA NA NA NA NA NA 4':> c l.O 425 99 120 99 121 99 126 99 126 Steam 428 Trans NA NA NA NA NA NA NA NA 43la Water NA NA NA NA NA NA NA NA b NA NA NA NA NA NA NA NA 435 Water NA NA NA NA NA NA NA NA 438 Water NA NA NA NA NA -NA NA NA N/A Not Applicable NOTES: (1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.  
EPRI/CE             LVE TEST DATA TABLE 3.3. l.d VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86-3K6 (STEAM INTERNALS)
(2) No measurtment 11as taken. (3) Unstable conditions precluded reliable measurement.
CONDITIONS AT 3% ACCUMULATION ( 1)                       CONDITIONS AT 6% ACCUMULATION ( 1)
LIQLJ.IO FLOW MAX. TANK CONDITIONS STEADY PRESS. TEMP. LI QU ![l % RATED (PSIA) (Of) FLOW LIFT (GPM) N:. NA NA NA NA NA NA '" *( .... NA NA NA Nil. NA NA NA NA NA NA NA NA NA NA NA NA NA NA 'til NA NA NA 'IA NA NA NA NA NA NA NA 2430 648 1616 78 2284 630 1370 57 NA NA NA 'lA 2575 526 493 6 ( 3) ( 3) ( 3) ( 3)
BASED LJN ___ --                                                              LIQLJ.IO FLOW  MEASUREME~H s;;sEJ ot:                                         ... BASED-ON _____ -*
TEST TEST NO. TYPE 441 Steam 442 Steam 506 Steam 508 Steam 516 Steam 517 Steam 503 Manual w 512 Manual I tJ1 ...... N/A Not Applicable NOTES: EPR!/CE
TANK PRESSURE                                                                        BASED ON                                 MAX.
* VE TEST DATA TABLE 3.3.1.d (Can't) VALVE FLOW RATE PERFORMANCE DATA FOR THE CORSBY HB-BP-86 3K6 (STEAM INTERNALS)
TEST                                    VALVE INLET PRESSURE             TANK PRESSURE         VALVE INLET PRESSURE TEST     % RATED       % RATED     % RATED     % RATED       %- RATED                                       TANK CONDITIONS          STEADY NO. TYPE      LIFT            STEAM                                              % RATED     % RATED     % RATED PRESS.      TEMP.         LI QU ![l    % RATED LIFT         STEAM           LIFT         STEAM       LIFT       STEAM FLOW                   FLOW                                                          (PSIA)    (Of)          FLOW           LIFT FLOW                     FLOW                             (GPM) 406   Steam       N/A               N/A     N/A           N/A           N/A           M/A       N/A           N/A   N:.          NA 408   Steam       N/A                                                                                                                           NA          NA N/A     N/A           N/A           N/A           N/A       N/A           N/A   NA          NA          NA          '"....
CONDITIONS AT 3% ACCUMULATION ( 1) CONDITIONS AT 6% ACCUMULATION ( 1) BASED ON BASED ON BASED ON BASED ON TA"NK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE % RATED % RATED % RATED % RATED % RATED % RATED TRATrn xm-LIFT STEAM LIFT STEAM LIFT STEAM LIFT STEAM FLOW FLOW FLOW FLOW 98 123 98 120 99 127 98 126 98 121 g9 125 99 127 (2) (2) N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 99 103 99 104 99 109 99 103 Actuation.
411   Steam       96             122     g5           122
                                                                                                                                                                          *(
96               128         96           129   NA          NA          NA          Nil.
415   Steam     101               118   102             121         1')4             125       104             127   NA          NA 416     Steam     109                                                                                                                             NA          NA 120   109             122         110               126       110             127   NA          NA          NA          NA 419     Steam     (2)               117     (2)           119           (2)             123       (2)             124   NA          NA          NA          ~iA 422<! Steam     99                 120   99             120           99             126       99               126   NA           NA         NA           'til w            b            NA               NA     NA           NA I
NA             NA       NA               NA   NA           NA         NA           'IA 4':>         c           NA                NA      NA            NA l.O                                                                               NA              NA        NA              NA    NA          NA        NA          ~A 425     Steam    99               120     99           121             99             126       99             126   NA          NA          NA          NA 428     Trans     NA               NA     NA           NA             NA             NA       NA             NA   2430        648      1616          78 43la   Water     NA               NA     NA           NA             NA             NA       NA             NA   2284        630      1370          57 b             NA                NA     NA           NA             NA               NA       NA             NA   NA           NA          NA          'lA 435   Water     NA               NA     NA           NA             NA               NA       NA             NA   2575        526          493        6 438   Water     NA               NA     NA           NA             NA             -NA         NA             NA   ( 3)        ( 3)        ( 3)        ( 3)
N/A Not Applicable NOTES:
(1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.
(2) No measurtment 11as taken.
(3) Unstable conditions precluded reliable measurement.
 
EPR!/CE
* VE TEST DATA TABLE 3.3.1.d (Can't)
VALVE FLOW RATE PERFORMANCE DATA FOR THE CORSBY HB-BP-86 3K6 (STEAM INTERNALS)
CONDITIONS AT 3% ACCUMULATION ( 1)
CONDITIONS AT 6% ACCUMULATION ( 1)
BASED ON               BASED ON                                                                   LIQUID FLOW MEASUREMENT TA"NK PRESSURE                                            BASED ON                 BASED ON TEST    TEST                            VALVE INLET PRESSURE             TANK PRESSURE                                                 MAX.
                              % RATED       % RATED   % RATED     % RATED                                 VALVE INLET PRESSURE TANK CONDITIONS NO. TYPE      LIFT                                                  % RATED     % RATED TRATrn         xm-                       STEADY STEAM     LIFT         STEAM             LIFT                                     PRESS.  -TEMP. LIQUID        ~    : ! ~rn FLOW                                                  STEAM     LIFT       STEAM (PSIA)    (Of)
FLOW                           FLOW                                           FLOW               ~~T FLOW                       (GPM) 441      Steam      98             123     98             120           99 442      Steam                                                                          127       98         126 98             121     g9             125                                                         N/A      N/A    N/A        t~_*  .!
506                                                                      99           127         (2)
Steam      N/A            N/A                                                                          (2)     N/A      N/A    N/A N/A            N/A           N/A                                                                        h .!
508      Steam      N/A                                                                 N/A         N/A         N/A     N/A N/A     N/A             N/A                                                                   N/A     N/A       t~    ..:,
516                                                                        N/A           N/A         N/A         N/A Steam      N/A             N/A     N/A                                                                         N/A       N/A     N/A       ,.~-. ~
N/A           N/A           N/A 517      Steam      99                                                                             N/A          N/A    N/A      N/A 103     99             104           99                                                               N/A      I
                                                                                                                                                                  \  -*
109       99         103     N/A 503      Manual Actuation.                                                                                                       N/A    N/A        \      ~
Valve performance data are not applicable.
Valve performance data are not applicable.
Actuation.
w          512      Manual Actuation.
Valve perfonnance data are not applicable.  
I                                      Valve perfonnance data are not applicable.
(1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.  
tJ1 N/A Not Applicable NOTES:
(2) The appropriate measurement conditions were not achieved.
(1)   During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.
* LIQUID FLOW MEASUREMENT MAX. TANK CONDITIONS STEADY PRESS. -TEMP. LIQUID : ! (PSIA) (Of) FLOW (GPM) N/A N/A N/A
(2)   The appropriate measurement conditions were not achieved.
.! N/A N/A N/A h .! N/A N/A N/A ..:, N/A N/A N/A N/A N/A N/A I * \ -N/A N/A N/A \ 
* 3.4      CROSBY HB-BP-86, 3K6 (LOOP SEAL INTERNALS)
..
: 3. 4 .. l  Valve Description and Inlet Piping Configuration Data, "As Tested"Test Matrix and Valve Performance Data.
* 3.4 CROSBY HB-BP-86, 3K6 (LOOP SEAL INTERNALS)
Tests were performed on the Crosby HB-BP-86 3K6. (Loop Seal Internals) safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The v~lve model was tested on both a short (test series 400, configuration E) and a long (test series 500, configuration F) inlet piping configuration. The following is the list of tables that contain the safety valve informdtion/data for these tests:
* 3. 4 .. l Valve Description and Inlet Piping Configuration Data, "As Tested"Test Matrix and Valve Performance Data. Tests were performed on the Crosby HB-BP-86 3K6. (Loop Seal Internals) safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility.
Table Description                                 Table Number Safety Valve Description and Inle.t Piping Configuration                                     3. 4. l. a "As Tested" Test Matrix                             3 .4. l. b Valve Transient and leakage Performance Data         3. 4. l. c Valve Flow Rate Performance Data                    3. 4. l. d 3.4.2       Principal Observations 3.4.2.a.         Short .Inlet Pipe Configuration (Configuration E). One steam test was performed on the Crosby HB-BP-86 3K6 (Loop Seal Internals) safety valve mounted on a short inlet pipe configuration (test No. 403). The test was a low ramp rate, high back pressure steam test with a drained loop seal.           Prior to this test, higher than typically measured seat leakage was observed. The valve then opened at a reduced pressure pi-ior to activation of the data acquisition system. The valve behavior was stable and the valve closed with a blowdown of 10.lS. After the test, the valve was disassembl1~d and inspected. Scratches and marks were observed on the valve seats. The seats were replaced with steam internal seats.
The model was tested on both a short (test series 400, configuration E) and a long (test series 500, configuration F) inlet piping configuration.
3.4.2.b. !ong lnl~t P_ipe Conf~_~tion (Configuration F). A total of seven tests 1-1as performed with the valve mounted on a long inlet configuration. Six of the tests were performed using the final ring positions established during the long inlet pipe configuration Crosby 3K6 (Steam Internals) 500 series tests. The last test was performed with the rings adjusted to reduce blowdown. The principal obser-
The following is the list of tables that contain the safety valve informdtion/data for these tests: Table Description Safety Valve Description and Inle.t Piping Configuration "As Tested" Test Matrix Valve Transient and leakage Performance Data Valve Flow Rate Performance Data Table Number 3. 4. l. a 3 .4. l. b 3. 4. l. c 3. 4. l. d 3.4.2 Principal Observations 3.4.2.a. Short .Inlet Pipe Configuration (Configuration E). One steam test was performed on the Crosby HB-BP-86 3K6 (Loop Seal Internals) safety valve mounted on a short inlet pipe configuration (test No. 403). The test was a low ramp rate, high back pressure steam test with a drained loop seal. typically measured seat leakage was observed.
* vat.ions for these tests are as follows~
Prior to this test, higher than The valve then opened at a reduced pressure pi-ior to activation of the data acquisition system. The valve behavior was stable and the valve closed with a blowdown of 10.lS. After the test, the valve was and inspected.
3-53
Scratches and marks were observed on the valve seats. The seats were replaced with steam internal seats. 3.4.2.b. !ong P_ipe (Configuration F). A total of seven tests 1-1as performed with the valve mounted on a long inlet configuration.
 
Six of the tests were performed using the final ring positions established during the long inlet pipe configuration Crosby 3K6 (Steam Internals) 500 series tests. The last test *was performed with the rings adjusted to reduce blowdown.
Steam Tests Two high back pressure, drained loop seal steam tests were performed. For both tests, the valve opened within ~3% of the valve design set pressure and had stable behavior. When the pressure accumulated to 6% above the valve design set pressure, the valve achieved rated lift. Valve blowdown varied from 15. 7 to 20.1% depending on the ring positions.
vat.ions for these tests are as The principal obser-3-53 Steam Tests Two high back pressure, drained loop seal steam tests were performed.
Loop Seal-Steam Tests Four loop seal-steam tests were performed at test initiation ramp rates of 3.4-220 psi/sec. For these tests, valve lift initiation occurred at pres-sures ranging from 2536 *psia to 2637 psia. The valve fluttered and/or chattered at partial lift positions during three of the loop seal discharges and was stable during the fourth, then popped open on steam at pressures from 2531 psia to 2708 psia. Valve behavior was stable on steam and the valve achieved rated lift when the pressure was 6%. above the valve design set pressure. The valve closed with 17.7 to 19.9% blowdown.
For both tests, the valve opened within of the valve design set pressure and had stable behavior.
While the loop seal was being discharged during loop seal tests, the valve fluttered and/or chattered through partial lift positions at frequences of approximately 170-260 Hz. The valve oscillations during the water dis-charge caused water-hammer type pressure oscillations in the valve inlet piping. Pressure oscill:itions measured in the pressure transducers immediately upstream of the valve inlet indicated pn~ssures ranging from O psia to a pressure which over-ranged the transducer at 3400-3600 psia.
When the pressure accumulated to 6% above the valve design set pressure, the valve achieved rated lift. Valve blowdown varied from 15. 7 to 20.1% depending on the ring positions.
These pressure oscillations were not observed in Tank 1.
Loop Seal-Steam Tests ' ' Four loop seal-steam tests were performed at test initiation ramp rates of 3.4-220 psi/sec. For these tests, valve lift initiation occurred at sures ranging from 2536 *psia to 2637 psia. The valve fluttered and/or chattered at partial lift positions during three of the loop seal discharges and was stable during the fourth, then popped open on steam at pressures from 2531 psia to 2708 psia. Valve behavior was stable on steam and the valve achieved rated lift when the pressure was 6%. above the valve design set pressure.
Transition Test One loop seal-st2am-to-water transition test was performed. For this test, the valve initially opened and fully opened within ~3% of the valve design set pressure and exhibited partial lift flutter and/or chatter during the 3-54
The valve closed with 17.7 to 19.9% blowdown.
 
While the loop seal was being discharged during loop seal tests, the valve fluttered and/or chattered through partial lift positions at frequences of approximately 170-260 Hz. The valve oscillations during the water charge caused water-hammer type pressure oscillations in the valve inlet piping. Pressure oscill:itions measured in the pressure transducers immediately upstream of the valve inlet indicated ranging from O psia to a pressure which over-ranged the transducer at 3400-3600 psia. These pressure oscillations were not observed in Tank 1. Transition Test One loop seal-st2am-to-water transition test was performed.
10011 seal discharge. The val.ve popped open on steam and was stable. When the transition from steam-to-water occurred, the valve began to fl11tter and subsequently chatter. The test was terminated after the valve was manually opened to stop chattering.
For this test, the valve initially opened and fully opened within of the valve design set pressure and exhibited partial lift flutter and/or chatter during the 3-54 * * 
The pressure oscillations description in the Loop Seal-Steam Tests section also applies to the transition test.
' ' 10011 seal discharge.
Valve Inspection Results After each test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected. In each case, galled guiding surfaces and damaged internal parts were found.
The val.ve popped open on steam and was stable. When the transition from steam-to-water occurred, the valve began to fl11tter and subsequently chatter. The test was terminated after the valve was manually opened to stop chattering.
Damaged parts were either refurbished or replaced prior to continued testing.
The pressure oscillations description in the Loop Seal-Steam Tests section also applies to the transition test. Valve Inspection Results After each test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected.
For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimi~e seat leakage.
In each case, galled guiding surfaces and damaged internal parts were found. Damaged parts were either refurbished or replaced prior to continued testing. For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces.
3-55
The seat surfaces were lapped prior to reassembly and continued testing in order to seat leakage. 3-55 w I CJ1 '-.I EPRI/CE SAF LVE TEST PROGRAM TABLE 3.4.1.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 3K6 (LOOP SEAL INTERrJALS)
 
Valve Description Manufacturer Type Model No. Serial No. Drawing No. Crosby Valve and Gage Spring Loaded Safety HB-BP-86 3K6 None SK-3658-V Body Si?e (inlet/outlet) 3 Bore Area 1 . 841 in. 2 in./ Orifice Designation K Design Set Point Pressure 2485 psig Design Bl owdown 5 percent ----6 in. Rated Flow 2 1 2 ,1 82 lb/hr. Rated Lift 0*382 in. Internals Type: Loop Seal Ring Setting Reference Position:
EPRI/CE SAF       LVE TEST PROGRAM TABLE 3.4.1.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 3K6 (LOOP SEAL INTERrJALS)
The reported measurements are relative to the bottom of the disc ring. Inlet Piping Configuration "F" Length, in. Nozzle 17 Venturi 38 Pipe 6 Reducer 6 Loop Seal Straight 54 Bends 4-90&deg; Reducer 4 Inlet Flange 7 Inlet Piping Configuration "E" Length, in. Nozzle 17 Venturi 38 Pipe 6 Reducer 10 Pipe 4 Inlet Flange 7 I.D., in. 6.813 6.813 6.813 6.813/3.152
Valve Description Inlet Piping Configuration "F" Length, in. I.D.,  in.
: 3. 152 6 inches
Manufacturer      Crosby Valve and Gage Type              Spring Loaded Safety                       Nozzle                    17        6.813 Model No.          HB-BP-86 3K6 Serial No.        None                                       Venturi                  38        6.813 Drawing No.        SK-3658-V                                   Pipe                      6        6.813 Body Si?e (inlet/outlet)       3     in./    6  in.        Reducer Bore Area 1. 841 in. 2                                                                   6        6.813/3.152 Orifice Designation         K                                 Loop Seal w                                                                    Straight              54        3. 152 I
: 3. 152/2.624 2.624 I.D., in. 6.813 6.813 6.813 6.813/2.624 2.624 2.624 w , I (.TT \.0 Tt'<:'T  
Design Set Point Pressure       2485 psig                         Bends                          6 inches CJ1
'.'r:_ ".: NO. TYPE SETTINGS PIP'.NG UPPER MIDDLE LOWER CONFIG. *403 STEAM -55 N/A -14 E *525 LS -115 N/A -14 F 526 LS -115 N/A -14 F 529 LS -115 N/A -14 F *532 LS ,-115 N/A -14 F TRANS 535 STEAM -115 N/A -14 F 536 LS -115 N/A -14 F 537 STEAM -95 N/A -14 F "" (" .,.. ...............  
'-.I                                                                                          4-90&deg;              radi~;,
'""'" M..J l*LJ I LU EPRI/CE TEST DATA TABLE 3.4.1.b TEST MATRIX FOR THE CROSBY HB-BP-3K6 (LOOP SEAL INTERNALS)
Design Bl owdown
CONDITIONS AT VALVE OPENING IN TANK 1 AT VALVE INLET FLUID PRESS. TEMP. PRESS. RATE FLU ID TEMP. (PSIA) (OF) (PSI/SEC) (OF) STEAM ( 3) (1) (3) STEAM (1) STEAM 2536 (l) 3.4 WATER 110 STEAM 2608 (1) 220 WATER 94 STEAM 2602 (1) 13.3 WATER 86 STEAM/ 2572 (1) 3.3 WATER 360 WATER STEAM 2530 (l) 85.7 STEAM ( l ) STEAM 2637 ( 1 ) 43.6 WATER 98 STEAM 2500 ( l ) 267 STEAM (1) TRANSIENT CONDITIONS PEAK PEAK INDUCED (2) MAX. STEADY TANK 1 BACK-BENDING MOMENT LIQUID FLOW PRESS. PRESS. OPENING/CLOSING (GPM) (PS!/\) (PSIA) (IN. LBS.) (3) 696 142,500 N/A 2558 471 70,800 N/A 2708 513 147,500 N/A 2638 480 64,900 N/A 2573 615 59,000 (4) 2650 541 59,000 N/A 2677 507 59,000 N/A 2713 557 64,900 N/A N/A Not applicable NOTES: (l ) (2) (3) (4) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation temperature.
                      - -percent                                Reducer                    4        3. 152/2.624 Rated Flow 212 ,1 82 lb/hr. Rated Lift   0* 382 in.
The reported values are the maximum induced bending moments on the valve discharge flange during opening or closing. The valve opened at a reduced pressure prior to data acquisition activation.
Inlet Flange              7        2.624 Internals Type:   Loop Seal Ring Setting Reference Position:                               Inlet Piping Configuration "E" The reported measurements are relative to                                     Length, in. I.D., in.
Unstable conditions precluded reliable measurement.
the bottom of the disc ring.
* The valve was disassembled, inspected, and refurbished as requ_ired.
Nozzle                     17         6.813 Venturi                   38         6.813 Pipe                       6        6.813 Reducer                   10        6.813/2.624 Pipe                        4         2.624 Inlet Flange               7         2.624
for representative test performance.
 
w I en ,__. VE TCSI DATA
EPRI/CE  SA~VE        TEST DATA TABLE 3.4.1.b
* TABLE 3.4.1.c VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA rnP CROSBY HB-BP-86 3K6 (LOOP SEAL INTERNALS)
                                                                    ""M..J .,..l *...............
PRE-TEST VALVE LEAKAGE VALVE OPENING AND CLOSING POST-TEST VALVE LEAKAGE NOMINAL NOMINAL TEST TEST MEDIA NO. TYPE 403 STEAM STEAM 525 LS WATER 526 LS WATER 529 LS WATER 532 LS
("
* WATER TRANS 535 STEAM STEAM 536 LS WATER 537 STEAM STEAM N/A Not Applicable NOTES: VALVE VALVE LEAKAGE INLET INLET RATE PRESS. TEMP. (GPM) (PSIA (OF 2315 Sat 0.7 2296 84 o.o 2278 94 u.u 2301 88 0.0 2309 BO o.o 2287 Sat .26 2303 98 0.0 2300 Sat 0.0 TllNK I INITIAL OPENING OPENING OPENING PRESS. OPENING "POP" SIMMER "POP" AT VALVE PRESS. PRESS. TIME TIME CLOSURE PSIA PSIA SEC SEC (PSIA) (l) (l) (l) (l) 2250 2536 2531 12 .0139 2032 2608 2708 .894 .090 2031 2604 2635 l .990 .007 2048 2572 2568 .402 .013 (2) 2530 2530 .008 .006 2000 2637 2676 1. 387 .008 2006 2500 2500 .009 . 007 2109 (1) The valve opened at a reduced pressure prior to data acquisition activation.
L J I LU
(2) Unstable conditions precluded reliable measurement.
                                                                                                  '""'" COM6USii0~ fNblN~tRING    TEST MATRIX FOR THE CROSBY HB-BP-3K6 (LOOP SEAL INTERNALS)
(3) The valve fluttered and/or chattered during loop seal discharge.
CONDITIONS AT VALVE OPENING                              TRANSIENT CONDITIONS Tt:"~T    Tt'<:'T       \'.~.L '.'r:_ ".: ~::
The valve stabilized on steam. (4) Data available after valve opening indicated stable performance.  
IN TANK 1                      AT VALVE INLET PEAK      PEAK    INDUCED (2)    MAX. STEADY NO. TYPE           SETTINGS               PIP'.NG                                                                                       TANK 1    BACK-  BENDING MOMENT  LIQUID FLOW UPPER MIDDLE LOWER             CONFIG. FLUID                PRESS.                TEMP.      PRESS. RATE      FLU ID  TEMP. PRESS. PRESS. OPENING/CLOSING      (GPM)
(PSIA)                (OF)        (PSI/SEC)                (OF)    (PS!/\)  (PSIA)      (IN. LBS.)
      *403 STEAM        -55        N/A           -14     E  STEAM                     ( 3)              (1)            (3)        STEAM      (1)    (3)      696      142,500          N/A
      *525    LS       -115       N/A             -14     F   STEAM                   2536                (l)          3.4        WATER      110  2558      471        70,800          N/A 526  LS      -115        N/A             -14     F   STEAM                    2608                (1)        220          WATER      94  2708      513      147,500          N/A 529  LS      -115        N/A            -14    F  STEAM                    2602                (1)          13.3        WATER      86  2638      480        64,900          N/A
      *532    LS      ,-115      N/A            -14    F  STEAM/                   2572                (1)          3.3        WATER      360  2573      615        59,000          (4)
TRANS                                            WATER 535 STEAM -115            N/A            -14    F    STEAM                    2530                (l)         85.7        STEAM      (l ) 2650      541        59,000          N/A 536 LS        -115        N/A            -14    F    STEAM                   2637                (1)         43.6        WATER      98  2677      507        59,000          N/A w      537 STEAM -95              N/A            -14    F    STEAM                   2500                (l )       267          STEAM     (1)   2713      557        64,900          N/A
, I
(.TT
\.0 N/A Not applicable NOTES:
(l ) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation temperature.
(2) The reported values are the maximum induced bending moments on the valve discharge flange during opening or closing.
(3) The valve opened at a reduced pressure prior to data acquisition activation.
(4) Unstable conditions precluded reliable measurement.
* The valve was disassembled, inspected, and refurbished as requ_ired. for representative test performance.
 
TABLE VE TCSI DATA 3.4.1.c VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA rnP CROSBY HB-BP-86 3K6 (LOOP SEAL INTERNALS)
TH~
PRE-TEST VALVE LEAKAGE                                  VALVE OPENING AND CLOSING NOMINAL NOMINAL                                                                                                  POST-TEST VALVE LEAKAGE VALVE    VALVE  LEAKAGE                                                  TllNK I                                    NIJM!rlAL NOM lNAL INITIAL      OPENING  OPENING TEST NO.
TEST    MEDIA    INLET    INLET    RATE    OPENING        "POP"    SIMMER OPENING "POP" PRESS.
AT VALVE % BLOWDOWN VALVE VALVE LEAY-AGE      i TYPE              PRESS. TEMP.    (GPM)                                                                           VALVE      MEDIA  INLET INLET        RATE .
I I
PRESS.        PRESS. TIME          TIME  CLOSURE                                                              I (PSIA    (OF                  PSIA                                                              STABILITY              PRESS. TEMP.      (GPM)
PSIA      SEC            SEC      (PSIA)                                   (PSIA)    (OF) 403    STEAM  STEAM      2315    Sat      0.7        (l)          (l)      (l)            (l)    2250      10. l  stable (4)    STEAM    2320      Sat    3.8 525    LS      WATER      2296  84        o.o      2536        2531      12            .0139    2032                stable (3) STEAM 526    LS      WATER                                                                                            18.8                          2298      Sat    0.0 2278  94        u.u      2608        2708          .894      .090 529    LS                                                                                            2031        18.9    stable (3) . STEAM    2307      Sat    0.0 WATER      2301  88        0.0      2604          2635      l .990      .007      2048        17. 7  stable (3) STEAM 532    LS
* WATER      2309  BO        o.o      2572          2568 2300      Sat    o.o TRANS                                                                     .402      .013        (2)        (2)  chatter (3)(5)WATER     2296      305    0.0 535    STEAM   STEAM       2287  Sat        .26 w                                                            2530          2530        .008      .006      2000        20. 1 I
536    LS      WATER                                                                                                        stable    STEAM    2300      Sat   o.o en
,__.                             2303    98        0.0     2637          2676      1. 387 537                                                                                        .008      2006        19. 9    stable    STEAM    2302 STEAM  STEAM      2300   Sat       0.0                                                                                                             Sat      .34 2500          2500        .009      . 007      2109        15.7      stable    STEAM    2300      Sat    l. 0 N/A Not Applicable NOTES:
(1) The valve opened at a reduced pressure prior to data acquisition activation.
(2) Unstable conditions precluded reliable measurement.
(3) The valve fluttered and/or chattered during loop seal discharge. The valve stabilized on steam.
(4) Data available after valve opening indicated stable performance.
(5) Chatter occurred simultaneous with steam/water transition.
(5) Chatter occurred simultaneous with steam/water transition.
NIJM!rlAL NOM lNAL VALVE VALVE LEAY-AGE % BLOWDOWN VALVE MEDIA INLET INLET RATE STABILITY PRESS. TEMP. (GPM) (PSIA) (OF) 10. l stable (4) STEAM 2320 Sat 3.8 18.8 stable (3) STEAM 2298 Sat 0.0 18.9 stable (3) . STEAM 2307 Sat 0.0 17. 7 stable (3) STEAM 2300 Sat o.o (2) chatter (3)(5)WATER 2296 305 0.0 20. 1 stable STEAM 2300 Sat o.o 19. 9 stable STEAM 2302 Sat .34 15.7 stable STEAM 2300 Sat l. 0 i I . I I w I CJ) w TEST TEST NO. TYPE 403 STEAM 525 LS 526 LS 529 LS 532 LS TRANS 535 STEAM 536 LS 537 STEAM N/A Not Applicable NOTES: VALVE CROSBY CONDITIONS AT 3% ACCUMULATION (1) BASED ON BASED ON TANK PRESSURE VALVE INLET PRESSURE % RATED % RATED % R/.\TED % RATE[* LIFT STEAM LI FT STEAM FLOW FLOW N/A N/A N/A N/A N/A N/A N/A N/A 109 96 108 97 111 99 110 100 N/A N/A N/A N/A 101 94 101 95 105 94 105 96 102 99 103 101 EPRI/CE SAF VE TEST DATA TABLE 3.4.1.d FLOW RATE PEP>ORMANCE DATA FOR THE -HB-BP-86 3K6 (LOOP SEAL INTERNALS)
 
CONDITIONS AT 6% ACCUMULATION ( 1) BASED ON BASED ON TANK SSURE VALVE INLET PRESSURE % RATE2 % RATED % RATED % RATED LIFT STEAM LIFT STEAM FLOW F.LOW N/A 1-J/A N/A N/A N/A N/A N/A N/11 109 101 109 104 (3) (3) (3) (3) N/A N/A N/A N/A (3) ( 3) (3) (JJ 107 104 104 105 103 105 103 108 (1) During the valve closing cycle. The valve inlet pressure corresponds to pressure.
EPRI/CE SAF          VE TEST DATA TABLE 3.4.1.d VALVE FLOW RATE PEP>ORMANCE DATA FOR THE CROSBY -HB-BP-86 3K6 (LOOP SEAL INTERNALS)
(2) Unstable conditions precluded reliable measurement.  
CONDITIONS AT 3% ACCUMULATION (1)                       CONDITIONS AT 6% ACCUMULATION ( 1)
BASED ON                 BASED ON                                                                       LIQUID FLOW MEASUREMENT TANK PRESSURE                                             BASED ON                    BASED ON TEST                                    VALVE INLET PRESSURE             TANK ~P.E SSURE                                                    MAX.
TEST    % RATED     %RATED % R/.\TED         % RATE[*                                 VALVE INLET PRESSURE  TANK CONDITIONS    STEADY NO. TYPE                                                            % RATE2      % RATED % RATED          % RATED LIFT         STEAM     LI FT         STEAM           LIFT                                          PRESS. TEMP. LI QU Ji)  % RATED FLOW                                                   STEAM      LIFT        STEAM  ( PSIA)    (OF)
FLOW                           FLOW                                                FLOW        LIFT F.LOW                      (GPMl 403    STEAM    N/A            N/A       N/A           N/A             N/A 525  LS                                                                                1-J/A    N/A         N/A       N/A     N/A N/A             N/A       N/A           N/A                                                                                 N/A        N/A N/A             N/A       N/A         N/11 526    LS      109              96                                                                                      N/A       N/A       N/A       N/A 108              97            109             101 529    LS                                                                                          109         104     N/A      N/A        N/A 111              99      110            100                                                                                            N/A (3)             (3)       (3) 532  LS        N/A            N/A                                                                              (3)     N/A      N/A      N/A        N/A N/A            N/A            N/A             N/A TRANS                                                                                        N/A         N/A       (2)      (2)        (2)        (2) 535  STEAM    101              94      101              95            (3)             ( 3)     (3) 536  LS        105              94                                                                            (JJ     N/A      N/A      N/A        N/A 105              96            107             104 537  STEAM                                                                                      104         105       N/A      N/A      N/A w                      102              99      103           101                                                                                            N/A I                                                                            103            105       103         108       N/A CJ)                                                                                                                                      N/A      N/A        N/A w
N/A Not Applicable NOTES:
(1) During the valve closing cycle. The valve inlet pressure corresponds to (2) Unstable conditions precluded reliable measurement.
                                                                                            -~tagnation  pressure.
(3) The appropriate measurement conditions were not achieved.
(3) The appropriate measurement conditions were not achieved.
LIQUID FLOW MEASUREMENT MAX. TANK CONDITIONS STEADY PRESS. TEMP. LI QU Ji) % RATED ( PSIA) (OF) FLOW LIFT (GPMl N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (2) (2) (2) (2) N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
* For the low backpressure test, the valve opened at a system pressure of 2410 psia, had stable behavior and closed with 8.2% blowdown.
Loop Seal-Steam Tests Seven 100&deg;F nominal temperature loop seal-steam tests were performed at test initiation ramp rates of 3.2-375 psi/sec and back pressures ranging from 227 to 710 psia. For four tests, the valve lift initiation occured at a system pressure within .:!::_3% of the valve design set pressure.
For all of the tests, the valve initially opened, fluttered and/or chattered at partial lift sition during the loop seal discharge, then popped open on steam at press8res ranging from 2580 to 2734 psia and stabilized.
The valve closed with a down varying from 5.1 to 9.4%. Four high ramp rate, low back pressure, 350&deg;F nominal temperature loop steam tests were performed.
For all of the tests, the valve opened initially within .:!::_3% of the valve design set pressure, fluttered and/or chattered at partial lift position during the loop seal discharge (except test no. 1415), popped open on steam at pressures of 2662-2755 psia and closed with 6.2-9.0% blowdown.
During two tests, the valve chattered on closu*re, and the tests were terminated after the valve was manually opened to stop the chattering.
While the loop seal was being discharged during loop seal tests, the valve fluttered and/or chattered through partial lift positions at frequencies of approximately 170-260 Hz. The valve oscillations during the water charge caused water-hammer type pressure oscillations measured in the valve inlet piping. For the 900 series tests, pressure oscillations measured in the pressure transducers located 13 inches upstream of the valve inlet flange face indicated pressures ranging from 0 psia to a pressure which over-ranged the transducer at 3400-3600 psia. For the 1400 series tests, the 900 series pressure transducers were replaced by pressure transducers with increased pressure ranges and strain gauges were mounted on the inlet pipe 15 inches upstream of the valve inlet flange face. The 1400 series data indicated that the pipe was responding to internal pressure oscillations of +/-_2450 psia at a frequency of approximately 170-260 Hz about a steady state pressure of 2650 psia. These internal pressures are based on strain gauge data since the pressure transducer sensing line lengths did not result in accurate pressure measurements for the frequency of these oscillations.
3-66 


===3.5 CROSBY===
For the low backpressure test, the valve opened at a system pressure of 2410 psia, had stable behavior and closed with 8.2% blowdown.
HB-BP-86 6M6 (LOOP SEAL INTERNALS) 3.5. l Valve Description and Inlet Piping Configuration, "As Tested"Test Matrix and Valve Performance Data. Tests were performed on the Crosby HB-BP-86 6M6 (Loop Seal Internals) safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility.
Loop Seal-Steam Tests Seven 100&deg;F nominal temperature loop seal-steam tests were performed at test initiation ramp rates of 3.2-375 psi/sec and back pressures ranging from 227 to 710 psia. For four tests, the valve lift initiation occured at a system pressure within .:!::_3% of the valve design set pressure. For all of the tests, the valve initially opened, fluttered and/or chattered at partial lift po-sition during the loop seal discharge, then popped open on steam at press8res ranging from 2580 to 2734 psia and stabilized. The valve closed with a blow-down varying from 5.1 to 9.4%.
The valve model was tested. on a long inlet piping configuration (test series 900 and 1400, configuration G). The fol lowing is the 1 ist of tables that contain the safety valve information/data for these tests: Table Description Safety Valve Description and Inlet Piping Configuration "As Tested" Test Matrix Valve Transient and Leakage Performance Data Valve Flow Rate Performance Data 3.5.2 Principal Observations Table Number 3.5.l.a 3. 5. 1. b 3.5. l.c 3.5.l.d A total of seventeen tests were performed on the Crosby HB-BP-86 6M6 (Loop Seal Internals) safety valve mounted on a long inlet pipe configuration.
Four high ramp rate, low back pressure, 350&deg;F nominal temperature loop seal-steam tests were performed. For all of the tests, the valve opened initially within .:!::_3% of the valve design set pressure, fluttered and/or chattered at partial lift position during the loop seal discharge (except test no. 1415),
Essentially, two groups of tests were performed.
popped open on steam at pressures of 2662-2755 psia and closed with 6.2-9.0%
The first group of tests (nos. 903 to 926) were performed with *several "lowered" ring positions selected in order to increase the opening time and decrease the inlet transient pressure drop. The second group of tests (nos. 929 to 932 and the 1400 series tests) generated valve performance data for the Crosby valve with ring positions representative of typical PWR plant ring positions.
blowdown. During two tests, the valve chattered on closu*re, and the tests were terminated after the valve was manually opened to stop the chattering.
The principal observations for these tests are as follows: Steam Tests Two high ramp rate steam tests were performed at high and low back sures. During the high back pressure test, the valve opened at a system pressure of 2490 psia, had stable behavior and closed with 9.5% blowdown . 3-65
While the loop seal was being discharged during loop seal tests, the valve fluttered and/or chattered through partial lift positions at frequencies of approximately 170-260 Hz. The valve oscillations during the water dis-charge caused water-hammer type pressure oscillations measured in the valve inlet piping. For the 900 series tests, pressure oscillations measured in the pressure transducers located 13 inches upstream of the valve inlet flange face indicated pressures ranging from 0 psia to a pressure which over-ranged the transducer at 3400-3600 psia. For the 1400 series tests, the 900 series pressure transducers were replaced by pressure transducers with increased pressure ranges and strain gauges were mounted on the inlet pipe 15 inches upstream of the valve inlet flange face. The 1400 series data indicated that the pipe was responding to internal pressure oscillations of +/-_2450 psia at a frequency of approximately 170-260 Hz about a steady state pressure of 2650 psia. These internal pressures are based on strain gauge data since the
* Transition Tests Three low ramp rate, high back pressure, steam-to-water transition tests were performed.
* pressure transducer sensing line lengths did not result in accurate pressure measurements for the frequency of these oscillations.
Two of the tests included loop seals (nos. 914 and 931) and one test was a drained loop seal test (no. 926). Test number 914 was performed with the valve rings inccirrect1y set and the valve chattered during the steam portion of the test. For the tests with the rings rectly set, the valve had stable performance and closed with blowdowns of 9.1 to 13.1%. The pressure oscillation description in the Loop Seal-Steam section also applies to the loop seal-transition tests. Water Tests After the valve closed on test no. 931 (loop seal-steam-to-water tion test), the system was permitted to repressurize and the valve cycled on 650&deg;F nominal temperature water. Test observations indicated that the valve did not chatter. During the 550&deg;F subcooled water test, the valve opened at a system pressure within +/-_3% of the valve design set pressure and chattered.
3-66
 
3.5   CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS) 3.5. l   Valve Description and Inlet Piping Configuration, "As Tested"Test Matrix and Valve Performance Data.
Tests were performed on the Crosby HB-BP-86 6M6 (Loop Seal Internals) safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The valve model was tested. on a long inlet piping configuration (test series 900 and 1400, configuration G). The fol lowing is the 1ist of tables that contain the safety valve information/data for these tests:
Table Description                                   Table Number Safety Valve Description and Inlet Piping Configuration                                       3.5.l.a "As Tested" Test Matrix                               3. 5. 1. b Valve Transient and Leakage Performance Data         3.5. l.c Valve Flow Rate Performance Data                      3.5.l.d 3.5.2 Principal Observations A total of seventeen tests were performed on the Crosby HB-BP-86 6M6 (Loop Seal Internals) safety valve mounted on a long inlet pipe configuration. Essentially, two groups of tests were performed. The first group of tests (nos. 903 to 926) were performed with *several "lowered" ring positions selected in order to increase the valv~ opening time and decrease the inlet transient pressure drop.       The second group of tests (nos. 929 to 932 and the 1400 series tests) generated valve performance data for the Crosby valve with ring positions representative of typical PWR plant ring positions. The principal observations for these tests are as follows:
Steam Tests Two high ramp rate steam tests were performed at high and low back pres-sures. During the high back pressure test, the valve opened at a system pressure of 2490 psia, had stable behavior and closed with 9.5% blowdown .
3-65
 
Transition Tests Three low ramp rate, high back pressure, steam-to-water transition tests were performed. Two of the tests included loop seals (nos. 914 and 931) and one test was a drained loop seal test (no. 926). Test number 914 was performed with the valve rings inccirrect1y set and the valve chattered during the steam portion of the test. For the tests with the rings cor-rectly set, the valve had stable performance and closed with blowdowns of 9.1 to 13.1%. The pressure oscillation description in the Loop Seal-Steam
_l~t~ section also applies to the loop seal-transition tests.
Water Tests After the valve closed on test no. 931 (loop seal-steam-to-water transi-tion test), the system was permitted to repressurize and the valve cycled on 650&deg;F nominal temperature water. Test observations indicated that the valve did not chatter.
During the 550&deg;F subcooled water test, the valve opened at a system pressure within +/-_3% of the valve design set pressure and chattered.
The test was terminated after the valve was manually opened to stop the chattering.
The test was terminated after the valve was manually opened to stop the chattering.
Valve Lift For those.tests in which the valve was in full lift at a pressure 6% above the valve design set pressure, rated flow was achieved even though the valve was in a lift position of up to 8% below rated lift. Valve Inspection Results After each test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected.
Valve Lift For those.tests in which the valve was in full lift at a pressure 6% above the valve design set pressure, rated flow was achieved even though the valve was in a lift position of up to 8% below rated lift.
In each case, galled guiding surfaces and damaged internal parts were found. 3-67
Valve Inspection Results After each test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected. In each case, galled guiding surfaces and damaged internal parts were found.
/ Damaged parts were eilher refurbished or replaced prior to continued testing. For all other inspections, the typical wear pattern observed was scratches or marks on the seat surf aces. The seat surfaces were lapped prior to and continued testing in order to minimize 1 seat leakage. 3-68
3-67
* w EPRI/CE TEST PROGRAM TABLE 3.5.1.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
 
Valve Description Inlet Piping Configuration "G" Length, in. Manufacturer TV!iP Model No. Serial No. Drawing No. Crosby Valve and Cage Company Valve HB-BP-86 6M6 N56964-00-0086 Crosby DS-C-56964 Rev. C Body Size (inlet/outlet) 6 in./ 6 in. Bore Area 3.644 in.2 --------Orifice Designation M ------Design Set Point Pressure _2_4_8_5 _ __,psig Nozzle . 17 Venturi 3.8 Pipe 13 Reducer 6 Loop Seal Straight 48 Bends 2-1800 Design Slowdown ___ 5 _ _,percent l.O Inlet Flange 10 Rated Flow 420,006 lb/hr. Rated Lift 0.538 ------Internals Type: Loop Seal Ring Setting Reference Position ring setting position refers to the number of notches relative to the bottom of the disc ring.
Damaged parts were eilher refurbished or replaced prior to continued testing.
* J.D., in. 6.813 6.813 6.813 6.813/4.897 4.897 9 in. radius 4.897 w I -....J I-"
For all other inspections, the typical wear pattern observed was scratches or marks on the seat surf aces. The seat surfaces were lapped prior to
* TEST TEST VALVE RING INLET NO TYPE SETTINGS PIP ING UPPER MIDDLE LOWER CONFIG. *903 STEAM -136 -68 G 906a LS -136 -68 G b c 908 LS -136 -68 G *910 LS -136 -68 G 913 LS 66 G *914a LS 66 G TRANS b c 917 LS -136 -68 G *920 LS -136 -68 G 923 LS -186 -68 G N/A Applicable NOTES: EPRI/CE TEST DATA TABLE 3.5. l .b "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE CROSBY HB-BP-86-6M6 (LOOP SEAL INTERNALS)
  ~eassembly and continued testing in order to minimize 1seat leakage.
CONDITIONS AT VALVE OPENING IN TANK l AT VALVE INLET FLUID PRESS. TEMP. PRESS. RATE FLUID TEMP. (PSIA) (oF) \PSI/SEC)  
/
("F) STEAM 2490 (l) 291 STEAM (1) STEAM 2582 ( 1 ) 3.2 WATER ( 5) STEAM 2455 31. 5 STEAM (1) STEAM 2456 14.2 STEAM ( 1i STEAM 2567 ( l) 297 WATER ( 5) STEAM 2480 (l) 375 WATER ( 5) STEAM 2550 ( 1 ) 375 WATER (5) STEAM 2510 (l) 1. 1 WATER ( 5) STEAM 2400 21.8 STEAM (1) STEAM 2360 (3) STEAM (1) STEAM 2458 ( 1 ) 291 WATER (5) STEAM 2497 ( 1 ) 297 WATER (5) STEAM 2649 (1) 283 WATER 91 TRANSIENT CONDITIONS PEAK PEAK INDUCED (2) TANK l BACK-BENDING MOMENT PRESS. PRESS. OPENING/CLOS ING (PSIA) (PSIA) (IN. LBS.) 2667 665 215, 100 2582 554 256,925 2455 532 2456 520 2688 649 298,750 2634 227 209, 125. 2735 242 239,000 2516 520 203,150 2400 330 2400 (3) 2732 245 227,050 2725 246 215' 100 2736 667 179,250 (1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation temperature.  
3-68
(2) The reported values are the maximum induced bending moments on the valve discnarge flange durino openinq or closing. ( 3) Unstable conditions precluded reliable measurement.  
* EPRI/CE SAFET~E      TEST PROGRAM TABLE 3.5.1.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
Valve Description                                                     Inlet Piping Configuration "G" Length, in. J.D., in.
Manufacturer          Crosby Valve and Cage Company                   Nozzle              . 17 TV!iP 5~rir.g ~8adcd ~~7cty Valve                                                         6.813 Model No.              HB-BP-86 6M6                                   Venturi Serial No.            N56964-00-0086                                                         3.8          6.813 Drawing No.          Crosby DS-C-56964 Rev. C                         Pipe                  13            6.813 Body Size (inlet/outlet)         6     in./     6   in.             Reducer                6 Bore Area 3.644     in.2 - - - -           ----                                                           6.813/4.897 Orifice Designation           M                                       Loop Seal Straight          48            4.897 Design Set Point Pressure _2_4_8_5_ __,psig                               Bends             2-1800 w                                                                                                          9 in. radius
~  Design Slowdown ___   5 _ _,percent                                   Inlet Flange l.O                                                                                             10           4.897 Rated Flow 420,006   lb/hr. Rated Lift 0.538 Internals Type:   Loop Seal Ring Setting Reference Position Th~ ring setting position refers to the number of notches relative to the bottom of the disc ring.
* EPRI/CE   SA~LVE TABLE 3.5. l .b TEST DATA "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE CROSBY HB-BP-86-6M6 (LOOP SEAL INTERNALS)
CONDITIONS AT VALVE OPENING                             TRANSIENT CONDITIONS TEST      TEST        VALVE RING          INLET                      IN TANK l                       AT VALVE INLET PEAK    PEAK    INDUCED (2)    MAX. STEADY NO        TYPE        SETTINGS          PIP ING                                                                    TANK l  BACK-    BENDING MOMENT  LIQUID FLOW UPPER MIDDLE LOWER      CONFIG. FLUID     PRESS.     TEMP.     PRESS. RATE       FLUID   TEMP. PRESS. PRESS. OPENING/CLOS ING    (SPM)
(PSIA)     (oF)       \PSI/SEC)                 ("F)   (PSIA)  (PSIA)    (IN. LBS.)
        *903    STEAM  -136            -68      G    STEAM     2490       (l)           291           STEAM   (1)   2667    665        215, 100        NJfJ.
906a LS        -136            -68      G    STEAM     2582       (1)               3.2       WATER   ( 5)   2582    554        256,925          'i/A b                                          STEAM     2455                         31. 5       STEAM   (1)   2455    532                        'UA c                                          STEAM     2456                         14.2       STEAM   ( 1i   2456    520                        ':i/A 908    LS    -136            -68      G    STEAM     2567       ( l)           297           WATER   ( 5)   2688    649        298,750          ,,,~
        *910    LS    -136            -68      G    STEAM     2480       (l)           375           WATER   ( 5)   2634    227        209, 125.        ':i/A 913    LS    - 44            -66      G    STEAM     2550       (1)           375           WATER   (5)   2735    242        239,000          ~I/A w
I
-....J  *914a    LS    - 44            -66      G    STEAM     2510         (l)               1. 1     WATER   ( 5)   2516    520        203,150          (4)
I-"              TRANS b                                          STEAM     2400                         21.8       STEAM   (1)   2400    330                          (4) c                                          STEAM     2360                         (3)         STEAM   (1)   2400    (3)                          (4) 917    LS    -136            -68      G    STEAM     2458         (1 )         291           WATER   (5)   2732    245        227,050          NI.A
        *920    LS    -136            -68      G    STEAM     2497       (1 )           297           WATER   (5)   2725    246        215' 100          N/A 923    LS    -186            -68      G    STEAM     2649       (1)           283           WATER     91   2736   667       179,250         N/A.
N/A l~ot Applicable NOTES:
(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation temperature.
(2) The reported values are the maximum induced bending moments on the valve discnarge flange durino openinq or closing.
( 3) Unstable conditions precluded reliable measurement.
(4) The test was terminated, interferinq with this measurement.
(4) The test was terminated, interferinq with this measurement.
* The valve was disassembled, inspected, and refurbished as required, for representative test performance.  
* The valve was disassembled, inspected, and refurbished as required, for representative test performance.
(5) The test malfunctioned.
(5) The test in~trllfnent;ition malfunctioned. No reliable measurement was avaiiable.
No reliable measurement was avaiiable.
J
* MAX. STEADY LIQUID FLOW (SPM) NJfJ. 'i/A 'UA ':i/A
* trl\ 111.,t                 It ST UA TA TABLE 3.5. l .b (Con' t)
':i/A (4) (4) (4) NI.A N/A N/A. J w I -....J w
                                                              "AS TESTED" COMBUSTION ENGINEERING           TE~T  MATRIX FOR THE CROSBY HB-BP-86-6M6 (LOOP SEAL INTERNALS)
* TEST TEST VALVE RING INLET NO. TYPE SETTINGS PIPING UPPER MIDDLE LOWER CONFJG. *926a TRANS -186 -68 G b c d 929 LS 18 G 93la LS 18 G TRANS b *932 WATER 18 G *1406 LS 18 G *1411 STEAM 18 G 1415 LS 18 G *1419 LS 18 G N/A Not applicable NOTES: trl\ 111.,t It ST UA TA TABLE 3.5. l .b (Con' t) "AS TESTED" COMBUSTION ENGINEERING MATRIX FOR THE CROSBY HB-BP-86-6M6 (LOOP SEAL INTERNALS)
CONDITIONS AT VALVE OPENING                                             TRANSIENT CONDITIONS TEST    TEST        VALVE RING          INLET                                                                          PEAK              PEAK                INDUCED (2)      MA.X. STEADY NO. TYPE          SETTINGS          PIPING                        IN TANK l                         AT VALVE INLET TANK 1            BACK-                BENDING MOMENT    LIC'.! ! D FLOW UPPER MIDDLE LOWER      CONFJG. FLUID   PRE SS.       TEMP.     PRESS. RATE     FLUID   TEMP. PRESS.            PRESS. OPENING/CLOSING                      (GPM)
CONDITIONS AT VALVE OPENING IN TANK l AT VALVE INLET FLUID PRE SS. TEMP. PRESS. RATE FLUID TEMP. ( P<;TA) (OF) !PST /<;Fr\ ran ' , STEAM/ 2389 (l) 2.0 STEAM (1) WATER STEAM/ l. 6 STEAM (1} WATER STEAM/ l.9 STEAM (l) WATER WATER l. 5 l*IATER 635 STEAM 2600 (l) 319 WATER 90 STEAM/ 2570 ( l ) 2.5 WATER 117 WATER (4) (4) (4) WATER 2501 515 3.0 WATER 463 STEAM. 2530 (1) 325 WATER 147 STEAM 2410 (1) 300 STEAM (l) STEAM 2555 (l) 360 WATER 290 STEAM 2464 ( 1 ) 360 WATER 350 TRANSIENT CONDITIONS PEAK PEAK INDUCED (2) TANK 1 BACK-BENDING MOMENT PRESS. PRESS. OPENING/CLOSING ( OC"l I'\' r nr T n' ( ;;i. LBS.) \' ...... , \' _,,,,.,...., 2389 445 95,600 2385 440 2384 650 2271 585 2726 710 179,250 2578 725 201, 150 (4) (4) 2520 650 107 ,550 2703 250 286,800 2664 245 239,000 2760 255 268,875 2675 245 256,925 (1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was* the saturation temperature.  
( P<;TA)       (OF)       !PST /<;Fr\                 ran
(2) The reported values are the maximum induced bending moments on the valve discharge flange durina openi:19 or closinq. (3) Unstable conditions preclude reliable measurements.  
                                                                                                                            ' ,         ......I'\',
(\ 'OC"l                    T n' r\ 'nr_,,,,.,....,      ( ;;i. LBS.)
        *926a    TRANS -186            -68        G    STEAM/     2389           (l)             2.0           STEAM     (1) 2389                445                    95,600              N/A WATER b                                          STEAM/                                     l. 6         STEAM     (1} 2385                  440                                        N/A WATER c                                          STEAM/                                     l.9           STEAM     (l) 2384                  650                                        ~II A WATER d                                          WATER                                     l. 5         l*IATER   635 2271                  585                                      2233 929    LS      -71            -18        G    STEAM     2600           (l)           319             WATER     90 2726                  710                  179,250              ~l/A w
I
-....J    93la    LS      -71            -18        G    STEAM/     2570           (l )             2.5           WATER     117 2578                  725                  201, 150            2355 w                TRANS                                  WATER b                                                                                      (4)          (4)      (4) (4)                   (4)
        *932      WATER   -71            -18        G    WATER      2501           515             3.0           WATER     463 2520                  650                  107 ,550              (3)
      *1406      LS      -77            -18        G    STEAM. 2530           (1)           325             WATER     147 2703                  250                  286,800              II/A
      *1411      STEAM   -77            -18        G    STEAM      2410           (1)           300             STEAM     (l) 2664                  245                  239,000              N/A 1415    LS      -77            -18        G    STEAM     2555           (l)           360             WATER     290 2760                255                  268,875              NIA
      *1419      LS      -77            -18        G    STEAM     2464           (1)           360             WATER     350 2675                 245                 256,925               N/A N/A Not applicable NOTES:
(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was* the saturation temperature.
(2) The reported values are the maximum induced bending moments on the valve discharge flange durina openi:19 or closinq.
(3) Unstable conditions preclude reliable measurements.
(4) These data were not available
(4) These data were not available
* The valve was disassembled, inspected, and refurbished as required for test performance.
* The valve was disassembled, inspected, and refurbished as required for re,resent~tive test performance.
* MA.X. STEADY LIC'.! ! D FLOW (GPM) N/A N/A A 2233 2355 (3) II/A N/A NIA N/A l:.PRl/CE
 
':>A. LVE JEST DATA
l:.PRl/CE ':>A.        LVE JEST DATA TABLE 3.5.1.c VALVE TRANSIENT h~D LEA~AGE PlR~ukMANLE UAIA FUR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
* TABLE 3.5.1.c VALVE TRANSIENT UAIA FUR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
PRE-TEST VAL VE LEAKAGE NOMINAL NOMINAL                                                VAL VE OPENING AND CLOSING TEST                            VALVE      VALVE LEAKAGE      INITIAL                                            TANI< I                              POST-TEST VALVE -~AKAGE TEST    MEDIA      INLET      INLET                            OPENING      OPENING        OPENING                                              NO~~HIAL NOt>':~.!L NO.        TYPE                                    RATE    OPENING        "POP"                                  PRESS.
PRE-TEST VAL VE LEAKAGE VAL VE OPENING AND CLOSING POST-TEST VALVE NOMINAL NOMINAL TANI< I VALVE VALVE LEAKAGE INITIAL OPENING OPENING OPENING PRESS. VilLVE VAL'::: LEAKAGE TEST TEST MEDIA INLET INLET RATE OPENING "POP" SIMMER "POP" AT VALVE % BLOWDOWN VALVE MEDIA Ilic ET R.l\T E NO. TYPE PRESS. TEMP. (GPM) PRESS. PRESS. TIME TIME CLOSURE STABILITY PPtSS. E"i:-. (GPM) (PSIA OF PSIA PSIA SEC SEC PSIA) (FSIA) 903 STEAM STEAM 2275 470 o.o 2490 2496 .0194 .008 2264 9.5 stable STEAM Sat n.o 906a LS WATER 2300 104 o.o 2582 2580 .857 (5) 2294 8.3 stable (4) STEAM 2300 Sa: 0.0 b 2555 2294 8.3 stable c 2557 2298 8.1 stable 908 LS WATER 2275 159 o.o 2567 2687 .93 .012 2294 8.3 stable ( 4) STEAM 2276 Sat 0.0 910 LS WATER 2280 354 0.0 2480 2628 l. 17 (5) 2306 7.8 stable (4) STEAM 2300 Sat 0.0 w 913 LS WATER 2300 124 0.0 2550 2734 .82 .014 2316 7.4 stable (4) STEAM 2300 590 1.0 I -....J 914a LS WATER 2308 126 o.o 2510 2500 2.94 .011 2309 7.7 stable (4) (6) (6) (6) (5) tJ1 TRAHS b 2400 2360 5.6 stable c 2360 (2) (2) chatter .... 917 LS WATER 2280 477 0.0 2458 2662 .69 .016 2276 9.0 stable (4) STEAM 2300 Sat o.o 920 LS WATER 2292 333 0.0 2497 2695 0.73 0.017 (2) (21 chatter (7) STEAM 2275 Sat 0.0 923 LS WATER 2275 94 0.0 2649 2732 0.9 0.009 2308 7.7 stable (4) STEAM 2300 Sat 0.0 N/A Not Applicable NOTES: (1 J No measurement .was taken. (2) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.  
PRESS. TEMP.     (GPM)                                  SIMMER        "POP"  AT VALVE % BLOWDOWN                          VilLVE    VAL'::: LEAKAGE (PSIA      OF                  PRESS.      PRESS.           TIME                                        VALVE      MEDIA    Ilic ET              R.l\T E TIME  CLOSURE                                                Ir1~:~
(3) Unstable condition precluded reliable measurements.
PSIA          PSIA          SEC                                        STABILITY            PPtSS.             (GPM) 903                                                                                                        SEC      PSIA)                                                E"i:-.
The*valye stabilized on steam. (4) The valve fluttered and/or chattered during the loop seal discharge. The test instrument malfunctioned.
STEAM    STEAM      2275                                                                                                                          (FSIA)     (C~
No reliable data was available.
470         o.o     2490           2496           .0194 906a      LS                                                                                              .008     2264       9.5 WATER       2300       104         o.o                                                                               stable      STEAM      2~08 b                                                          2582          2580             .857         (5)
limit of lO gpm. Post-test leakage was not measured because it exceeded the system measurement (7) The valve chattered on closure.
Sat      n.o 2294     8.3     stable (4) c                                                                        2555                                                                  STEAM     2300     Sa:       0.0 2294     8.3       stable 908        LS                                                                2557                                   2298 WATER      2275                                                                                            8.1       stable 159         o.o     2567           2687           .93 910        LS                                                                                              .012     2294       8.3   stable (4)
w I -....J -....J
WATER      2280       354         0.0                                                                                           STEAM    2276      Sat 2480           2628         l. 17 0.0 w        913      LS      WATER                                                                                    (5)     2306       7.8   stable (4)
* PRE-TEST VALVE LEAKAGE NOMINAL NOMI NAE VALVE VALVE LEAKAGE TEST TEST MEDIA INLET INLET RATE NO. TYPE PRESS. TEMP. (GPM) (PS!AJ (OF) 926 a TRANS STEAM 2283 Sat 0.36 b c d 929 LS WATER 2290 94 o.o 93la LS WATER 2300 122 0.0 TRANS b 932 WATER WATER 2300 489 0.0 1406 LS WATER 2300 105 o.o 1411 STEAM STEAM 2275 Sat 0.76 1415 LS WATER 2300 196 o.o 1419 LS WATER 2300 342 0.0 N/A Not applicable NOTES: (1) No measurement was taken. EPRl/CE SA.LVE TEST DATA rn . 5. I. c (Con ' t) VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
I 2300      124        0.0    2550                                                                                  STEAM     2300     Sat       0.0
VAL VE OPENING AND CLOSING TANK I INITIAL OPENING OPENING OPENING PEESS. OPENING "POP" SIMMER "POP" AT VALVE % BLOWDOWN PRESS. PRESS. TIME TIME CLOSURE (PSIA} {PSIA} {SEC} (SEC} (PSIA) 2389 2389 0.010 0.013 2267 9.4 2385 2274 9.1 2384 2174 13. 1 2263 2203 12.0 2600 2717 0.83 0.019 23"13 5 .1 2570 2575 4.25 0.021 (6) (6) (6) (6) (6) 2501 (3) (3) N/A (2) (2) 2595 (3) (5) (5) 2666 9.4 2410 2420 .007 .019 2297 8.2 2555 2755 1. 115 .012 2346 6.2 2464 2674 l .035 .019 (2) (2)
-....J                                                                                2734           .82           .014 tJ1      914a      LS      WATER                                                                                            2316     7.4     stable (4) 2308      126        o.o      2510                                                                                  STEAM     2300     590       1.0 TRAHS                                                              2500        2.94            .011      2309     7.7     stable (4) b                                                                                                                                                  (6)       (6)     (6)       (5) 2400 2360       5.6       stable c
* POST-TEST VALVE LEAKAGE NOMINAL NOMINAL VALVE VALVE LEAKAGE VALVE MEDIA INLET INLET RATE STABILITY PRESS. TEMP. (GPM) (PSIA) (OF) Stable STEAM . 2295 Sat 0.08 Stable Stable Stable Stable (4) WATER 2300 476 0.0 Stable(4)
2360 (2)       (2)       chatter 917       LS       WATER       2280       477         0.0     2458                                                                                                                           ....
WATER 2295 485 0.0 (7) Chatter ( 1) ( 1) ( 1) ("1) Stable (4) STEAM 2275 Sat 0.63 Sfable STEAM 2275 Sat 0.37 Stable STEAM 2300 540 0.0 Chatter (B) STEAM 2300 Sat l. 5 (2) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.  
2662          .69          .016 920      LS      WATER                                                                                            2276     9.0     stable (4) 2292        333        0.0                                                                                            STEAM     2300     Sat       o.o 2497         2695       0.73 923      LS                                                                                            0.017     (2)       (21 WATER      2275        94                                                                                        chatter (7)   STEAM     2275     Sat 0.0     2649          2732        0.9                                                                                        0.0 0.009     2308       7.7     stable (4)   STEAM     2300       Sat       0.0 N/A Not Applicable NOTES:
(3) Unstable condition precluded reliable measurement.
(1 J No measurement .was taken.
(4) The valve fluttered and/or chattered during the loop seal discharge.
(2)
The valve stabilized on steam. (5) The test instrument malfunctioned.
(3)    The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.
No reliable data was available.  
(4)
(6) These data were not available.
Unstable condition precluded reliable measurements.
(7) Visual test observations indicated that the valve did not chatter. (8) The valve chattered on closure.
The valve fluttered and/or chattered during the loop seal discharge.
w I '-.I \.0
(~? Post-test The test instrument malfunctioned. No reliable data was available.
* TEST TEST NO. TYPE 903 STEAM 906 LS 908 LS 910 LS 913 LS 914 LS TRANS 917 LS 920 LS 923 LS N/A Not Applicable NOTES: EPR!/CE SAF .VE TEST DATA TABLE 3.5.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
leakage   was not measured because it exceeded   the system The*valye stabilized on steam.
CONDITIONS AT 3% ACCUMULATION (I) CONDITIONS AT 6% ACCUMULATION ( 1) BASED or: BASED ON BASED ON BASED ON TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE % RATED % RATED % RATED % RATE[. % RATED % RATED % RATED % RATED LIFT STEAM LIFT STEAM LI FT STEAM LI FT STEAM. FLOW FLOW FLOW FLOW 93 (4) 93 ( 4) 94 (4) 94 (4) N/A N/A N/A N/A N/A A N/A N/A 97 104 97 105 99 110 99 110 ( 4) 104 (4) 107 (3) (3) (3) (3) 95 105 95 107 95 111 96 112 N/A N/A N/A N/A N/A N/A N/A 97 98 97 98 97 102 97 104 106 95 106 95 lll 95 111 95 104 95 105 96 109 96 110
measurement (7) The valve chattered on closure.                                                                   limit of lO gpm.
* LIQUID FLOW MEASUREMENT MAX. TANK CONDITIONS STEADY PRESS. TEMP. LIQUID % RATED (PSIA) (OF) FLOW LI FT (GPM) N/A N/A N/A N/A N/A N/A N/A '</A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (2) (2) (2) (2) N/A N/A N/A N/A "!/A N/A "/A N/A N/A N/A N/A N/A (1) During the valve closing cycle.The valve inlet pressure corresponds to stagnation pressure.
 
(2) The test was terminated when tile va 1 ve was manually opened to stop chatter interfering with this measurement.  
EPRl/CE SA.LVE TEST DATA rn      ~  . 5. I. c (Con ' t)
VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
PRE-TEST VALVE LEAKAGE                                   VAL VE OPENING AND CLOSING                                  POST-TEST VALVE LEAKAGE NOMINAL  NOMI NAE                                                                TANK I                                  NOMINAL NOMINAL VALVE    VALVE  LEAKAGE  INITIAL      OPENING    OPENING        OPENING      PEESS.                                  VALVE VALVE LEAKAGE TEST    TEST    MEDIA    INLET    INLET   RATE   OPENING        "POP"      SIMMER          "POP"      AT VALVE % BLOWDOWN    VALVE    MEDIA    INLET INLET    RATE NO. TYPE            PRESS. TEMP.   (GPM)   PRESS.        PRESS.      TIME            TIME      CLOSURE              STABILITY            PRESS. TEMP. (GPM)
(PS!AJ   (OF)              (PSIA}      {PSIA}    {SEC}            (SEC}      (PSIA)                                  (PSIA)  (OF) 926 a TRANS   STEAM   2283     Sat     0.36       2389        2389      0.010            0.013      2267      9.4      Stable      STEAM  . 2295  Sat  0.08 b                                                             2385                                  2274      9.1      Stable c                                                              2384                                  2174      13. 1    Stable d                                                              2263                                  2203      12.0     Stable 929    LS     WATER   2290        94    o.o       2600        2717      0.83            0.019      23"13      5 .1    Stable (4)  WATER     2300   476    0.0 93la  LS     WATER   2300     122      0.0       2570        2575      4.25            0.021        (6)        (6)     Stable(4)  WATER    2295  485    0.0 w              TRANS I
-....J
-....J b                                                              (6)                                     (6)        (6)      (7) 932    WATER  WATER    2300      489      0.0        2501          (3)        (3)            N/A          (2)      (2)    Chatter      ( 1)    ( 1)   ( 1) ("1) 1406    LS      WATER    2300      105      o.o        2595          (3)         (5)             (5)       2666      9.4    Stable (4)   STEAM    2275    Sat  0.63 1411    STEAM  STEAM    2275      Sat      0.76      2410         2420         .007           .019     2297       8.2     Sfable      STEAM    2275    Sat  0.37 1415    LS      WATER    2300      196      o.o        2555        2755      1. 115           .012     2346       6.2     Stable      STEAM    2300    540  0.0 1419    LS      WATER    2300      342      0.0        2464         2674       l .035           .019       (2)       (2)     Chatter (B) STEAM    2300    Sat l. 5 N/A Not applicable NOTES:
(1) No measurement was taken.
(2) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.
(3) Unstable condition precluded reliable measurement.
(4) The valve fluttered and/or chattered during the loop seal discharge. The valve stabilized on steam.
(5) The test instrument malfunctioned. No reliable data was available.
(6) These data were not available.
(7) Visual test observations indicated that the valve did not chatter.
(8) The valve chattered on closure.
* EPR!/CE SAF        .VE TEST DATA TABLE 3.5.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
CONDITIONS AT 3% ACCUMULATION (I)                       CONDITIONS AT 6% ACCUMULATION ( 1)         LIQUID FLOW MEASUREMENT BASED or:              BASED ON                      BASED ON                    BASED ON                        MAX.
TANK PRESSURE        VALVE INLET PRESSURE            TANK PRESSURE          VALVE INLET PRESSURE  TANK CONDITIONS    STEADY TEST     TEST     % RATED      %RATED %RATED          %RATE[.          % RATED        % RATED    % RATED      %RATED  PRESS. TEMP. LIQUID      % RATED NO. TYPE     LIFT          STEAM   LIFT          STEAM          LI FT          STEAM      LI FT        STEAM. (PSIA)    (OF)      FLOW       LI FT FLOW                  FLOW                          FLOW                    FLOW                      (GPM) 903  STEAM      93              (4)    93              ( 4)            94              (4)     94            (4)   N/A      N/A      N/A        N/A 906  LS        N/A            N/A    N/A            N/A              N/A            ~I/ A    N/A            N/A  N/A        N/A      N/A        '</A 908  LS        97            104    97            105              99              110      99            110  N/A       N/A       N/A       N/A 910    LS        (4)           104     (4)           107             (3)             (3)     (3)           (3)   N/A       N/A       N/A       N/A 913    LS        95            105    95            107              95              111        96          112  N/A       N/A       N/A       N/A 914    LS        N/A            N/A    N/A            N/A              N/A            ~I/A    N/A          N/A    (2)       (2)     (2)        (2)
TRANS w
I
'-.I 917    LS        97              98    97              98            97              102      97            104    N/A       N/A       N/A       N/A
\.0 920    LS                        106    95            106            95              lll      95            111    "!/A     N/A     "/A         N/A 923    LS        95            104    95            105            96              109      96            110    N/A       N/A     N/A         N/A N/A Not Applicable NOTES:
(1) During the valve closing cycle.The valve inlet pressure corresponds to stagnation pressure.
(2) The test was terminated when tile va 1ve was manually opened to stop chatter 1 interfering with this measurement.
(3)  The appropriate measurement conditions were not achieved.
(4) The instrumentation malfunctioned. No reliable measurement was available.
* Ei''llCE SAf-VE llSI DA1A TABLE    .5.1.d (Can't)
VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
CONDITIONS AT 3% ACCUMULATION (1)                          CONDITIONS AT 6% ACCUMULATION ( 1)          LIQUID FLOW MEASUREMENT BASED OK                BASED ON                      BASED ON                    BASED arr---
TANK PRESSURE        VALVE INLET PRESSURE              TANK PRESSURE TEST      TEST    % RATED      % RATED    % RATED                                                  VALVE INLET PRESSURE  TANK CONDITIONS    STEADY
                                                                  % RATED          %-R~--Y-RATED %RATED                  % RATED NO.      TYPE      LIFT          STEAM      LIFT          STEAM                                                          PRESS. TEMP. LIQUID      % RATED LIFT          STEAM      LI FT        SlEAM  (PSIA)    (OF)      FLOW FLOW                    FLOW                            FLOW                                                          LIFT FLOW                      (GPM) 926a  TRANS    N/A          N/A        N/A          N/A              N/A          N/A        N/A          N/A b
c d                                                                                                                  2300        640    2233          64 929    LS        93          1ll        93          112                93          117          93        118      N/A      N/A      N/A        N/A 93la  LS      N/A          N/A        N/A          N/A TRANS                                                            N/A            N/A        N/A          N/A    2415        641    2355          56 b
w          932    WATER    N/A            N/A      N/A            N/A I                                                                                N/A            N/A        N/A          N/A      (2)      (2)
CXl                                                                                                                                                    (2)        (2) 1406    LS        (2)          l 07      (2)          109              (2)          112        (2)          116    N/A      N/A      N/A        N/A 1411    STEAM      92          107        92          108                93          111        (3)          (3)    N/A      N/A      N/A        N/A 1415    LS        92          109        92          111                92          114          92          116    N/A      N/A      N/A        N/A 1419    LS        94          109          94          110                95          114        (3)          (3)    N/A      N/A      N/A        N/A N/A Not Applicable NOTES:
(1) During the valve closing cycle.The valve inlet pressure corresponds (2) Unstable conditions precluded reliable measurement.                           to stagnation pressure.
(3) The appropriate measurement conditions were not achieved.
(3) The appropriate measurement conditions were not achieved.
1 (4) The instrumentation malfunctioned.
 
No reliable measurement was available.
3.6   CROSBY HB-BP-86 6N8 (STEAM INTERNALS) 3.6. l   Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on   the Crosby HB-BP-86 6N8 safety valve model at the EPRI/CE PWR Safety-and Relief Valve     Test Facility. The valve was tested on a long (test series 1200, configuration H)     inlet piping configuration. The following is the list of tables that contain the     safety valve information/data for these tests:
* Ei''llCE SAf-VE llSI DA1A
Table Description                                   Table Number Safety Valve Descriptidn and Inlet Piping Configuration                                       3. 6. l. a "As Tested" Test Matrix                              3. 6. l. b Valve Transient and Leakage Performance Data          3.6.1.c Valve Flow Rate Performance Data                      3. 6. l. d 3.6.2    Principal Observations
* TABLE .5.1.d (Can't) VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)
* A total of eight tests was performed with the Crosby HB-BP-86 6N8 (Steam Internals) safety valve mounted on a long straight inlet pipe configuration. A flow venturi was not in -place during these tests. The principal observations for these tests are as follows:
CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ACCUMULATION ( 1) LIQUID FLOW MEASUREMENT BASED OK BASED ON BASED ON BASED arr---TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE TANK CONDITIONS STEADY TEST TEST % RATED % RATED % RATED % RATED
Steam Tests Five steam tests were performed at test initiation ramp rates of 2-325 psi/sec with three different ring positions. For all of the tests, the valve opened within ~3% of the design set pressure and had stable behavior.
%RATED % RATED PRESS. TEMP. LIQUID % RATED NO. TYPE LIFT STEAM LIFT STEAM LIFT STEAM LI FT SlEAM (PSIA) (OF) FLOW LIFT FLOW FLOW FLOW FLOW (GPM) 926a TRANS N/A N/A N/A N/A N/A N/A N/A N/A b c d 2300 640 2233 64 929 LS 93 1ll 93 112 93 117 93 118 N/A N/A N/A N/A 93la LS N/A N/A N/A N/A N/A N/A N/A N/A 2415 641 2355 56 TRANS b w 932 WATER N/A N/A N/A N/A N/A N/A N/A N/A (2) (2) (2) (2) I CXl ....... 1406 LS (2) l 07 (2) 109 (2) 112 (2) 116 N/A N/A N/A N/A 1411 STEAM 92 107 92 108 93 111 (3) (3) N/A N/A N/A N/A 1415 LS 92 109 92 111 92 114 92 116 N/A N/A N/A N/A 1419 LS 94 109 94 110 95 114 (3) (3) N/A N/A N/A N/A N/A Not Applicable NOTES: (1) During the valve closing cycle.The valve inlet pressure corresponds to stagnation pressure.
For those tests in which the system pressure was 6% above the valve design set pressure, the valve achieved a lift position which was 97% of its rated lift.
(2) Unstable conditions precluded reliable measurement.
The first two tests were performed with ring positions (-110, -18) repre-3-83
(3) The appropriate measurement conditions were not achieved. 
 
' . *
sentative of typical PWR plant ring positions. The valve opened, had stable behavior and closed with a blowdown range of 15.1 to 16.6%. Both tests were high back pressure tests.
* 3.6 CROSBY HB-BP-86 6N8 (STEAM INTERNALS) 3.6. l Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Crosby HB-BP-86 6N8 safety valve model at the EPRI/CE PWR Safety-and Relief Valve Test Facility.
In order to reduce the valve bJowdown, the ring positi*ons were changed two
The valve was tested on a long (test series 1200, configuration H) inlet piping configuration.
  ~imes during the subsequent steam tests. The last ring position (-40, -18) resulted in a blowdown of 9.6% and 9.8% for high and low back pressures, respectively. The last ring position was used during the subsequent transition and water tests.
The following is the list of tables that contain the safety valve information/data for these tests: Table Description Safety Valve Descriptidn and Inlet Piping Configuration "As Tested" Test Matrix Valve Transient and Leakage Performance Data Valve Flow Rate Performance Data 3.6.2 Principal Observations Table Number 3. 6. l. a 3. 6. l. b 3.6.1.c 3. 6. l. d A total of eight tests was performed with the Crosby HB-BP-86 6N8 (Steam Internals) safety valve mounted on a long straight inlet pipe configuration.
Transition Test One low ramp rate, high back pressure, steam-to-water transition test was performed. The valve had stable behavior during the four actuations of this transition test. During the initial actuation, the valve opened at a system pressure within ~3% of valve design set pressure and closed with 8.6% blowdown. During the subsequent actuations,! the opening pressure range was 2420 - 2480 psia and the closing pressur~ range was 2120 - 2305 psi a.
A flow venturi was not in -place during these tests. The principal observations for these tests are as follows: Steam Tests Five steam tests were performed at test initiation ramp rates of 2-325 psi/sec with three different ring positions.
Water Tests Two high back pressure water tests were performed at nominal temperat~res of 650&deg;F and 550&deg;F.
For all of the tests, the valve opened within of the design set pressure and had stable behavior.
During the 650&deg;F water test, the valve opened at a system pressure within
For those tests in which the system pressure was 6% above the valve design set pressure, the valve achieved a lift position which was 97% of its rated lift. The first two tests were performed with ring positions  
+3% of the valve design set pressure, had stable behavior and closed with 20 .9~~ bl owdown.
(-110, -18) repre-3-83 sentative of typical PWR plant ring positions.
During the 5500F water test, the valve opened at 2526 psia and chattered.
The valve opened, had stable behavior and closed with a blowdown range of 15.1 to 16.6%. Both tests were high back pressure tests. In order to reduce the valve bJowdown, the ring positi*ons were changed two during the subsequent steam tests. The last ring position (-40, -18) resulted in a blowdown of 9.6% and 9.8% for high and low back pressures, respectively.
The test was terminated after the valve was manually opened to stop the chat te'ri ng.
The last ring position was used during the subsequent transition and water tests. Transition Test One low ramp rate, high back pressure, steam-to-water transition test was performed.
3-84
The valve had stable behavior during the four actuations of this transition test. During the initial actuation, the valve opened at a system pressure within of valve design set pressure and closed with 8.6% blowdown.
During the subsequent actuations,!
the opening pressure range was 2420 -2480 psia and the closing range was 2120 -2305 psi a. Water Tests Two high back pressure water tests were performed at nominal of 650&deg;F and 550&deg;F. During the 650&deg;F water test, the valve opened at a system pressure within +3% of the valve design set pressure, had stable behavior and closed with 20 bl owdown. During the 5500F water test, the valve opened at 2526 psia and chattered.
The test was terminated after the valve was manually opened to stop the chat te'ri ng. 3-84 ' *, * * * 
' . *
* After the 55QOF water test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected.
* After the 55QOF water test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected.
Galled guiding surfaces and several damaged internal parts were found. For all other inspections, the typical wear pattern was scratches or marks on the seat surfaces.
Galled guiding surfaces and several damaged internal parts were found.
The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat 3-85
For all other inspections, the typical wear pattern observ~d was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage~
* Valve Descr{ption Manufacturer Type Model No. EPRI/CE SAFET E TEST PROGRAM TABLE 3.6. l.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)
* 3-85
Crosby Valve and Gage Company Spring Loaded Safety Valve Inlet P*iping Configuration "H" Length, in. HB-BP-86 6N8 Nozzle 17
* EPRI/CE SAFET     E TEST PROGRAM TABLE 3.6. l.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)
* I.D., in. 6.813 Serial No. Drawing No. N61894-00-0006 Crosby DSC-61894 Rev. D Venturi Not Applicable Body Size (inlet/outlet) 6 in./ Bore Area 4.381 in.2 --"'---8 in. Orifice Designation N Design Set Point Pressure 2485 psig Design Bl owdown _ __,5=--_.percent Rated Flow 504,952 lb/hr. Rated Lift a 591 in. Internals Type: Steam Ring Setting Reference Position:
Valve Descr{ption Inlet P*iping Configuration "H" Manufacturer                                                                      Length, in. I.D., in.
The ring setting position refers to the number of notches relative to the bottom of the disc ring. Pipe 9 6.813 Reducer 6 6 .813/5 .189 Pipe 76 5.189 Inlet Flange 7 5.189 w I 00 \.0 EPRl/CE SA LVE TEST DATA TABLE 3.6.1.b "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)
Type                  Crosby Valve and Gage Company Spring Loaded Safety Valve          Nozzle Model No.            HB-BP-86     6N8                                               17               6.813 Serial No.           N61894-00-0006 Drawing No.                                                Venturi                      Not Applicable Crosby DSC- 61894 Rev. D Body Size (inlet/outlet)       6     in./                   Pipe                      9 8  in.                                                    6.813 Bore Area 4.381 in.2 --"'---
TEST TEST VALVE RING INLET CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS NO. TYPE UPPER *1202 Steam -110 1203 Steam -110 1205 Steam -75 1207 Steam -40 1208 Steam -40
Orifice Designation         N                               Reducer                    6                6 .813/5 .189 Pipe                      76              5.189 Design Set Point Pressure     2485   psig Inlet Flange              7              5.189 Design Bl owdown _ __,5=--_.percent Rated Flow 504,952 lb/hr.     Rated Lift   a 591 in.
* l 209a TRANS -40 b c d 1211 Water -40 *1213 Water -40 N/A Not aprlicable NOTES: SETTINGS MIDDLE LOWER 18 18 18 18 PIPING IN TANK 1 CONFIG. FLUID PRESS. TEMP. (PSIA) (OF) H Steam 2487 (1) H Steam 2450 (1) H Steam 2472 (1) H Steam 2484 ( 1 ) H Steam 2445 ( l) H Steam/ 2466 (1) Water Steam/ Water Steam/ Water Steam/ Water H Water 2450 635 H Hater 2526 549 AT VALVE INLET PEAK PEAK INDUCED (2) TANK l BACK-BENDING MOMENT PRESS. RATE* FLUID TEMP. PRESS. PRESS. OPEN ING/CLOS I NG (PSI/SEC)  
Internals Type:     Steam Ring Setting Reference Position:
(')r l ( PSIA) (rSIA) (IN. LBS.) 2.0 STEAM ( 1 ) 2487 388 527,800 286 STEAM (1) 2680 500 682,500 317 STEAM (1) 2635 546 254,800 317 STEAM (l) 2674 560 655,200 *325 STEAll. (1) 2640 200 473,200 2.6 STEAM (1) 2466 398 518, 700 5. 1 STEAM (1) 2455 402 5.0 STEAM (l) 2480 420 5.3 STEAM (1) 2420 572 4.6 l*/ater 621 2450 525 591,500 3. 1 Hater 536 2605 318 518,700 (1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests, the initiation temperature was the saturation temoerature.  
The ring setting position refers to the number of notches relative to the bottom of the disc ring.
(2) The reported values are the maximum indur.ed be:1dino mnrnent.s on the valve discharge flanqe <111rino openinn nr closinri.  
 
(3) Because of the inlet configuration used for this test series valve flow rate was not  
EPRl/CE SA           LVE TEST DATA TABLE 3.6.1.b "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)
-*The valve was disassembled, inspected, and refurbished as required for representative test performance.
TEST     TEST                                                       CONDITIONS AT VALVE OPENING                                   TRANSIENT CONDITIONS VALVE RING          INLET NO. TYPE         SETTINGS         PIPING                       IN TANK 1                       AT VALVE INLET   PEAK     PEAK     INDUCED (2)     MAX. STEADY UPPER MIDDLE LOWER      CONFIG. FLUID                                                              TANK l   BACK- BENDING MOMENT     LIQUID FLOW PRESS. TEMP.      PRESS. RATE* FLUID         TEMP. PRESS. PRESS. OPEN ING/CLOS I NG (PSIA)      (OF)      (PSI/SEC)                 (')r l (GPM)
* MAX. STEADY LIQUID FLOW (GPM) N/A N/A N/A N/A N/A (3) (3) (3)
( PSIA)   (rSIA)       (IN. LBS.)
* PRE-HST VAL VE LEAKAGE TEST TEST MEDIA NO. TYPE 1202 Steam Steam i203 Steam Steam 1205 Steam Steam 1207 Steam Steam 1208 Steam Steam 1209a Steam w b I \.Q ._. c d 1211 Water Water 1213 Water Water N/A Not applicable NOTES: NOMINAL flOMINAL VALVE VALVE LEAKAGE INLET INLET RATE PRESS. TEMP. (GPM) (PSIA) (OF) 2280 SAT 0. 1 2290 SAT 0.06 2275 SAT 0.09 2300 SAT 0.6 2290 SAT 0.48 2278 SAT 0.1 (2) (2) (2) 2300 558 0.0 EPRl/CE TEST DATA TA .6.1.c VALVE TRANSIENT PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)
    *1202 Steam -110                -18      H      Steam      2487      (1)            2.0         STEAM     ( 1)     2487     388         527,800           N/A 1203 Steam -110                -18      H      Steam      2450      (1)            286         STEAM     (1)     2680     500         682,500           N/A 1205 Steam - 75                -18      H      Steam      2472        (1)            317         STEAM     (1)     2635     546         254,800           N/A 1207 Steam - 40                -18      H      Steam      2484        (1 )          317         STEAM     (l)     2674     560         655,200         N/A 1208 Steam - 40                -18        H      Steam      2445        ( l)        *325         STEAll.   (1)     2640     200         473,200         N/A
VALVE OPENING AND CLOSING -TA/fl( 1 INITIAL OPENING OPENING OPENING PRESS. OPENING "POP" SIMMER "POP" AT VALVE % SLOWDOWN PRESS. PRFSS. rIME TIME CLOSURE _i!>SIAJ__(_P_s_!jl.J
* l 209a TRANS - 40              -18        H      Steam/    2466        (1) w                                                                                          2.6         STEAM     (1)     2466     398         518, 700 I                                                    Water                                                                                                      (3) 00
_ _J_S_E_Cj
\.0        b Steam/                              5. 1         STEAM     (1)
___ (PSIA) 2487 2487 0.012 0.008 2124 15. 1 2450 2452 0.010 0.008 2088 16.6 2470 2474 0.010 0. 010 14.3 2484 2486 0.009 0.016 22151 9.6 2445 2447 0.012 0.009 22!j6 9.8 2466 2466 0.009 0.010 22B6 8.6 2455 2282 8.8 2480 2305 7.8 2420 2120 15.3 2450 2450 0. 011 0.016 1980 20.9 2526 2526 0.009 .. N/A ( 1 ) ( 1 ) (1) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.  
Water                                                                2455     402 c                                          Steam/                              5.0         STEAM     (l)     2480     420 Water d
Steam/                              5.3         STEAM     (1)     2420 Water                                                                        572 1211    Water - 40            -18      H      Water      2450      635            4.6         l*/ater   621     2450     525         591,500           (3)
    *1213 Water - 40                -18      H      Hater      2526      549            3. 1         Hater     536     2605     318         518,700           (3)
N/A Not aprlicable NOTES:
(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests, the initiation temperature was the saturation temoerature.
(2) The reported values are the maximum indur.ed be:1dino mnrnent.s on the valve discharge flanqe <111rino openinn nr closinri.
(3) Because of the inlet configuration used for this test series valve flow rate was not me~sured.                                -
          *The valve was disassembled, inspected, and refurbished as required for representative test performance.
* EPRl/CE SA~*LVE TA TEST DATA
                                                                                              .6.1.c VALVE TRANSIENT PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)
PRE-HST VAL VE LEAKAGE                                    VALVE OPENING AND CLOSING NOMINAL flOMINAL                                                                                                POST~TEST VALVE LEAKAGE VALVE                                                                      -TA/fl( 1                       -*----NOM f NAL -Nor~ lNAL___ --- -
VALVE  LEAKAGE  INITIAL     OPENING OPENING           OPENING TEST      TEST    MEDIA    INLET    INLET                                                                PRESS.                                 VALVE VALVE LEAKAGE RATE  OPENING         "POP"       SIMMER         "POP"   AT VALVE % SLOWDOWN NO. TYPE              PRESS. TEMP.    (GPM)                                                                          VALVE    MEDIA    INLET  INLET      RATE PRESS.       PRFSS.       rIME         TIME   CLOSURE             STAB!LiTY            PRESS.            (GPM)
(PSIA)    (OF)                                                                                                                  TEMP.
_i!>SIAJ__(_P_s_!jl.J_ _J_S_E_Cj ___~E_C_l__ (PSIA)                                         (PSIA)    (OF) 1202    Steam  Steam    2280        SAT      0. 1    2487         2487       0.012         0.008     2124       15. 1   Stable    Steam 2290        SAT i203 0.06 Steam  Steam    2290      SAT      0.06    2450         2452       0.010         0.008     2088       16.6     Stable    Steam  2290    SAT        0 1205    Steam  Steam    2275      SAT      0.09    2470         2474       0.010         0. 010     21*~4      14.3   Stable    Steam  2280    SAT      0. 01 1207    Steam  Steam    2300      SAT      0.6      2484         2486       0.009         0.016     22151       9.6   Stable    Steam  2290    SAT      0.48 1208    Steam  Steam    2290      SAT      0.48    2445         2447         0.012         0.009     22!j6         9.8   Stable    Steam  2278    SAT      0.1 1209a    TRAl~S  Steam    2278      SAT      0.1    2466         2466       0.009         0.010     22B6         8.6   Stable    Steam  2280    SAT      0.0 w        b I
\.Q                                                                      2455                                 2282         8.8   Stable c
2480                                 2305         7.8   Stable d
2420                                 2120       15.3     Stable 1211    Water  Water    (2)        (2)      (2)    2450           2450       0. 011       0.016     1980       20.9     Stable    Water  2275    SAT      0.0 1213    Water  Water    2300      558      0.0                                      ..
2526           2526       0.009         N/A       (1)         (1 )     Chatter  (2)    (2)      (2)      (2)
N/A Not applicable NOTES:
(1) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.
(2) No measurement was taken.
(2) No measurement was taken.
* VALVE LEAKAGE -*----NOM f NAL lNAL ___ ----VALVE VALVE LEAKAGE VALVE MEDIA INLET INLET RATE STAB!LiTY PRESS. TEMP. (GPM) (PSIA) (OF) Stable Steam 2290 SAT 0.06 Stable Steam 2290 SAT 0 Stable Steam 2280 SAT 0. 01 Stable Steam 2290 SAT 0.48 Stable Steam 2278 SAT 0.1 Stable Steam 2280 SAT 0.0 Stable Stable Stable Stable Water 2275 SAT 0.0 Chatter (2) (2) (2) (2)
* EPRl/CE SA        LVE TEST DATA TABLE 3.6.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)
* EPRl/CE SA LVE TEST DATA TABLE 3.6.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)
CONDITIONS AT 3% ACCUMULATION ( 1)                     CONDITIONS AT 6% ACCUMULATION ( 1)                 LIQUID FLOW MEASUREMENT BASED ON                  BASED ON                  BASED ON TANK PRESSURE      VALVE INLET PRESSURE                                            BASED ON TEST      TEST   %RATED                                                  TANK PRESSURE        VALVE INLET PRESSURE        . TANK CONDITIONS
CONDITIONS AT 3% ACCUMULATION ( 1) CONDITIONS AT 6% ACCUMULATION ( 1) LIQUID FLOW MEASUREMENT BASED ON BASED ON BASED ON BASED ON TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE . TANK CONDITIONS TEST TEST % RATED % RATED % RA1 ED % RATElJ % RATED % RATED % RATED % RATED --pJlEss.
                                          % RATED    %RA1 ED      % RATElJ      % RATED      %RATED      % RATED STEADY NO.      TYPE      LIFT          STEAM      LIFT.        STEAM
TEMP. NO. TYPE LIFT STEAM LIFT. STEAM L !FT STEAM LIFT STEAM (PSIA) (OF) FLOW FLOW FLOW FLOW 1202 Stearn N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1203 Stearn 96 (2) (2) (2) 97 (2) (2) (2) N/A N/A 1205 Stearn 97 (2) (2) (2) (3) (2) (2) (2) N/A N/A 1207 Stearn 96 (2) (2) (2) 97 (2) (2) (2) N/A N/A 1208 Stearn 97 (2) (2) (2) (3) (2) (2) (2) N/A N/A 1209 TRANS N/A N/A N/A N/A N/A N/A N/A N/A (2) (2) w I ID 1211 Water N/A N/A N/A N/A N/A N/A N/A N/A (2) (2) w 1213 Water N/A N/A N/A N/A N/A N/A N/A N/A (2) (2) N/A Not applicable NOTES: (1) During valve closing cycle. (2) Because of the inlet configuration flow was not measured.
                                                                                                                        % RATED       --pJlEss. TEMP.      LIQUID  % RATED L !FT        STEAM        LIFT         STEAM           (PSIA)   (OF)       FLOW FLOW                     FLOW                         FLOW                                                                 LIFT FLOW                               (GPM) 1202     Stearn   N/A           N/A       N/A           N/A           N/A           N/A       N/A         N/A             N/A       N/A      N/A      N/A 1203     Stearn   96           (2)       (2)           (2)           97             (2)       (2)         (2)             N/A       N/A      N/A      N/A 1205     Stearn   97           (2)       (2)           (2)           (3)           (2)       (2)         (2)             N/A       N/A      N/A      N/A 1207     Stearn   96           (2)       (2)           (2)           97             (2)       (2)         (2)             N/A      N/A      N/A     N/A 1208     Stearn   97           (2)       (2)           (2)           (3)           (2)       (2)         (2)             N/A       N/A      N/A      N/A 1209     TRANS     N/A           N/A       N/A           N/A             N/A           N/A       N/A         N/A w                                                                                                                                        (2)       (2)       (2)      (2)
This precfoded determination of valve inlet conditions.  
I ID w        1211     Water   N/A           N/A       N/A           N/A             N/A           N/A       N/A         N/A             (2)       (2)      (2)      (2) 1213       Water   N/A           N/A       N/A           N/A             N/A           N/A       N/A         N/A             (2)      (2)       (2)       (2)
(3) The appropriate measurement conditions were not achieved.
N/A Not applicable NOTES:
STEADY LIQUID FLOW (GPM) N/A N/A N/A N/A N/A (2) (2) (2) % RATED LIFT N/A N/A N/A N/A N/A (2) (2) (2)
(1) During valve closing cycle.
* 3.7 TARGET ROCK CORPORATION SAFETY VALVE MODEL 69C 3.7.l Valve Description and Inlet Piping Configuration, 11 As Tested 11 Test Matrix and Valve Performance Data Tests were performed on the Target Rock 69C safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility.
(2)   Because of the inlet configuration flow was not measured.       This precfoded determination of valve inlet     sta~nation  conditions.
The valve was tested on a long (test series 700, configuration I) inlet piping configuration.
(3)   The appropriate measurement conditions were not achieved.
The following is the list of tables that contain safety valve information/data for these tests: Table Description Safety Valve Description arid Inlet Piping Configuration "As Tested 11 Test Matrix Valve Transient and Leakage Performance Data Valve Flow Rate Performance Data 3.7.2 Principal Observations Table Number 3.7.1.a 3.7.1.b 3.7.1.c 3.7.1.d A total of nine tests were performed with the Target Rock 69C pilot operated safety valve mounted on a long inlet pipe configuration.
 
The principal observations for these tests are as follows: Steam Tests Two high ramp rate steam tests were performed with high and low back pressures.
3.7  TARGET ROCK CORPORATION SAFETY VALVE MODEL 69C 3.7.l Valve Description and Inlet Piping Configuration,  11 As Tested Test Matrix 11 and Valve Performance Data Tests were performed on the Target Rock 69C safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The valve was tested on a long (test series 700, configuration I) inlet piping configuration. The following is the list of tables that contain t~e safety valve information/data for these tests:
For these high ramp rate tests, the pilot disc opened within +3% of the valve design set pressure and the main disc opened at pressures of 2612 and 2630 psia. The valve exhibited stable performance and closed with less than 4% blowdown.
Table Description                                    Table Number Safety Valve Description arid Inlet Piping Configuration                                         3.7.1.a "As Tested Test Matrix 11 3.7.1.b Valve Transient and Leakage Performance Data           3.7.1.c Valve Flow Rate Performance Data                        3.7.1.d
When the system pressure accumulated to 6% above the valve design set pressure, rated flow was achieved.
* 3.7.2  Principal Observations A total of nine tests were performed with the Target Rock 69C pilot operated safety valve mounted on a long inlet pipe configuration. The principal observations for these tests are as follows:
3-95 Loop Seal Steam Tests Two high back pressure loop seal-steam tests were performed at high and low ramp rates. For the low ramp rate test, the valve cycled opened and closed a total of eight times in response to system repressurizations.
Steam Tests Two high ramp rate steam tests were performed with high and low back pressures. For these high ramp rate tests, the pilot disc opened within
For the initial actuation cycle, the pilot disc and the main disc opened within of the valve design set pressure, exhibited stable performance and closed with 4.9% blowdown.
        +3% of the valve design set pressure and the main disc opened at pressures of 2612 and 2630 psia. The valve exhibited stable performance and closed with less than 4% blowdown. When the system pressure accumulated to 6%
In the subsequent actuations, the pilot disc and main disc opened and closed at generally decreasing pressures down to minimum opening and closing pressures of 2390 and 2325 psia, respectively.
above the valve design set pressure, rated flow was achieved.
Valve performance was stable for all cycles. For the high ramp rate test, the pilot disc opened within +3% of the valve design set and the main disc opened at a pressure of 2610 psia. The valve ex1ioited stable performance and closed with 8.5% blowdown.
3-95
When the system pressure accumulated to 6% above the valve design set pressure, rated flow was achieved.
 
Transition Test In the loop seal-steam-to-water transition test, the valve cycled opened and closed twice. For the first cycle, the valve opened on the loop seal and closed on steam with performance similar to the low ramp rate loop seal-steam test performance.
Loop Seal  ~ Steam Tests Two high back pressure loop seal-steam tests were performed at high and low ramp rates. For the low ramp rate test, the valve cycled opened and closed a total of eight times in response to system repressurizations. For the initial actuation cycle, the pilot disc and the main disc opened within ~3%
The system repressurized and the valve pilot disc and main disc opened on steam with performance similar to the low ramp rate steam test performance, had stable performance and closed on water with 12.5% blowdown.
of the valve design set pressure, exhibited stable performance and closed with 4.9% blowdown. In the subsequent actuations, the pilot disc and main disc opened and closed at generally decreasing pressures down to minimum opening and closing pressures of 2390 and 2325 psia, respectively.
Water Tests Four cold loop seal-water tests were performed at nominal water atures of 6S0&deg;F, 550bF and 4000F (2 tests). For the initial actuation cycle of each test, the pilot disc and main disc opened within of the valve design set pressure and closed with 3.1 to 23.7 blowdowns.
Valve performance was stable for all cycles.
In the 550&deg;F water test, the valve open and closed seven additional times in response to system repressurization with opening pressures of 2390-2466 psia and closing pressures of 2245-2390 psia. 3-96 * 
For the high ramp rate test, the pilot disc opened within +3% of the valve design set ~ressure and the main disc opened at a pressure of 2610 psia.
' ' *
The valve ex1ioited stable performance and closed with 8.5% blowdown. When the system pressure accumulated to 6% above the valve design set pressure, rated flow was achieved.
* Based on upstream pressure data, the valve fluttered during all of the water tests. Valve Inspection Results The valve was disassembled and inspected twice. The first inspection occurred after the water tests were completed.
Transition Test In the loop seal-steam-to-water transition test, the valve cycled opened and closed twice. For the first cycle, the valve opened on the loop seal and closed on steam with performance similar to the low ramp rate loop seal-steam test performance. The system repressurized and the valve pilot disc and main disc opened on steam with performance similar to the low ramp rate steam test performance, had stable performance and closed on water with 12.5% blowdown.
For this inspection, it was observed that the main disk shaft had bowed and that there was scoring of the piston and piston ring. A new valve was used for the final two steam tests rather than refurbishing the existing test valve. The inspection of the second test valve occurred after the two steam tests were completed.
Water Tests Four cold loop seal-water tests were performed at nominal water tempe~
No wear was observed . 3-97 EPRI/CE SAFETY -TEST PROGRAM TABLE 3 .. 7.1.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE TARGET ROCK 69C Valye Description Manufacturer Type Model No. (1) Serial No. Drawing No. Target Rock Pilot Operated Safety Valve 69C 4,5 69C-OOO Rev. 07 Body Size (inlet/outlet) 6 in./ 6 in. Bore Area 3.513 in.2 ----Orifice Designation Not Applicable Design Set Point Pressure _24_8_5 _ __,psig Inlet Piping Configuration Length, in. Nozzle 17 Venturi 38 Pipe 33 Reducer 6 Loop Seal Straight 60 Bends 2-1800 Design Slowdown 5 percent <.O Inlet Flange 7 <.O Rated Flow 345,000 lb/hr. Rated Lift Not Applicable Internals Type: Not Applicable
atures of 6S0&deg;F, 550bF and 4000F (2 tests). For the initial actuation cycle of each test, the pilot disc and main disc opened within +/-_35~ of the valve design set pressure and closed with 3.1 to 23.7 blowdowns.
* I.D., in. 6.813 6.813 6.813 6.813/4.897 4.897 9 in. radius 4 .897 (1) Valve serial no. 4 was used for all tests except 722 and 723. Valve serial no. 5 was used for tests 722 and 723.
In the 550&deg;F water test, the valve ~ycled open and closed seven additional times in response to system repressurization with opening pressures of 2390-2466 psia and closing pressures of 2245-2390 psia.
w I ...... 0 ......
3-96
 
Based on upstream pressure data, the valve fluttered during all of the water tests.
Valve Inspection Results The valve was disassembled and inspected twice. The first inspection occurred after the water tests were completed. For this inspection, it was observed that the main disk shaft had bowed and that there was scoring of the piston and piston ring. A new valve was used for the final two steam tests rather than refurbishing the existing test valve. The inspection of the second test valve occurred after the two steam tests were completed.
No wear was observed .
* 3-97
 
EPRI/CE SAFETY TABLE
                                                                        - TEST PROGRAM 3.. 7.1.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE TARGET ROCK 69C Valye Description                                                    Inlet Piping Configuration Length, in.      I.D., in.
Manufacturer      Target Rock                                        Nozzle                17 Type                                                                                                          6.813 Pilot Operated Safety Valve Model No. (1)      69C                                                Venturi              38              6.813 Serial No.        4,5 Drawing No.       69C-OOO Rev. 07                                    Pipe                  33              6.813 Body Size (inlet/outlet)      6    in./    6    in.              Reducer                6              6.813/4.897 Bore Area 3.513 in.2                      ----
Orifice Designation Not Applicable                                    Loop Seal Straight          60              4.897 Design Set Point Pressure _24_8_5_ __,psig                                Bends          2-1800        9 in. radius
~    Design Slowdown      5    percent                                    Inlet Flange            7              4 .897
<.O                    ---~
<.O Rated Flow 345,000   lb/hr. Rated Lift Not Applicable Internals Type:     Not Applicable (1) Valve serial no. 4 was used for all tests except 722 and 723.       Valve serial no. 5 was used for tests 722 and 723.
* EPRI/CE SAFE.E TEST DATA TABLE 3.7.l.b "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE
* EPRI/CE SAFE.E TEST DATA TABLE 3.7.l.b "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE
* TARGET ROCK 69C TEST TEST VALVE RING INLET CONDITIONS AT VAL VE OPEN ING TRANSIENT CONDITIONS NO. TYPE UPPER *703 a LS N/A b c d e f g h 706 LS N/A 709 a LS N/A TRANS b 712 water N/A N/A Not applicable NOTES: SETTINGS MIDDLE LOWER N/A N/A N/A N/A N/A N/A N/A N/A PIPING IN TANK 1 CONFIG. FLU ID PRESS. TEMP. (PSIA)(3) (OF) steam 2543 (l) steam 2562 steam 2503 steam 2472 steam 2445 steam 2430 steam 2415 steam 2390 steam 2610 ( l) steam/ 2508 (l) water steam/ 2474 water water 2486 613 AT VALVE INLET PEAK PEAK TANK 1 BACK-PRESS. RATE FLUID TEMP. PRESS. PRESS. (PSI/SEC) (OF) (PSIA) ( PSIA) 2.7 water 90 2543 380 4. l steam (l) 2562 330 20.6 steam (l) 2503 320 2.2 steam (l) 2472 270 5.0 steam (l) 2445 280 3.9 steam (l) 2430 270 3.1 steam ( l ) 2415 270 0.0 steam ( l ) 2390 135 300 water 93 2713 482 2.0 water 97 2508 270 3.4 steam (l) 2474 617 2.8 water 118 2486 500 (1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation (2) The reported values are the maximum induced bending moments on the valve discharge flange durina opening or closing. (3) The main disc opening pressures ar* reported under Tank l conditions at valve openina.
* TARGET ROCK 69C TEST   TEST                                                         CONDITIONS AT VAL VE OPEN ING VALVE RING        INLET                                                                                    TRANSIENT CONDITIONS NO. TYPE         SETTINGS         PIPING                         IN TANK 1                     AT VALVE INLET  PEAK    PEAK    INDUCED (2)    MAX. STEADY UPPER MIDDLE LOWER    CONFIG. FLU ID                                                             TANK 1  BACK-    BENDING MOMENT LIQUID FLOW PRESS. TEMP.      PRESS. RATE FLUID        TEMP. PRESS.
(PSIA)(3) (OF)                                                   PRESS. OPENING/CLOSING    (GPM)
(PSI/SEC)               (OF)   (PSIA)   ( PSIA)     (IN. LBS.)
      *703 a LS        N/A    N/A      N/A              steam      2543        (l)          2.7         water     90   2543     380         143,750        N/A b                                            steam      2562                      4. l         steam       (l) 2562     330 c                                            steam      2503                    20.6         steam     (l)   2503     320 d                                            steam      2472                      2.2         steam     (l)   2472     270 e                                            steam      2445                      5.0         steam     (l)   2445     280 w          f                                            steam        2430 I                                                                                            3.9         steam       (l)   2430     270
......      g 0
......                                                  steam      2415                      3.1         steam       (l ) 2415     270 h                                            steam      2390                      0.0         steam       (l ) 2390     135 706    LS      N/A    N/A      N/A              steam      2610        ( l)          300         water     93   2713     482         230,000        N/A 709 a LS        N/A    N/A      N/A              steam/      2508        (l)          2.0         water     97   2508 TRANS                                    water                                                                        270         258,750        N/A b                                            steam/      2474                      3.4         steam     (l)   2474     617 water                                                                                                    2540 712    water    N/A    N/A      N/A            water        2486        613          2.8         water     118   2486     500          80,500       1873 N/A Not applicable NOTES:
(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation te~perature.
(2) The reported values are the maximum induced bending moments on the valve discharge flange durina opening or closing.
(3) The main disc opening pressures ar reported under Tank l conditions at valve openina.
* The valve was disassembled, inspected, and refurbished as required for representative test performance.
* The valve was disassembled, inspected, and refurbished as required for representative test performance.
INDUCED (2) BENDING MOMENT OPENING/CLOSING (IN. LBS.) 143,750 230,000 258,750 80,500 MAX. STEADY LIQUID FLOW (GPM) N/A N/A N/A 2540 1873 w I I-' 0 w
* EPR!/CE  SAFET~ TEST DATA TABLE 3.7.1.b (Con't)
* EPR!/CE TEST DATA TABLE 3.7.1.b (Con't) "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE TARGET ROCK 69C CONDITLONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST NO. TYPE UPPER 714 a water N/A b c d e f g h 717 water N/A *719 water N/A *722 steam N/A *723 steam N/A N/A Not applicable NOTES: VALVE RING SETTINGS MIDDLE N/A N/A N/A N/A N/A INLET IN PIPING LOWER CONFIG. FLUID PR[SS.(3) (PSIA) N/A water 2464 water 2433 water 2466 water 2450 water 2424 water 2411 water 2396 water 2390 N/A water 2490 N/A water 2487 N/A steam 2612 N/A steam 2630 TANK 1 AT VALVE INLET PEAK PEAK TANK l BACK-TEMP. PRE SS. RATE FLU ID TEMP. PRESS. PRESS. (OF) (PSI/SEC) (OF) (PSJA) (PSIA) 568 2.2 water 97 2464 87 4.2 water 540 2433 90 5.0 water 510 2466 265 7.0 water 530 2450 380 8.0 water 540 2424 405 7.5 water !i42 2411 420 6.7 water 550 2396 410 2.7 water 2390 380 410 2.6 water 82 2490 215 397 0.7 water 83 2487 146 (l) 311 steam ( 1 ) 2678 430 (1) 307 steam (1) 2674 63 (1) All tests were initiated at a nomin;il pre>sure of 2300 PSJA. For steam tests and stean11water transition tests, the initiation temperature was the saturation temperature.  
                                                          "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE TARGET ROCK 69C CONDITLONS AT VALVE OPENING                              TRANSIENT CONDITIONS TEST    TEST         VALVE RING        INLET                      IN TANK 1                                   PEAK      PEAK    INDUCED (2)       MAX. STEADY NO. TYPE                                                                                    AT VALVE INLET SETTINGS        PIPING                                                                  TANK l    BACK-  BENDING MOMENT    LIQUID FLOW UPPER MIDDLE LOWER    CONFIG. FLUID    PR[SS.(3) TEMP.      PRE SS. RATE  FLU ID    TEMP. PRESS. PRESS. OPENING/CLOSING      (GPM)
(2) The reported values are the induced bending moments on the valve flange during opening or closinq. (3) The main disc opening pressures are reported under Tank l conditions at valve opening. INDUCED (2) BENDING MOMENT OPENING/CLOSING (IN. LBS.) 201 ,250 58,650 74 '750 54,625 54,625
(PSIA)      (OF)      (PSI/SEC)              (OF)  (PSJA)    (PSIA)      (IN. LBS.)
* MAX. STEADY LIQUID FLOW (GPM) 2575 2041 1501 N/A N/A *The valve was disassembled, inspected, and refurbished as required for representative test performance.
714 a  water     N/A   N/A     N/A             water    2464      568          2.2        water     97  2464       87        201 ,250 b                                            water     2433                     4.2        water   540    2433        90 c                                            water    2466                     5.0        water   510    2466      265 d                                            water    2450                     7.0        water    530    2450      380 e                                            water    2424                    8.0        water   540    2424       405                          2575 f                                            water     2411                     7.5        water   !i42  2411      420 w
For tests 722 and 723 valve serial number 4 was replaced with serial number 5.
I g                                            water     2396                    6.7        water   550    2396      410 I-'
EPR!/CE SAF E TEST DATA . c VALVE TRANSIENT ANn I FAkAGF PFPFnRMBHrF nnrn rnD THE TARGET ROCK 69C PRE-TEST VALVE LEAKAGE VALVE OPENING AND CLOSING -t*iuMtNAC-
0        h                                            water    2390                    2.7        water    ~;47  2390      380 w
____ ------------------
717    water    N/A    N/A    N/A             water    2490      410            2.6        water      82  2490      215          58,650          2041
TANK 1 VALVE VALVE LEAKAGE INITIAL(2)
    *719    water    N/A    N/A    N/A              water    2487      397            0.7        water      83  2487      146          74 '750        1501
OPENING (3bPENING OPENING PRESS. TEST TEST MEDIA INLET INLET RATE OPENING "POP" SIMMER "POP" AT VALVE NO. TYPE PRESS. TEMP. (GPM) PRESS. PRESS. f IME TIME CLOSURE (PS!A) (Of)
    *722    steam    N/A    N/A    N/A              steam    2612        (l)           311        steam      (1) 2678      430          54,625          N/A
_____ j_S_E_Cj ___
    *723    steam    N/A    N/A    N/A              steam    2630        (1)          307        steam      (1) 2674        63          54,625          N/A N/A Not applicable NOTES:
703a LS water 2300 98 a.a 2541 2543 b 2562 c 2503 d 2472 w e 2445 I ...... 0 f 2430 U1 g 2415 h 2390 706 LS water 2283 116 0.0 2510 2610 709a LS TRANS water 2303 lll 0.0 2507 2508 b 2474 712 water water 2286 119 0.0 2485 2486 N/A Not applicable NOTES: (1) No measurement was taken. (2) The Initial Opening Pressure is reported for the pilot valve opening. (3) The Opening Pop Pressure is reported for the main disc opening. (4) Valve stability was inferred from the inlet pressure stability.
(1) All tests were initiated at a nomin;il pre>sure of 2300 PSJA. For steam tests and stean11water transition tests, the initiation temperature was the saturation temperature.
D.21 (1) 2378 2444 2400 2374 2350 2338 2325 2332 0.33 (1) 2290 0.39 (1) 2390 2190 0.25 (1) 2191 % SLOWDOWN 4.9 2.3 4.0 5.1 6.0 6.5 7.0 6.8 8.5 4.4 12.5 12.5 POsT:.TEST VALVE LEAKAGE NOMINAC!;'G'l!NAL-
(2) The reported values are the induced bending moments on the valve dischar~e flange during opening or closinq.
-----VALVE VALVE LEAKAGE VALVE (4) MEDIA INLET INLET RATE S l Al:llll TY PRESS. ii:_Nf'. (G<'l*I) (PSIA) (OF) stable steam 2300 SAT 0.0 stable stable stable stable stable stable stable stable steam 2300 SAT 0.0 stable water 2294 386 0.fl stable flutter water (1) 519 0.0 EPRl/CE TABLE TEST DATA l.c (Can't) VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE TARGET ROCK 69C PRE-TE
(3) The main disc opening pressures are reported under Tank l conditions at valve opening.
_., _____________
            *The valve was disassembled, inspected, and refurbished as required for representative test performance.      For tests 722 and 723 valve serial number 4 was replaced with serial number 5.
NOMINAL NOMINAL TANK 1 VALVE VALVE LEAKAGE INITIAL(2)
 
OPENING OPENING PRESS. TEST TEST MEDIA INLET INLET RATE OPENING "POP" SIMMER "POP" AT VALVE NO. TYPE PRESS. TEMP. (GPM) PRESS. PRESS. f !ME TIME CLOSURE (OF) (PSIAJ_{J.>_sm
EPR!/CE SAF        E TEST DATA
__ _J_S_E_0 __ ___j_S_E_CJ
                                                                                                .c VALVE TRANSIENT ANn I FAkAGF PFPFnRMBHrF nnrn rnD THE TARGET ROCK 69C PRE-TEST VALVE LEAKAGE
__ (!'_?IA) 714a water b c d e w f I ,_. 0 g '.J h 717 water 719 water 722 steam 723 steam N/A Not applicable NOTES: water 2300 water 2300 water 2300 steam 2300 steam 2300 (1) No measurement was taken. 103 0.0 2462 2464 2433 2466 2450 2424 2411 2396 2390 128 0.0 2488 2490 90 0.0 2487 2487 SAT 0.4 2500 2612 SAT *O.O 2505 2630 (2) The Initial Opening Pressure is reported for the pilot valve opening (3) The Opening Pop Pressure is reported for the main disc opening. (4) Valve Stability was inferred from the inlet pressure stability 0.31 (1) 2424 2391 2341 2275 2247 2245 2246 2247 0.70 ( l ) 1910 0.63 (1) 2235 0.37 (1) 2490 0.45 (1) 2410 %
                                -t*iuMtNAC- NDl~llil\l____ - - - - - - - - - - - VALVE  ----  OPENING
3.1 4.4 6.4 9.1 l 0.2 l 0. 3 10. 2 10.2 23.7 10.7 0.4 3.6 POST-TEST VALVE LEAKAGE ----oofftiAL -NOM [ NAC*------, VALVE VALVE LEAKAGE VALVE (4) MEDIA INLET INLET RATE STABILITY PRF.SS. TEMP. (GPM) (PSIA) (OF) fl utter water 2300 442 0.0 fl utter fl utter fl utter flutter flutter fl utter fl utter fl utter water 2300 270 0.0 fl utter water 2300 330 0.0 stable steam 2300 SAT 0.0 stable steam 2300 SAT 0.03 TEST TEST NO. TYPE 703a LS b c d e f w I ....... g 0 l.O h 706 LS 709a LS TRANS b 712 water N/A Not applicable NOTES: EPRI/CE SAFET TEST DATA TABLE 3.7.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE TARGET ROCK 69C CONDITIONS AT 3% ACCUMULATION (1) . CONDITIONS AT 6% ACCUMULATION (1) BASED ON BASED ON BASED ON BASED ON TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE % RATED % RATED % RATED % RATED %RATED % RATED % RATED % RATED LIFT LIFT STEAM LI FT STEAM LIFT FLOW FLOW FLOW FLOW N/A N/A N/A N/A N/A N/A N/A N/A (2) 126 (2) 128 (2) 132 (2) 133 N/A N/A N/A N/A N/A N/A. N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A (1) closing The valve inlet corresponds to stagnation pressure.  
                                                                                                - - - AND CLOSING                              POsT:.TEST VALVE LEAKAGE TANK 1                                    NOMINAC!;'G'l!NAL- -----
(2) The fl'arn disc stem pos*1t1on was not measured for this valve. LIQUID FLOW MEASUREMENT TANK CONDITIONS MAX.STEADY PRESS. TEMP: LIQUID % RATED (PSIA) (OF) FLOW LIFT (GPM) N/A N/A N/A N/A N/A N/A N/A N/A 2320 641 2540 (2) 2335 611 1873 (2)
VALVE    VALVE    LEAKAGE INITIAL(2) OPENING (3bPENING      OPENING    PRESS.                                     VALVE VALVE LEAKAGE TEST       TEST   MEDIA      INLET    INLET    RATE  OPENING     "POP"      SIMMER      "POP"    AT VALVE % SLOWDOWN VALVE (4)                                RATE NO.      TYPE              PRESS.                                                                                                     MEDIA   INLET INLET TEMP.     (GPM)   PRESS.     PRESS.       f IME       TIME   CLOSURE             Sl Al:llll TY          PRESS. ii:_Nf'. (G<'l*I)
TEST TEST NO. TYPE 714a water b c d e f w I g I-" I-" I-" h 717 water 719 water 722 steam 723 steam N/A Not applicable NOTES: EPR !/CE SAFETY EST DATA TABLE 3.7.l.d (Con't) VALVE FLOW RATE PERFORMANCE DATA FOR THE TARGET ROCK 69C CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ACCUMULATION (1) BASED ON BASED ON BASED ON Bl\SED ON TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE % RA1ED % RATED % RAt ED % RATED % RAlED % RATED % RATED. % RATED LIFT STEAM* LIFT STEAM l !FT STEAM LIFT STEAM FLOW FLOW FLOW FLOW N/A N/A N/A N/A N/A N/A N/A N/A a11r. N/A N/A N/A N/A N/A N/A N/A 1*/M N/A N/A N/A N/A N/A N/A N/A N/A (2) 116 (2) 117 (2) 110 (2) 75 (2) 127 (2) 129 (2) 123 (2) 99 (1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.  
(PS!A)   (Of)             ~&___l_P~_I__A_l__J_S_E_Cj _____ j_S_E_Cj___(~S_IA)                                      (PSIA)  (OF) 703a     LS       water     2300     98         a.a     2541       2543         D.21        (1)    2378        4.9      stable      steam    2300  SAT      0.0 b                                                              2562                            2444        2.3      stable c                                                              2503                            2400        4.0       stable d                                                              2472                              2374        5.1      stable w          e                                                              2445 I
(2) The main disc stem position was not measured for this valve. LIQUID FLOW MEASUREMENT AX TANK CONDITIONS STEADY PRESS. TEMP. LIQUID % RATED (PSIA) (OF) FLOW LIFT (GPM) 2340 567 2676 (2) 2340 411 2041 (2) 2390 396 1601 (2) N/A N/A N/A N/A N/A N/A N/A N/A  
......                                                                                                      2350        6.0      stable 0          f                                                              2430 U1                                                                                                           2338        6.5      stable g
., ' Section 4 4.0
2415                             2325        7.0      stable h                                                             2390                             2332        6.8      stable 706     LS       water     2283     116         0.0   2510       2610         0.33        (1)    2290        8.5      stable      steam    2300  SAT      0.0 709a     LS TRANS water     2303     lll               2507 0.0               2508         0.39        (1)    2390        4.4      stable      water    2294  386      0.fl b                                                    2474                                       2190        12.5      stable 712       water   water     2286     119         0.0   2485       2486       0.25          (1)    2191        12.5      flutter      water    (1)    519      0.0 N/A Not applicable NOTES:
(1) No measurement was taken.
(2) The Initial Opening Pressure is reported for the pilot valve opening.
(3) The Opening Pop Pressure is reported for the main disc opening.
(4) Valve stability was inferred from the inlet pressure stability.
 
EPRl/CE  S.l\FET~      TEST DATA TABLE      l.c (Can't)
VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE TARGET ROCK 69C PRE-TE ~_T_'{.81J_~-1=J~KA~_E_., _____________y~_L_V_f___Q_f'_E_N~r:!__G~_i_L 0~1-~G                              POST-TEST VALVE LEAKAGE NOMINAL    NOMINAL                                                        TANK 1                           ----oofftiAL -NOM [ NAC*------,
VALVE      VALVE    LEAKAGE INITIAL(2) OPENING (3~PENING      OPENING    PRESS.                                   VALVE VALVE LEAKAGE TEST      TEST    MEDIA    INLET      INLET    RATE  OPENING      "POP"      SIMMER    "POP"    AT VALVE % BLOl~DO\.IN  VALVE (4) MEDIA   INLET   INLET   RATE NO.      TYPE              PRESS.     TEMP.     (GPM)   PRESS.      PRESS.        f !ME    TIME    CLOSURE                STABILITY          PRF.SS. TEMP. (GPM)
(PSJA~      (OF)             (PSIAJ_{J.>_sm__ _J_S_E_0__ ___j_S_E_CJ_ _(!'_?IA)                                    (PSIA)  (OF) 714a    water    water    2300      103        0.0    2462      2464        0.31        (1)   2424          3.1      fl utter  water    2300    442  0.0 b                                                                2433                            2391          4.4      fl utter c                                                                2466                            2341          6.4      fl utter d                                                                2450                            2275          9.1      fl utter e                                                                2424                            2247        l 0.2      flutter w
I f                                                                2411                            2245        l 0. 3      flutter 0
'.J g                                                                2396                            2246        10. 2      fl utter h                                                                 2390                            2247        10.2        fl utter 717     water     water   2300       128          0.0    2488      2490        0.70        (l )   1910        23.7        fl utter  water    2300    270  0.0 719      water      water    2300        90        0.0   2487       2487         0.63        (1)   2235        10.7        fl utter  water    2300    330  0.0 722      steam    steam    2300      SAT          0.4    2500      2612        0.37        (1)   2490          0.4      stable    steam    2300    SAT  0.0 723      steam    steam    2300      SAT        *O.O    2505      2630        0.45       (1)   2410         3.6       stable    steam    2300    SAT  0.03 N/A Not applicable NOTES:
(1) No measurement was taken.
(2) The Initial Opening Pressure is reported for the pilot valve opening (3) The Opening Pop Pressure is reported for the main disc opening.
(4) Valve Stability was inferred from the inlet pressure stability
 
EPRI/CE SAFET            TEST DATA TABLE 3.7.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE TARGET ROCK 69C CONDITIONS AT 3% ACCUMULATION (1)                    . CONDITIONS AT 6% ACCUMULATION (1)           LIQUID FLOW MEASUREMENT BASED ON                BASED ON                    BASED ON                  BASED ON TANK PRESSURE      VALVE INLET PRESSURE            TANK PRESSURE          VALVE INLET PRESSURE  TANK CONDITIONS    MAX.STEADY TEST    TEST      %RATED      %RATED    %RATED      % RATED        %RATED        %RATED      %RATED      % RATED  PRESS. TEMP:      LIQUID % RATED NO. TYPE      LIFT          ~lEAM    LIFT        STEAM            LI FT        STEAM      LIFT        ~lEAM    (PSIA)   (OF)       FLOW  LIFT FLOW                  FLOW                          FLOW                    FLOW                      (GPM) 703a    LS        N/A            N/A      N/A          N/A            N/A              N/A        N/A      N/A        N/A      N/A      N/A    N/A b
c d
e f
w I
.......     g 0
l.O h
706       LS       (2)            126      (2)          128            (2)            132        (2)        133      N/A      N/A      N/A     N/A 709a  LS TRANS    N/A            N/A      N/A          N/A            N/A            N/A.       N/A        N/A      2320      641      2540    (2) b 712      water    N/A            N/A      N/A          N/A            N/A            N/A        N/A        N/A      2335      611      1873    (2)
N/A Not applicable NOTES:
(1) During.val~e closing cyc~e. The valve inlet pressu~e corresponds to stagnation pressure.
(2) The fl'arn disc stem pos*1t1on was not measured for this valve.
 
EPR !/CE SAFETY          EST DATA TABLE 3.7.l.d (Con't)
VALVE FLOW RATE PERFORMANCE DATA FOR THE TARGET ROCK 69C CONDITIONS AT 3% ACCUMULATION (1)                     CONDITIONS AT 6% ACCUMULATION (1)             LIQUID FLOW MEASUREMENT BASED ON                BASED ON                    BASED ON                  Bl\SED ON TANK PRESSURE      VALVE INLET PRESSURE                                                                                  AX TEST    TEST    %RA1ED                                                  TANK PRESSURE          VALVE INLET PRESSURE  TANK CONDITIONS      STEADY
                                        %RATED    %RAt ED    % RATED        % RAlED      % RATED      % RATED.    % RATED NO. TYPE      LIFT          STEAM*                                                                                PRESS. TEMP.     LIQUID % RATED LIFT        STEAM            l !FT        STEAM        LIFT        STEAM    (PSIA)   (OF)        FLOW FLOW                  FLOW                                                                                        LIFT FLOW                      FLOW                       (GPM) 714a    water  N/A             N/A       N/A         N/A             N/A           N/A         N/A         N/A b
c d
e f
w                                                                                                                                2340      567      2676    (2)
I         g I-"
I-"
I-"       h 717     water   a11r.
1*/M            N/A      N/A          N/A             N/A            N/A        N/A        N/A      2340      411        2041    (2) 719      water  N/A            N/A        N/A          N/A            N/A            N/A        N/A        N/A      2390      396        1601    (2) 722      steam  (2)            116        (2)         117            (2)            110        (2)        75        N/A      N/A      N/A     N/A 723      steam  (2)            127        (2)          129            (2)            123        (2)        99        N/A       N/A       N/A     N/A N/A Not applicable NOTES:
(1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.
(2) The main disc stem position was not measured for this valve.
 
Section 4 4.0  


==SUMMARY==
==SUMMARY==
OF RELIEF VALVE OPERABILITY DATA A total of ten relief valves were tested under steam, water, steam to water sition) and water seal conditions.
OF RELIEF VALVE OPERABILITY DATA A total of ten relief valves were tested under steam, water, steam to water (tran-sition) and water seal conditions.
The ten relief valves selected for testing in the EPRI Program, and the relief valves represented by the valves tested are identified in Section 2.0 of this report. All relief valves testing as part of the EPRI/PWR Safety and Relief Valve Test Program is complete.
The ten relief valves selected for testing in the EPRI Program, and the relief valves represented by the valves tested are identified in Section 2.0 of this report.
The purpose of this section is to present the "as tested" test matrices, valve performance data and principal observations for all relief valves tested. To assist in understanding the overall performance of each of the manufacturer's relief valve designs, refer to the Valve Description section of the "Valve Selection/
All relief valves testing as part of the EPRI/PWR Safety and Relief Valve Test Program is complete. The purpose of this section is to present the "as tested" test matrices, valve performance data and principal observations for all relief valves tested.
Justification Report" (Hcference 1). 4-1
To assist in understanding the overall performance of each of the manufacturer's relief valve designs, refer to the Valve Description section of the "Valve Selection/
. ' 4.1 DRESSER RELIEF VALVE 4.1.1 "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Dresser relief valve model at the Marshall Steam Station and _during Phase II and Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Dresser relief valve tested at each of the test facilities.
Justification Report" (Hcference 1).
Test Facility Marshall Wyl e (Phase II) Wyl e (Phase II I) 4.1.2 Principal Observations Marshall Steam Station "As Tested" Test Matrix Table 4.1.l-la 4.l.l-2a 4.1.1-3a Valve Performance Data Table 4.1.l-lb 4.l.l-2b 4.l.l-3b The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles. During the evaluation tests, steam leaked past the valve pilot stem. Upon valve disassembly, the bellows was found to have several partially failed welds. The valve was reassembled with a new bellows and cycled 16 more times with varying steady state pilot backpressures up to 900 psig. The valve fully opened and closed on demand for each cycle and the bellows did not leak. Upon disassembly, the bellows did not have any visible cracks. In all test cases, the valve fully opened on demand and closed on demand even though the bellows was damaged during some tests. Based on this input and the manufacturer's assessment of valve performance with the observed damage, the damage was determined to have no potential impact on valve npPration.
4-1
4-3 The valve fully opened on demand and fully closed on demand for each of the five (5) test cycles. Wyle Phase III The valve fully opened on demand and fully closed on demand during nine (9) of the twelve (12) tests performed.
 
The valve fully opened on demand and did not close on demand during the three (3) water seal simulation tests; number 16-DR-6W, 2?-DR-9W/W and 24-DR-6W.
4.1   DRESSER RELIEF VALVE 4.1.1 "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Dresser relief valve model at the Marshall Steam Station and _during Phase II and Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Dresser relief valve tested at each of the test facilities.
Each test was a 2500 psia pressure test with low temperature water just upstream of the valve followed by 650&deg;F water. In test number 16-DR-6W, the low temperature water was at l03&deg;F. During the test, the Dresser valve opened on demand. Upon de-energizing the valve for closure, the valve remained open until the valve was isolated from the ! test loop. At an indeterminate time following  
Test                     "As Tested" Test         Valve Performance Facility                  Matrix Table               Data Table Marshall                        4.1.l-la               4.1.l-lb Wyl e (Phase II)                4.l.l-2a               4.l.l-2b Wyl e (Phase II I)              4.1.1-3a              4.l.l-3b 4.1.2 Principal Observations Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles. During the evaluation tests, steam leaked past the valve pilot stem. Upon valve disassembly, the bellows was found to have several partially failed welds. The valve was reassembled with a new bellows and cycled 16 more times with varying steady state pilot backpressures up to 900 psig.
'test valve isolation, the valve closed. The valve was isolated approximately 40 seconds after it was signaJled
The valve fully opened and closed on demand for each cycle and the bellows did not leak. Upon disassembly, the bellows did not have any visible cracks. In all test cases, the valve fully opened on demand and closed on demand even though the bellows was damaged during some tests. Based on this input and the manufacturer's assessment of valve performance with the observed damage, the damage was determined to have no potential impact on valve npPration.
_to close. The valve was removed from the test facility and disassembled by the Dresser representative.
4-3
No damage was observed which might affect the ability of the valve to open/close on demand. In test number 22-DR-9W/W, the low temperature water at the valve inlet was 321&deg;F. During the test, the valve opened on demand. Upon de-energizing the valve for closure, the valve remained open for 2 seconds and then closed fully. Test number 24-DR-6W was a repeat of the test l 6-DR-6W except that the test was run to maximize the time before the valve was i so 1 ated. The water temperature immediately upstream of the valve was 105&deg;F. During the test, the valve opened on demand but failed to close immediately upon energjzing the solenoid.
 
The valve closed on its own approximately 70 seconds after the closure signal at an inlet pressure of approximately 2110 psi a. 4-4
The valve fully opened on demand and fully closed on demand for each of the five (5) test cycles.
' ' After all tests were completed, the Dresser valve was removed, bled, and inspected.
Wyle Phase III The valve fully opened on demand and fully closed on demand during nine (9) of the twelve (12) tests performed. The valve fully opened on demand and did not close on demand during the three (3) water seal simulation tests; number 16-DR-6W, 2?-DR-9W/W and 24-DR-6W.     Each test was a 2500 psia pressure test with low temperature water just upstream of the valve followed by 650&deg;F water.
No damage was observed which might affect the ability of the valve to open/close on demand. Valve Opening/Closing Times .No direct measurement of stem position was possible for the Dresser relief valve design. Therefore, no valve opening or .closing stroke times have been reported.
In test number 16-DR-6W, the low temperature water was at l03&deg;F. During the test, the Dresser valve opened on demand. Upon de-energizing the valve for closure, the valve remained open until the valve was isolated from the test loop. At an indeterminate time following 'test valve isolation, the valve closed. The valve was isolated approximately 40 seconds after it was signaJled _to close. The valve was removed from the test facility and disassembled by the Dresser representative. No damage was observed which might affect the ability of the valve to open/close on demand.
Estimates of total opening/closing times (time from energize/
In test number 22-DR-9W/W, the low temperature water at the valve inlet was 321&deg;F. During the test, the valve opened on demand. Upon de-energizing the valve for closure, the valve remained open for 2 seconds and then closed fully.
de-energize signal to full open/closed) have been made and are reported in the Valve Performance Data Table. These estimates were based on accelerometer or acoustic emission detector and inlet pressure measure-1nents and the methods used were confirmed by evaluation of data from other valves tested with stem position indication available.
Test number 24-DR-6W was a repeat of the test l 6-DR-6W except that the test was run to maximize the time before the valve was i so 1ated. The water temperature immediately upstream of the valve was 105&deg;F. During the test, the valve opened on demand but failed to close immediately upon de-energjzing the solenoid. The valve closed on its own approximately 70 seconds after the closure signal at an inlet pressure of approximately 2110 psi a.
4-5 I Q') EPRI/ MARSHALL PORV TEST DATA (3) TABLE 4. l. l 4'1a "AS TESTED" MARSHALL TEST MATRIX FOR THE DRESSER RELIEF VALVE CONDITIONS VALVE INLET TEST TEST FLUID PRESS. . TEMP. NO. TYPE (PSIA) (OF) STEAM STEAM 2435 (SAT.) 2 STEAM STEAM 2455 (SAT.) STEAM STEAM 2440 (SAT.) 4 STEAM ST.EAM 2435 (SAT.) 5 STEAM STEAM 2445 (SAT.) 6 STEAM STEAM 2450 (SAT.} STEAM STEAM 2455 (SAT.) 8 STEAM STEAM 2420 (SAT.) 9 STEAM STEAM 2415 (SAT.) 10 STEAM STEAM 2435 (SAT.) 11 STEAM STEAM 2435 (SAT.) NOTES: (1) Maximum Quasi steady discharge pipe pressure.  
4-4
 
After all tests were completed, the Dresser valve was removed, disassem-bled, and inspected. No damage was observed which might affect the ability of the valve to open/close on demand.
Valve Opening/Closing Times
    .No direct measurement of stem position was possible for the Dresser relief valve design. Therefore, no valve opening or .closing stroke times have been reported. Estimates of total opening/closing times (time from energize/ de-energize signal to full open/closed) have been made and are reported in the Valve Performance Data Table. These estimates were based on accelerometer or acoustic emission detector and inlet pressure measure-1nents and the methods used were confirmed by evaluation of data from other valves tested with stem position indication available.
4-5
 
EPRI/     MARSHALL         PORV TEST DATA (3)
TABLE 4. l. l 4'1a "AS TESTED"     MARSHALL     TEST MATRIX FOR THE     DRESSER RELIEF VALVE CONDITIONS AT VALVE OPENING                                        TRANSIENT CONDITIONS VALVE INLET                          IN ACCUMULATOR                    TEST OUAAT!ON VALVE INLET PRESS. WHEN MAXIMUM DISCHARG pl TEST         TEST         FLUID       PRESS.   . TEMP.        FLUID        PRESS.         TEMP.         (SEC)      SIGNAL GIVEN      PIPE PRESS.
NO.       TYPE                     (PSIA)      (OF)                      (PSIA)       (OF)                     TO CLOSE VALVE        (PSIA)
PSIA)
STEAM         STEAM       2435       (SAT.)         SAME AS VALYE INLET                    61              2295              415 2         STEAM         STEAM       2455       (SAT.)                                                 26              2335              415 STEAM       STEAM         2440       (SAT.)                   I                            22              2330              415 4         STEAM       ST.EAM       2435     (SAT.)                                                   21              2335              415 5         STEAM       STEAM         2445       (SAT.)                                                 24              2335              415 6         STEAM       STEAM         2450     (SAT.}                                                   66              2305              175
~
STEAM       STEAM         2455     (SAT.)                                                   23              2335              175 I
Q')    8         STEAM       STEAM       2420       (SAT.)                                                   27              2300              170 9         STEAM       STEAM       2415       (SAT.)                                                   24            2310              170 10           STEAM       STEAM       2435       (SAT.)
11           STEAM       STEAM       2435       (SAT.)                   l                              27
( 2) 2330 2295 175 415 NOTES:
(1) Maximum Quasi steady discharge pipe pressure.
(2) Not recorded.
(2) Not recorded.
AT VALVE OPENING IN ACCUMULATOR TEST OUAAT!ON FLUID PRESS. TEMP. (SEC) (PSIA) (OF) SAME AS VALYE INLET 61 I 26 22 21 24 66 23 l 27 24 27 ( 2) TRANSIENT CONDITIONS VALVE INLET MAXIMUM pl PRESS. WHEN DISCHARG SIGNAL GIVEN PIPE PRESS. TO CLOSE VALVE (PSIA) PSIA) 2295 415 2335 415 2330 415 2335 415 2335 415 2305 175 2335 175 2300 170 2310 170 2330 175 2295 415 (3) Test results are for evaluation tests only. Total of 21 supplementary valve actuation cycles were performed under similar conditions  
(3) Test results are for evaluation tests only. Total of 21 supplementary valve actuation cycles were performed under similar conditions
* * 
* EPRI I MARSHALL       PORV TEST llATA (3)
**
TABLE 4.1.l.-lb
* EPRI I MARSHALL PORV TEST llATA (3) TABLE 4.1.l.-lb  


==SUMMARY==
==SUMMARY==
OF DRESSER RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS  
OF DRESSER RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS               &deg;COMMENTS TOTAL VALVE (1)                             VALVE VALVE INLET         OUTLET   FLOW TEST        TEST    OPEN ING TIME  FLUID    PRESS.                                TOTAL VALVE (2)                   VALVE INLET       LEAKAGE NO.       TYPE                                        TEMP. PRESS. RATE     CLOSING TIME       MEDIA     PRESS.
&deg;COMMENTS VALVE TOTAL VALVE (1) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPEN ING TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM) STEAM 0.190 STEAM (SAT.) A pre-operational lea<a9e 2295 415 155,000 0. 300 STEAM 2405 (SAT.) 0.005 test showed 0.0 GPM lea<a;e 2 STEAM 0.170 * * * *
(SEC)               (PSIA)     (OF)   (PSIA)                                                       TEMP.      RATE (LBM/HR)       (SEC)                     (PSIA)     (OF)     (GPM)
* 0.320 * *
STEAM       0.190       STEAM     2295      (SAT.)   415     155,000     0. 300           STEAM                                 A pre-operational lea<a9e 2405       (SAT.)   0.005 test showed 0.0 GPM lea<a;e 2       STEAM       0.170         *         *       *         *
* STEAM 0.190 * * * *
* 0.320 STEAM 0.190         *         *       *         *
* 0.310 * * *
* 0.310 4       STEAM       0.190                   *       *         .
* 4 STEAM 0.190 .. * * ..
* 0.320                                     .
* 0.320 * * ..
5       STEAM       0.190
* 5 STEAM 0.190 * * * *
                                              *         *       *       *
* 0.310 STEAM 2455 (SAT.) 0.013 6 STEAM 0. 180 STEAM 2305 (SAT.) 175 155,000 0.300 * *
* 0.310             STEAM       2455       (SAT.)   0.013 6       STEAM       0. 180     STEAM     2305     (SAT.)     175   155,000     0.300               *         *
* STEAM 0.230 * * *
* STEAM       0.230                   *         *       *
* 0.300 *
* 0.300
* 8 STEAM 0.170 * *
* 8       STEAM       0.170
* 0.300 * .. .+::> I -....J 9 STEAM 0.180 * * *
.+::>
* 0.300 * * .. 10 STEAM 0.170 * * * *
I
* 0.300 * * *
-....J     9       STEAM
* 11 STEAM 0.190 * * * *
                                              *        *
* 0.300 STEAM 2435 (SAT.) 0.0
* 0.300                          *                    ..
* not applicable to this test NOTES: (1) Opening time measured from time of energizing solenoid until valve reaches full open position.  
0.180 10        STEAM
(2) Closing time measured from time of de-energizing solenoid until *valve reaches full f,osition, (3) Test results are for evaluation tests only. Total of 21 supplementary valve actuation eye es were performed under similar conditions.
                                              *         *                 *
+:> I co
* 0.300               *                     *         .
* E PR!/ WYLE roRV TEST DATA TABLE 4. 1. 1-2a "AS TESTED" WYLE.PHASE II TEST MATRIX FOR THE DRESSER RELIEF VALVE INITIAL CONDITIONS TRANSIENT VALVE INLET ( 1) IN ACCUMULATOR VAL VE TNI ET DURATION PRESS. WHEN TEST TEST FLUID PRESS. TEMP. FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN NO. TYPE (PSIA) (OF) (PSIA) (OF) TO CLOSE VALVE (PSIA) DR-1-S STEAM STEAM 2490 674 SAME AS VALVE INLET 6 2215 DR-3-W WATER WATER 680 373 SAME AS VALVE INLET 15 510 DR-5-W WATER WATER 2500 646 SAME AS VALVE INLET 26 2300 DR-6-W WATER WATER 2500 506 SAME AS VALVE INLET 17 2120 DR-7-W HATER WATER 2510 447 SAME AS VALVE INLET 16 2120 NOTES: (!) Fluid conditions at the valve *inlet inmediately prior to actuation of test valve. (2) Maximum Quasi steady discharge pipe pressure.  
0.170         *         *       *         *
* (3) Not recorded.
* 0.300               *           *         *
* CONDITIONS (2) qu,;s; .STEADY DISCHARGE MAX !MUM PIPE PRESS. PILOT LINE (PSJA) B.P. (PSIA) 60 1040 110 213 290 680 340 380 230 333
* 11       STEAM       0.190         *         *       *         *
* 40:> I <..O
* 0.300           STEAM       2435       (SAT.)   0.0
* EPRI I 1-IYLE PHASE II PORV TEST DATA TABLE 4.1.1-2b  
* not applicable to this test NOTES:
(1) Opening time measured from time of energizing solenoid until valve reaches full open position.
(2) Closing time measured from time of de-energizing solenoid until *valve reaches full ~losed f,osition, (3) Test results are for evaluation tests only. Total of 21 supplementary valve actuation eye es were performed under similar conditions.
 
EPR!/     WYLE         roRV TEST DATA TABLE 4. 1. 1-2a "AS TESTED" WYLE.PHASE II TEST MATRIX FOR THE DRESSER RELIEF VALVE INITIAL CONDITIONS                                                   TRANSIENT CONDITIONS VALVE INLET ( 1)                 IN ACCUMULATOR               TF~T      VAL VE TNI ET       ~. 0.Y!"'.''1 (2) qu,;s; .STEADY TEST          TEST                                                                        DURATION   PRESS. WHEN         DISCHARGE            MAX !MUM FLUID     PRESS.     TEMP.       FLUID     PRESS.     TEMP.       (SEC)     SIGNAL GIVEN       PIPE PRESS.
NO.         TYPE               (PSIA)     (OF)                                                                                             PILOT LINE (PSIA)       (OF)                 TO CLOSE VALVE           (PSJA)            B.P.
(PSIA)                                (PSIA)
DR-1-S       STEAM     STEAM     2490       674             SAME AS VALVE INLET             6             2215               60                  1040 DR-3-W       WATER     WATER     680       373             SAME AS VALVE INLET             15             510             110                    213 DR-5-W       WATER     WATER     2500       646             SAME AS VALVE INLET             26           2300             290                    680 DR-6-W       WATER     WATER     2500       506             SAME AS VALVE INLET             17           2120             340                    380 DR-7-W       HATER     WATER     2510       447             SAME AS VALVE INLET             16           2120             230                    333
+:>
I co NOTES:
(!)   Fluid conditions at the valve *inlet inmediately prior to actuation of test valve.
(2)   Maximum Quasi steady discharge pipe pressure.                     *
(3)   Not recorded.
 
EPRI I 1-IYLE PHASE II PORV TEST DATA TABLE 4.1.1-2b


==SUMMARY==
==SUMMARY==
OF ORESSER RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS VALVE TOTAL VA.LYE (I) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TlMP. RATE TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM) DR-1-S STEAM 0. 15 STEAM 2355 668 56 137,000 0.60 STEAM 2saa 660 0.0 DR-3-W WATER 0. 17 WATER 630 373 102 331,000 0.6a WATER 685 J8a o.o DR-5-W lo/ATER 0. 15 WATER 2430 646 278 328,000 0.6a WATER 2475 651 0.0 OR-6-W lo/ATER 0. 15 WATER 2330 sag 310 590,aaa 0.6a WATER 2380 514 a.a DR-7-W WATER 0.10 WATER 2360 447 22a 641,00a a.so WATER 2495 454 a.a llOTES: (I) Opening time measured fro.m time of energizing solenoid until valve reaches full open position.  
OF ORESSER RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS                                     LEAKAGE MEASUREMENTS         COMMENTS VALVE TOTAL VA.LYE (I)         VALVE INLET         OUTLET       FLOW   TOTAL VALVE (2)             VALVE INLET   LEAKAGE TEST     TEST     C?f),~:jG TIME   FLUID   PRESS. TEMP. PRESS.     RATE     CLOSING TIME     MEDIA   PRESS. TlMP. RATE
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.
      ~lO. TYPE           (SEC)               (PSIA)   (OF)     (PSIA) (LBM/HR)         (SEC)                 (PSIA)   (OF) (GPM)
* COMMENTS EPR!/WYLE PHASE III PORV TEST DATA TABLE 4.1.l-3a "AS TESTED" WYLE PllASE II I TEST MATRIX FOR DRESSER RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS Valve Inlet Back-At Valve Inlet In Accumulator Pressure Maximum Maximum Maximum pressure at Discharge Bending Valve Orifice Test Closure Pipe Moment Acceleration Area Temp Press. Temp Press. Duration Signal Press. lnduced(l)lnduced Test No. Test Type ( in2) Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (in-lb) (g's) 10-DR-lS Steam 4.155 Steam 668 2,503 Steam 669 2,503 15 2,035 760 N/A 6.8 ll-DR-4W Water 6.166 Water 647 2,514 Water 658 2,514 15 2,338 625 N/A 5.0 12-DR-3W Water 6.166 Water 450 699 Water 456 699 15 685 260 N/A 8.2 .p. 13-DR-?W Water 6.166 Water 451 2,492 Water 460 2,492 10 2,230 420 N/A 7.4 I ....... -o 14-DR-2W Water 6.166 Water 112 689 Water 116 689 10 652 5 N/A 8.6 15-DR-5W Water 6.166 Water 643 2,504 Water 658 2,504 10 2,360 640 25,500 5.3 (Pre load) 16-DR-6W Water 6.166 Water 103 2,500 Water 652 2,500 54 2,320 295 N/A 8.2 Seal Simulation 20-DR-lS Steam 6.166 Steam 657 2,505 Steam 659 2,505 10 2,110 495 N/A 9.2 21-DR-8S/W Transition 6.166 Steam 656 2,496 Water 641 2,496 10 2,360 660 N/A 9.6 22-DR-9W/W Water 6.166 Water 321 2,490 Water 647 2,490 17 2,310 678 N/A 6.9 Seal Simulation 23-DR-lS . Steam 6.166 Steam 657 2,505 Steam 659 2,505 10 2,110 440 N/A 8.9 24-DR-6W/W Water 6.166 Water 105 2,505 Water 649 2,505 88 2,360 690 N/A 8.6 Seal Simulation Notes. -(1) V 1wn corresponds to maximum applied while valve was in the .closing process. (2) Co , to timP prmv r.los11rP or.r:1irP.rl  
DR-1-S   STEAM         0. 15       STEAM     2355     668         56     137,000     0.60           STEAM   2saa     660     0.0 DR-3-W   WATER         0. 17       WATER     630     373         102     331,000     0.6a           WATER     685     J8a     o.o DR-5-W   lo/ATER       0. 15       WATER     2430     646         278       328,000     0.6a           WATER   2475     651     0.0 OR-6-W   lo/ATER       0. 15       WATER     2330     sag         310       590,aaa     0.6a           WATER   2380     514     a.a 40:>
;it 11nr!Pt _ rl t. imo ;ift.P.r inn.
I  DR-7-W   WATER         0.10         WATER     2360     447         22a       641,00a     a.so           WATER   2495     454     a.a
* EPRl/WYLE PHASE Ill PORV TEST .DATA TABLE 4.1.l-3b  
<..O llOTES:
(I) Opening time measured fro.m time of energizing solenoid until valve reaches full open position.
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.
 
EPR!/WYLE PHASE III PORV TEST DATA TABLE 4.1.l-3a "AS TESTED" WYLE PllASE II I TEST MATRIX FOR DRESSER RELIEF VALVE INITIAL CONDITIONS                                                                   TRANSIENT CONDITIONS Valve Inlet Back-             At Valve Inlet                           In Accumulator                               Pressure Maximum     Maximum Maximum pressure                                                                                                 at       Discharge   Bending Valve Orifice                                                                                     Test         Closure Pipe Area                     Temp         Press.                                                                                   Moment      Acceleration Test No.                                                                                      Temp         Press.     Duration Signal       Press.       lnduced(l)lnduced Test Type     ( in2)     Fluid       (OF)         (psi a)       Fluid       (OF)         (psi a)     (seconds) (psi a)     (psi a)     (in- lb)   (g's) 10-DR-lS     Steam         4.155       Steam         668         2,503         Steam         669         2,503         15         2,035     760       N/A         6.8 ll-DR-4W     Water         6.166     Water         647         2,514         Water         658         2,514         15         2,338     625       N/A       5.0 12-DR-3W     Water         6.166       Water         450           699         Water         456           699         15           685     260       N/A       8.2
.p.
I      13-DR-?W     Water         6.166       Water         451         2,492         Water         460
.......                                                                                                              2,492         10         2,230     420       N/A       7.4
-o 14-DR-2W     Water         6.166       Water         112           689         Water         116           689         10           652       5       N/A       8.6 15-DR-5W     Water         6.166       Water         643         2,504         Water         658 (Pre load)                                                                                    2,504         10         2,360     640       25,500     5.3 16-DR-6W     Water         6.166       Water         103         2,500         Water         652 Seal                                                                                          2,500         54         2,320     295       N/A         8.2 Simulation 20-DR-lS     Steam         6.166       Steam         657         2,505         Steam         659         2,505         10         2,110     495       N/A         9.2 21-DR-8S/W   Transition   6.166       Steam         656         2,496         Water         641         2,496         10         2,360     660       N/A       9.6 22-DR-9W/W   Water         6.166       Water         321         2,490         Water         647 Seal                                                                                          2,490         17         2,310     678       N/A       6.9 Simulation 23-DR-lS   . Steam         6.166       Steam         657       2,505         Steam         659         2,505         10           2,110     440       N/A       8.9 24-DR-6W/W   Water         6.166       Water         105       2,505         Water         649 Seal                                                                                          2,505         88           2,360     690       N/A       8.6 Simulation Notes.
        -(1) V       1wn corresponds to maximum mom~nt applied while valve was in the .closing process.
(2) Co     , d~ to timP prmv w~~ i~ol;it.f!rl. Ar:t.*i~l r.los11rP or.r:1irP.rl ;it ~n 11nr!Pt     _rl t. imo ;ift.P.r i~ol;it. inn.
 
EPRl/WYLE PHASE Ill PORV TEST .DATA TABLE 4.1.l-3b


==SUMMARY==
==SUMMARY==
OF DRESSER RELIEF VALVE PERFORMANCE Test 10-11-12-13 15-16-20-21-22-23-24-Number DR-lS DR-4W DR-3W DR-7W DR-2W DR-SW DR-61i'/ DR-lS DR-8S/W DR-9W/W DR-lS DR-6W/W Pre-Test Leakage(!)
OF DRESSER RELIEF VALVE PERFORMANCE Test                             10-       11-       12-       13-      14-      15-     16-       20-     21-       22-       23-     24-Number                             DR-lS     DR-4W     DR-3W     DR-7W     DR-2W     DR-SW   DR-61i'/   DR-lS   DR-8S/W   DR-9W/W   DR-lS   DR-6W/W Pre-Test Leakage(!)
Media Steam Water Water Water Water Water Wateir Steam Water Water Steam Water Pressure (psia) 2,587 2,482 690 2;500 700 2,550 2,46'5 2,527 2,500 2,550 2,515 2,515 Temp (OF) 669 645 450 450 104 581 105 671 672 305 670 104 Leak Rate (GPM) 0.0013 0.0013* 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.00"13 .026 0.0013 Transient Performance Total Valve Opening Time (sec) 0.11 0.065 0.07 0.062 0.11 0.075 0.060 0.17 0.11 0.68 0.13 0.062 Valve Flowrate (lb/Hr) 133,200 295,200 262,800 622,800 388,800 302,400 331,200 129,600 324,000 309,600 132,480 316, 800 Corresponding Valve Inlet Press (psia) 2,318 2,422 692 2,320 662 2,410 2,360 2,296 2,400 2,380 2, 280 2,400 """"' Corresponding Valve I I-' Inlet Temp (OF) 658 652 453 456 117 650 636 648 633 638 645 535 I-' Corresponding Valve Outlet Press (psia) 670 610 248 405 2 621 265i 434 638 618 422 627 Corresponding Valve Outlet Temp (OF) 510 494 408 452 117 497 414 454 495 495 453 495 Corresponding Test Time Relative to Open Command (sec) 4.8 4.7 4.5 4.4 4.4 4.7 9.1 4.3 5.1 6.7 0.5 6.0 Inlet Pressure at Beginning of Valve Closure (psia) 2,030 2,340 680 2,230 650 2,370 14.7 2,110 2,360 2,310 2,105 2,120 Total Valve Closure Time (sec) 0.217 0.31 0.30 0.21 0.23 0.31 (2) .21 .35 1. 74 .023 69.15 Post-Test Leakage(!)
Media                         Steam     Water     Water       Water     Water     Water   Wateir     Steam   Water     Water     Steam   Water Pressure (psia)               2,587     2,482       690     2;500       700     2,550   2,46'5     2,527   2,500     2,550     2,515   2,515 Temp (OF)                       669     645       450       450       104       581       105       671       672       305       670     104 Leak Rate (GPM)             0.0013   0.0013*   0.0013     0.0013   0.0013   0.0013 0.0013     0.0013   0.0013   0.00"13     .026   0.0013 Transient Performance Total Valve Opening Time (sec)               0.11     0.065       0.07     0.062     0.11     0.075   0.060       0.17     0.11       0.68     0.13   0.062 Valve Flowrate (lb/Hr)     133,200   295,200   262,800     622,800   388,800   302,400 331,200     129,600 324,000   309,600   132,480 316, 800 Corresponding Valve Inlet Press (psia)     2,318     2,422       692     2,320       662     2,410   2,360     2,296   2,400     2,380     2, 280   2,400 I
Media Steam Water Water Water Water Water Water Steam Water Water Steam Water Pressure (psia) 2,591 2,465 700 2,250 700 2,567 2,244 2,593 2,476 2,490 2,510 2,435 Temp (OF) 646 600 445 415 104 577 389 631 630 480 669 495 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 .0024 .018 .0119 .026 .024 Notes: ( 1) Recorded leakages of .0013 GPM indicate measured values of less than or equal to .0013 GPM. (2) Valve closure occured at an undetermined time following the isolation of the PORV which occurred approximately 90 seconds after the valve rlflcqrn j'"tr1;d.
Corresponding Valve I-'
' '
I-'
* 4.t.' CROSBY l{LLlE.r Vl\LVL 4.2.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Crosby relief valve model at the Marshall Steam Station, and during Phase II and Phase III of the Wyle Test Program. The foll6wing is the list of tables that contain the "as tested" test matrices and valve performance data for the Crosby relief valve tested at each of the test facilities.
Inlet Temp (OF)           658       652       453       456       117       650     636       648       633       638       645     535 Corresponding Valve Outlet Press (psia)       670       610       248       405         2       621     265i       434       638       618       422     627 Corresponding Valve Outlet Temp (OF)           510     494       408       452       117       497     414       454       495       495       453     495 Corresponding Test Time Relative to Open Command (sec)             4.8     4.7       4.5       4.4       4.4       4.7     9.1       4.3       5.1       6.7       0.5     6.0 Inlet Pressure at Beginning of Valve Closure (psia)         2,030     2,340       680     2,230       650     2,370     14.7     2,110   2,360     2,310     2,105   2,120 Total Valve Closure Time (sec)             0.217     0.31       0.30       0.21     0.23     0.31       (2)       .21       .35     1. 74   .023   69.15 Post-Test Leakage(!)
4.2.2 Test Facility Marshall Wyle (Phase II) Wyle (Phase III) Principal Observations Marshall Steam Station "As Tested" Test Matrix Table 4.2.l-la 4.2.l-2a 4.2. l-3a Valve Performance Data Table 4.2.l-lb 4.2. l-2b 4.2.l-3b The valve fully opened on demand and fully closed on demand during each of the eleven (11) evaluation tests. Following several successful actuations performed prior to the evaluation tests, the Crosby valve failed to open on demand during 5 attempts and on. a subsequent test failed to seat properly.
Media                         Steam     Water     Water       Water     Water     Water   Water     Steam   Water     Water     Steam   Water Pressure (psia)               2,591     2,465       700     2,250       700     2,567   2,244     2,593   2,476     2,490     2,510   2,435 Temp (OF)                       646       600       445       415       104       577       389       631     630       480       669     495 Leak Rate (GPM)             0.0013   0.0013   0.0013     0.0013   0.0013   0.0013 0.0013       .0024     .018   .0119     .026     .024 Notes:
When the valve was disassembled and inspected, one bellows weld fracture was found and a bellows assembly part was found to be improperly machined.
( 1) Recorded leakages of .0013 GPM indicate measured values of less than or equal to .0013 GPM.
The bellows was replaced, the bellows assembly was correctly machined and the valve was reassembled for further tests. The valve was subsequently cycled fifty (50) times (dry, unpressurized) and twenty-eight (28) times (steam, full pressure/flow) including the eleven (11) evaluation tests. The valve fully opened and closed on demand and no bellows leakage occurred during these tests. 4-13 Wyl e Phase II Prior to Wyle Phase II testing, the test valve (a different valve than that test<:d at Marshall) was disassembled and_ inspected.
(2) Valve closure occured at an undetermined time following the isolation of the PORV which occurred approximately 90 seconds after the valve rlflcqrn ~ j'"tr1;d.
During this tion. it was noted that the bellows assembly was incorrectly machined as was the case for the Marshall valve. The bellows assembly was correctly machined prior to Wyle testing. The valve fully opened on demand and fully closed on demand for each of the six (6) test cycles. Upon disassembly after tests were completed, the pilot bellows was found to leak. Wyle Phase III The same Crosby tested during Phase II was utilized during Phase III of Wyle testing. The v a l v e f u l l y opened on d em an d and f u 11 y c l o s e d on demand for e a c h of t he ten (10) test cycles. Upon disassembly after tests were completed, the pilot. bellows was observed to be damaged. Be 11 ows Damage In all test cases, the valve fully opened on demand and closed on demand even though the bellows had been damaged. Based on this input and the manufacturer's assessment of valve performance with the observed damage, the damage was determined to have no potent i a 1 impact on valve operation.
 
_'{_(l_l_v_E i n_g __
4.t.' CROSBY l{LLlE.r Vl\LVL 4.2.l         "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Crosby relief valve model at the Marshall Steam Station, and during Phase II and Phase III of the Wyle Test Program. The foll6wing is the list of tables that contain the "as tested" test matrices and valve performance data for the Crosby relief valve tested at each of the test facilities.
No direct measurement of stem valve design. been reported.
Test                          "As Tested" Test        Valve Performance Facility                            Matrix Table              Data Table Marshall                              4.2.l-la                4.2.l-lb Wyle (Phase II)                       4.2.l-2a                4.2. l-2b Wyle (Phase III)                      4.2. l-3a               4.2.l-3b 4.2.2   Principal Observations
Therefore, no Estimates of position was possible for the Crosby valve opening or closing stroke times have total opening/closing times (time from energize/de-energize signal to full open/closed) have been made and are reported in the Valve Performance Data Table. These estimates were based on a:celerometer or acoustic emission detector and inlet pressure measurements and the mE'thods used were c9nf i rmed by evaluation of data from other valves tested with stem position indication available.
* Marshall Steam Station The valve fully opened on demand and fully closed on demand during each of the eleven (11) evaluation tests.
4-14 ' ' *
Following several successful actuations performed prior to the evaluation tests, the Crosby valve failed to open on demand during 5 attempts and on.
* I r * ' *
a subsequent test failed to seat properly. When the valve was disassembled and inspected, one bellows weld fracture was found and a bellows assembly part was found to be improperly machined. The bellows was replaced, the bellows assembly was correctly machined and the valve was reassembled for further tests.
* Supplementary Information During both Wyle Phase II and Phase III testing, the valve exhibited a tendency not to seal at very low pressures (below 100 psi). Repeated actuations and/or rapid pressurization of the valve inlet were at times required to obtain proper valve seating . 4-15
The valve was subsequently cycled fifty (50) times (dry, unpressurized) and twenty-eight (28) times (steam, full pressure/flow) including the eleven (11) evaluation tests. The valve fully opened and closed on demand and no bellows leakage occurred during these tests.
.p, I ....... ::J) * '.'AS TESTED" MARSHALL CONDITIONS AT VALVE INLET TEST TEST FLUID PRESS. NO. TYPE (PSIA) STEAM STEAM 2495 STEAM STEAM 2485 3 STEAM STEAM 2455 4 STEAM STEAM 2455 5 STEAM STEAM 2455 6 STEAM STEAM 2485 STEAM STEAM 2485 8 STEAM STEAM 2450 STEAM STEAM 2435 10
4-13
* STEAM STEAM 2465 11 STEAM STEAM 2475 NOTES: {!) Maximum Quasi steady discharge pipe pressure.
 
(2) Not recorded.
Wyl e Phase II Prior to Wyle Phase II testing, the test valve (a different valve than that test<:d at Marshall) was disassembled and_ inspected. During this inspec-tion. it was noted that the bellows assembly was incorrectly machined as was the case for the Marshall valve. The bellows assembly was correctly machined prior to Wyle testing.
TEMP. (OF) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) {SAT.) (SAT.) EPRI/ MARSHALL PORV TEST DATA (3) TABLE 4.2.1.-la TEST MATRIX FOR THE CROSBY RELIEF VALVE VALVE OPENING CONDITIONS IN Acc:;'*'.ULATOR TEST VALVE INLET MAXIM0M pl DURATION PRESS. WHEN DISCHARG FLUID F'lESS. TEMP. (SEC) SIGNAL GI VEN PIPE PRESS. (PSIA) (OF) TO CLOSE VALVE (PSIA) (PSIA) SAME AS VALVE INLET 66 2335 375 25 2350 385 21 2335 385 21 2330 375 18 2335 385 53 2335 135 22 2345 135 28 2315 135 25 2310 85 (4) 24 2350 135 i (2) 2325 375 (3) Test results are for evaluation tests only. Total of 31 supplementary valve actuation cycles were performed under similar conditions.
The valve fully opened on demand and fully closed on demand for each of the six (6) test cycles. Upon disassembly after tests were completed, the pilot bellows was found to leak.
{4) Downstream pressure Jppears to be anomalous.
Wyle Phase III The same Crosby valv~ tested during Phase II was utilized during Phase III of Wyle testing.
* *
The va l ve f ul l y opened on dem an d and f u11 y c l os e d on demand for e ac h of t he ten (10) test cycles. Upon disassembly after tests were completed, the pilot. bellows was observed to be damaged.
* EPRI I MADSHALL rn:iv TEST nAH (3) TABLE 4.2.l-lb
Be 11 ows Damage In all test cases, the valve fully opened on demand and closed on demand even though the bellows had been damaged. Based on this input and the manufacturer's assessment of valve performance with the observed damage, the damage was determined to have no potent i a1 impact on valve operation.
_'{_(l_l_v_E -~pe_r:!__i_~g/_C_l_ns. i n_g__ T_j!1~~-S.
No direct measurement of stem position was possible for the Crosby reli~f valve design. Therefore, no valve opening or closing stroke times have been reported. Estimates of total opening/closing times (time from energize/de-energize signal to full open/closed) have been made and are reported in the Valve Performance Data Table. These estimates were based on a:celerometer or acoustic emission detector and inlet pressure measurements and the mE'thods used were c9nf i rmed by evaluation of data from other valves tested with stem position indication available.
4-14
 
I r * '
* Supplementary Information During both Wyle Phase II and Phase III testing, the valve exhibited a tendency not to seal at very low pressures (below 100 psi). Repeated actuations and/or rapid pressurization of the valve inlet were at times required to obtain proper valve seating .
4-15
 
EPRI/      MARSHALL          PORV TEST DATA (3)
TABLE 4.2.1.-la
                                                '.'AS TESTED"       MARSHALL   TEST MATRIX FOR THE              CROSBY  RELIEF  VALVE CONDITIONS AT VALVE OPENING                                            TRANSIE~T  CONDITIONS TEST           TEST       FLUID VALVE INLET                            IN Acc:;'*'.ULATOR                  TEST DURATION VALVE INLET PRESS. WHEN MAXIM0M DISCHARG pl PRESS.      TEMP.        FLUID        F'lESS.          TEMP.        (SEC)        SIGNAL GI VEN NO.            TYPE                      (PSIA)      (OF)                                                                                      PIPE PRESS.
(PSIA)         (OF)                       TO CLOSE VALVE        (PSIA)
(PSIA)
STEAM      STEAM          2495      (SAT.)           SAME AS VALVE INLET                      66                2335              375 STEAM      STEAM          2485      (SAT.)                                                     25                2350              385 3            STEAM      STEAM          2455      (SAT.)                                                     21                2335              385 4            STEAM      STEAM          2455      (SAT.)                                                     21                2330              375 5            STEAM      STEAM            2455      (SAT.)                                                     18                2335              385 6            STEAM      STEAM            2485      (SAT.)                                                     53                2335              135 STEAM      STEAM            2485      (SAT.)                                                     22                2345
.p,                                                                                                                                                            135 I
.......      8            STEAM      STEAM            2450      (SAT.)                                                     28                2315
::J) 135 STEAM      STEAM            2435      (SAT.)                                                     25                2310              85 (4) 10
* STEAM      STEAM          2465      {SAT.)                                                      24                2350            135 11            STEAM      STEAM          2475      (SAT.)                                                      (2) i                                                2325            375 NOTES:
{!) Maximum Quasi steady discharge pipe pressure.
(2)  Not recorded.
(3)   Test results are for evaluation tests only. Total of 31 supplementary valve actuation cycles were performed under similar conditions.
{4) Downstream pressure Jppears to be anomalous.
 
EPRI  I  MADSHALL      rn:iv TEST TABLE 4.2.l-lb nAH


==SUMMARY==
==SUMMARY==
OF CROSBY RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS.
OF CROSBY RELIEF VALVE PERFORMANCE (3)
COMMOHS Vt'll VC-TOTAL VAL VE (1) VAL VE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM) STEAM 0.290 STEAM 2335 (SAT.) 375 168,000 0.150 STEAM 2495 (SAT.) 0.057 A pre-operational leakage
* FLOW MEASUREMENT CONDITIONS                                         LEAKAGE MEASUREMENTS.             COMMOHS Vt'll VC-TOTAL VAL VE (1)         VAL VE INLET         OUTLET       FLOW                                     VALVE INLET TEST        TEST    OPENING TIME                                                        TOTAL VALVE (2)                                 LEAKAGE FLUID     PRESS.     TEMP. PRESS.       RATE     CLOSING TIME     MEDIA     PRESS. TEMP.
* test showed 0.904 GPM leakage 2 STEAM 0.380 * * *
NO.       TYPE         (SEC)                 (PSIA)     (OF)                                                                           RATE (PSIA)     (LBM/HR)       (SEC)                   (PSIA)     (OF)     (GPM)
* 0.150 3 STEAM 0.350 *
STEAM     0.290         STEAM     2335     (SAT.)     375       168,000     0.150           STEAM     2495       (SAT.)   0.057 A pre-operational leakage
* 0.150 *
* 2                                                                                                                                              test showed 0.904 GPM leakage STEAM     0.380             *         *                   *
* 4 STEAM 0.350 * .* 0.150 * *
* 0.150 3       STEAM     0.350                                 *
* STEAM 0.380
* 0.150                         *
* 0.150 STEAM 2495 (SAT.) 0.026 6 STEAM 0.320 STEAM 2335 (SAT.) 135 168,000 0.150 * ... *
* 4       STEAM       0.350                       *                             .*       0.150                         *         *
* STEAM 0. 320 * * *
* STEAM       0.380
* 0.150           STEAM     2495       (SAT.)   0.026 6       STEAM       0.320         STEAM     2335     (SAT.)   135       168,000       0.150
* STEAM       0. 320           *         *                   *
* 0.150
* 0.150
* B STEAM 0.350 *
* B       STEAM       0.350                               *          *
* 0.150 *
~
* STEAM 0.300
0.150                                   *
* 0.160 * *
* STEAM       0.300 I
* I ....... '-I 10 STEAM 0.300 * * * *
.......
* 0. 140 * * *
* 0.160              *          *          *
* 11 STEAM 0.370 0.150 STEAM 2485 (SAT.) 0.045
'-I     10       STEAM       0.300           *         *         *         *
* not applicable to this test NOTES: (I) Opening time measured from t me of energizing solenoid until valve reaches full open position.  
* 0. 140             *         *         *
(2) Closing time measured from t me of de-energizing solenoid until valve reaches full closed position, (3) Test results are for evaluat on tests only. Total of 31 supplementary*
* 11       STEAM       0.370                                                               0.150           STEAM     2485       (SAT.)   0.045
valve actuation tests were performed under similar conditions.
* not applicable to this test NOTES:
* EPRI/ WYLE roPV HSi TABLE 4.2.l-2a "AS TESTED" WYLE PHASE II TEST MATRIX FOR THE IN IT !AL CONDITIONS ( l i ;...;:,,..,>.J::vL;,;,,:;r;.  
(I) Opening time measured from t me of energizing solenoid until valve reaches full open position.
*.;..L Vt 1 I DURATION TEST TEST FLUID PRESS. TEMP. FLUID PRESS. TEMP; (SEC) NO. TYPE (PSIA) (OF) (PSIA) (OF) CR-1-S STEAM STEAM 2150 672 SAME AS VALVE INLET 15 CR-2-S STEAM STEAM 2495 671 SAME AS VALVE INLET CR-3-W WATER WATER 680 376 SAME AS VALVE INLET JS CR-5-\1 WATER WATER 2510 634 SAME AS VALVE INLET 15 CR-6-W WATER WATER 2502 505 SAME AS VALVE INLET 19 CR-7-W WATER WATER 2510 446 SAME AS VALVE INLET 18 NOTES: (1) Fluid conditions at the valve inlet irmiediately prior to actuation of test valve. (2) Maximum Quasi steady discharge pipe pressure.  
(2) Closing time measured from t me of de-energizing solenoid until valve reaches full closed position, (3) Test results are for evaluat on tests only. Total of 31 supplementary* valve actuation tests were performed under similar conditions.
 
EPRI/                 WYLE           roPV HSi DATA TABLE   4.2.l-2a "AS TESTED" WYLE PHASE II TEST MATRIX FOR THE                         CROSBY        RELIEF VALVE IN IT !AL CONDITIONS                                                                           TRANSIENT COHDITIOMS
                              *.;..L Vt  1i~Lt. I ( l i                ~;i ;...;:,,..,>.J::vL;,;,,:;r;.                       '''" \/[;"  l'ILET        MAXIMUM (2) QUASI STEADY DURATION  PRESS. WHEN                DISCHARGE      MAXIMUM TEST       TEST     FLUID         PRESS.           TEMP.       FLUID           PRESS.                 TEMP;       (SEC)     SIGNAL GI VEN              PIPE PRESS. PILOT LINE NO.       TYPE                   (PSIA)           (OF)                       (PSIA)                 (OF)                   TO CLOSE VALVE                (PSIA)        B. p.
PSIA)                            PSIA CR-1-S   STEAM     STEAM         2150             672           SAME AS VALVE INLET                               15                 1920                60            945 CR-2-S   STEAM     STEAM         2495             671           SAME AS VALVE INLET                                                 2140              560          )1000 (3)
CR-3-W     WATER     WATER         680             376           SAME AS VALVE INLET                               JS                 618              125            200 CR-5-\1   WATER     WATER         2510             634           SAME AS VALVE INLET                             15                 2280              155            775 CR-6-W     WATER     WATER         2502             505           SAME AS VALVE INLET                             19                 2100              315            438 CR-7-W     WATER     WATER         2510             446           SAME AS VALVE INLET                             18                 2000              230            661 NOTES:
(1) Fluid conditions at the valve inlet irmiediately prior to actuation of test valve.
(2) Maximum Quasi steady discharge pipe pressure.
(3) The 1000 PSIA pressure sensor was over-ranged in this test.
(3) The 1000 PSIA pressure sensor was over-ranged in this test.
* DATA CROSBY RELIEF VALVE TRANSIENT COHDITIOMS
 
'''" \/[;" l'ILET MAXIMUM (2) QUASI STEADY PRESS. WHEN DISCHARGE MAXIMUM SIGNAL GI VEN PIPE PRESS. PILOT LINE TO CLOSE VALVE (PSIA) B. p. PSIA) PSIA 1920 60 945 2140 560 )1000 (3) 618 125 200 2280 155 775 2100 315 438 2000 230 661 * 
EPRI/WYLE PHASE II PORV TEST DATA TABLE 4.2.l-2b
+::> I ....... l.D EPRI/WYLE PHASE II PORV TEST DATA TABLE 4.2.l-2b  


==SUMMARY==
==SUMMARY==
OF CROSBY RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS VALVE TOTAL '/,\LVE (!) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (Of) (GPM) CR-1-S STEAM 0.10 STEAM 2280 661 57 162,000 0.20 STEAM 2000 637 0.0 CR-2-S STEAM 0.07 STEAM 2420 671 560 165,600 0.14 STEAM 2485 653 0.008 CR-3-W WATER 0.10 WATER 622 382 122 410,400 0.20 WATER 660 386 0.0 CR-5-W 11,\TER 0.10 WATER 2400 645 150 385,200 0.20 WATER 2500 651 0.0 CR-6-W WATER 0.05 WATER 2300 505 290 720,000 0.10 WATER 2500 516 0.0 CR-7-W WATER 0.07 WATER 2280 448 215 792,000 0.10 WATER 2500 456 a.a NOTES: (1) Opening time measured from time of energizing solenoid until valve reaches full open position.  
OF CROSBY RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS                                   LEAKAGE MEASUREMENTS         COMMENTS VALVE TOTAL '/,\LVE (!)       VALVE INLET           OUTLET   FLOW   TOTAL VALVE (2)               VALVE INLET   LEAKAGE TEST   TEST     OPENI~G TIME     FLUID   PRESS. TEMP. PRESS. RATE     CLOSING TIME     MEDIA   PRESS. TEMP. RATE NO. TYPE         (SEC)                 (PSIA)     (OF)     (PSIA)   (LBM/HR)     (SEC)                 (PSIA)     (Of) (GPM)
CR-1-S STEAM       0.10         STEAM     2280     661         57     162,000     0.20         STEAM     2000     637     0.0 CR-2-S STEAM       0.07         STEAM     2420     671         560     165,600     0.14         STEAM     2485     653     0.008 CR-3-W WATER       0.10         WATER     622     382         122     410,400     0.20         WATER       660     386     0.0 CR-5-W 11,\TER     0.10         WATER     2400     645         150     385,200     0.20         WATER     2500     651     0.0 CR-6-W WATER       0.05         WATER     2300     505         290     720,000     0.10         WATER     2500     516     0.0 CR-7-W WATER       0.07         WATER     2280     448         215     792,000     0.10         WATER     2500     456     a.a
+::>
I l.D NOTES:
(1) Opening time measured from time of energizing solenoid until valve reaches full open position.
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.
COMMENTS I -I Back-At pressure Orifice Area Test No. Test Type ( in2) Fluid 25-CR-lS Steam 10.0 Steam 26-CR-6S Steam 9.62 Steam (Pre load) 27-CR-2W Water 9.62 Water .j::> I 28-CR-3W Water 9.62 Water N 0 29-CR-lS Steam 11. 7 Steam 30-CR-lS Steam 8.82 Steam 31-CR-4S/W Trans it ion 8.82 Steam 32-CR-SW/W Water 8.82 Water Seal Simulation 33-CR-7W/W Water 8.82 Water Seal Simulation 34-CR-BW/W Water 8.82 Water Seal Simulation Notes: ( 1) PS-4 was inoperative during this test. (2) shown corresponds to maximum moment Valve Temp (OF) 656 657 104 437 656 656 656 469 294 118 EPRI/WYLE PHASE Ill PORV TEST DATA TABLE 4.2.l-3a "AS TESTED" WYLE PHASE II I TEST MATRIX FOR THE CROSBY RELIEF VALVE INITIAL CONDITIONS Inlet In Accumulator Test Press. Temp Press. Duration (psi a) Fluid (OF) (psi a) (seconds) 2,505 Stearn 659 2,505 10 2,505 Steam 659 2,505 10 694 Water 108 694 10 695 Water 448 695 10 2,505 Steam 659 2,505 10 2,505 Steam 658 2,505 10 2,510 Water 649 2,510 15 2,505 Water 646 2,505 15 2,505 Water 648 2,505 15 2,500 Water 645 2,500 15 applied when valve was in the g/closing process TRANSIENT CONDITIONS Valve Inlet Pressure Maximum Maximum Maximum at Discharge Bending Valve Closure Pipe Moment Acceleration Signal Press. Induced(2)Induced (psia) (psi a) (in-lb) ( g.' s) 2,050 (1) N/A 8.0 2,037 (1) 31,600 6.7 620 3 N/A 8.2 655 160 N/A 11.6 2,050 74 N/A 6.4 2,060 380 N/A 10.4 2,313 (1) N/A 9.2 2,290 560 N/A 8.2 2,300 580 N/A 8.0 2,290 575 N/A 9.4 *
 
* EPRI/WYLE PHASE III PORV TEST DATA TABLE 4.2.l-3b  
EPRI/WYLE PHASE Ill PORV TEST DATA TABLE 4.2.l-3a "AS TESTED" WYLE PHASE II I TEST MATRIX FOR THE CROSBY RELIEF VALVE INITIAL CONDITIONS                                                     TRANSIENT CONDITIONS Valve Inlet Back-          At Valve Inlet                  In Accumulator                   Pressure Maximum    Maximum Maximum pressure                                                                          at      Discharge  Bending Valve Orifice                                                                  Test     Closure Pipe        Moment    Acceleration Area                Temp      Press.               Temp       Press. Duration Signal    Press.      Induced(2)Induced Test No.      Test Type    ( in2)    Fluid    (OF)      (psi a)   Fluid     (OF)       (psi a) (seconds) (psia)   (psi a)     (in- lb)   ( g.' s) 25-CR-lS      Steam          10.0    Steam      656      2,505      Stearn      659      2,505    10      2,050     (1)       N/A         8.0 26-CR-6S      Steam            9.62  Steam      657      2,505      Steam      659      2,505    10      2,037     (1)       31,600       6.7 (Pre load) 27-CR-2W      Water            9.62  Water      104        694      Water      108        694    10          620     3       N/A         8.2
  .j::>
I N    28-CR-3W      Water            9.62  Water      437        695      Water      448        695    10          655   160       N/A       11.6 0
29-CR-lS      Steam          11. 7  Steam      656      2,505      Steam      659      2,505    10      2,050     74       N/A         6.4 30-CR-lS      Steam            8.82  Steam      656      2,505      Steam      658      2,505    10      2,060     380       N/A       10.4 31-CR-4S/W    Trans it ion    8.82  Steam      656      2,510      Water      649      2,510    15      2,313     (1)       N/A         9.2 32-CR-SW/W    Water            8.82  Water      469      2,505      Water      646      2,505    15      2,290     560       N/A         8.2 Seal Simulation 33-CR-7W/W    Water            8.82  Water      294      2,505      Water      648      2,505    15      2,300     580       N/A         8.0 Seal Simulation 34-CR-BW/W    Water            8.82  Water      118      2,500      Water      645      2,500    15      2,290     575       N/A         9.4 Seal Simulation Notes:
( 1) PS-4 was inoperative during this test.
(2)        shown corresponds to maximum moment applied when valve was in the          g/closing process
* EPRI/WYLE PHASE III PORV TEST DATA TABLE 4.2.l-3b


==SUMMARY==
==SUMMARY==
OF CROSBY RELIEF VALVE_ PERFORMANCE Test 25-26-27-28-29-30-31-32-33-34-Number CR-lS CR-6S CR-2W rR-3W ('O _ ! S CR-lS CR-4S/W CR-SW/W CR-7W/W CR-BW/W Pre-Test Leakage(!)
OF CROSBY RELIEF VALVE_ PERFORMANCE Test                               25-       26-       27-         28-         29-         30-       31-       32-       33-       34-Number                               CR-lS     CR-6S       CR-2W       rR-3W     ('O _ ! S   CR-lS     CR-4S/W   CR-SW/W   CR-7W/W   CR-BW/W Pre-Test Leakage(!)
Media Steam Steam Water Water Steam Steam Water Water Water Water Pressure (psia) 2,550 2,490 739 729 2,512 2,550 2,500 2,500 2,323 2,586 Temp (OF) 647 668 109 407 669 670 580 450 280 115 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.005 Transient Performance Total Valve Opening Time (sec) 0.15 0.17 0.07 0.09 0.15 0.18 0.16 0.08 0.08 0.08 Valve Flowrate (lb/Hr) 158,400 151,200 486,000 316,800 158,400 160,200 316,800 367' 200 374,400 388,800 Corresponding Valve Inlet Press (psia) 2,276 2,090 630 663 2,250 2,265 2,387 2,390 2,390 2,360 +>> I Corresponding Valve N ....... Inlet Temp (OF) 645 634 108 440 644 644 644 636 632 632 Corresponding Valve Outlet Press (psia) (2) (2) 1. 153 670 365 (2) 490 494 503 Corresponding Valve Temp (OF) 313 342 109 361 Corresponding Test Time 316 430 454 465 467 470 Relative to Open Corrwnand (sec) 4.1 8.3 6.3 3.7 4.8 4.5 6.9 4.9 4.7 6.4 Inlet Pressure at Beginning of Valve Closure {psia) 2,045 2,035 620 650 2,050 2,060 2,310 2,300 2,300 2,290 Total Valve Closure Time (sec) 0.15 0.14 0.18 0.27 0.13 0.12 0.25 0.24 0.29 0.55 Post-Test Leakage(!)
Media                         Steam     Steam       Water       Water     Steam       Steam     Water     Water       Water     Water Pressure (psia)               2,550     2,490         739         729     2,512       2,550     2,500     2,500     2,323     2,586 Temp (OF)                         647       668       109         407         669         670       580       450       280       115 Leak Rate (GPM)             0.0013     0.0013     0.0013     0.0013     0.0013     0.0013   0.0013     0.0013     0.0013     0.005 Transient Performance Total Valve Opening Time (sec)                 0.15       0.17       0.07       0.09       0.15         0.18     0.16       0.08       0.08       0.08 Valve Flowrate (lb/Hr)       158,400   151,200     486,000     316,800   158,400     160,200   316,800   367' 200   374,400   388,800 Corresponding Valve
Media Steam Steam Water Water .Steam Steam Water Water Water Water Pressure (psia) 2,495 2,500 698 695 2,555 2,540 2,530 2,590 2,417 2,510 Temp (OF) 595 668 107 382 672 671 587 523 408 375 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 1.13 0.0013 0.0013 0.0013 0.0013 0.004 Notes: ( 1) Re.corded leakages of .0013 GPM (2) PS-4 in-operative indicate measured values of less than or equal to .0013 GPM
+>>                    Inlet Press (psia)       2,276     2,090         630         663     2,250 I
' ' *
2,265     2,387     2,390     2,390     2,360 N              Corresponding Valve Inlet Temp (OF)             645       634       108         440         644         644       644       636       632       632 Corresponding Valve Outlet Press (psia)         (2)         (2)       1.         153         670         365       (2)       490       494       503 Corresponding Valve Temp (OF)                   313       342       109         361         316         430       454       465       467       470 Corresponding Test Time Relative to Open Corrwnand (sec)             4.1       8.3       6.3         3.7         4.8         4.5       6.9       4.9       4.7       6.4 Inlet Pressure at Beginning of Valve Closure {psia)           2,045     2,035         620         650     2,050       2,060     2,310     2,300       2,300     2,290 Total Valve Closure Time (sec)                 0.15       0.14       0.18       0.27       0.13         0.12     0.25       0.24       0.29     0.55 Post-Test Leakage(!)
* 4.3 TARGET ROCK RELIEF VALVE 4.3.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Target Rock relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance cjata for the Target Rock relief valve tested at each of the test facilities.
Media                         Steam     Steam       Water       Water     .Steam       Steam     Water     Water     Water     Water Pressure (psia)               2,495     2,500         698         695     2,555       2,540     2,530     2,590     2,417     2,510 Temp (OF)                         595       668         107         382         672         671       587       523       408       375 Leak Rate (GPM)               0.0013     0.0013     0.0013     0.0013       1.13     0.0013   0.0013     0.0013     0.0013     0.004 Notes:
Test Facility Marshall Wy l e (Phase I I I ) 4.3.2 frincipal Observations M1rshall Steam Station 11 As Tested" Test Matrix Table 4.3.l-la
( 1) Re.corded leakages of .0013 GPM indicate measured values of less than or equal to .0013 GPM (2) PS-4 in-operative
* 4.3.l-2a Valve Performance Data Table 4.3.l-lb 4.3.l-2b Tile v a.l ve fu 11 y opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles. WJle Phase III Tile valve fully opened on demand and fully closed on demand in eleven (11) oi the twelve (12) test cycles. The valve did not close on demand when the ftill pressure 2500 psi, water seal simulation test (test number 7-TR-7W) was performed.
 
The water just upstream of the valve was llOOF water. For this test, the valve opened on.demand.
4.3 TARGET ROCK RELIEF VALVE 4.3.l "As Tested" Test Matrices and Valve Performance Data Tests were     performed on the Target Rock relief valve model at the Marshall Steam Station and     during Phase III of the Wyle Test Program. The following is the list of tables that     contain the "as tested" test matrices and valve performance cjata for the Target Rock     relief valve tested at each of the test facilities.
Upon de-energizing the valve for closure, the valve remained opened for approximately 12 seconds and then closed at an inlet pressure of 2130 psia. The valve was removed from the tE'st facility and disassembled by the Target Rock representative following this test, test 9-TR-6W and again upon completion of all testing of this valve design. No damage was observed which might affect the ability of the valve to open/close on demand . 4-23
Test                             11 As Tested" Test       Valve Performance Facility                                Matrix Table             Data Table Marshall                                  4.3.l-la
* Valve Opentng/Closing Times Magnetic limit switches were installed on the casing surrounding the valve stem which provided an indication of stem position.
* 4.3.l-lb Wy l e (Phase I I I )                      4.3.l-2a              4.3.l-2b 4.3.2 frincipal Observations M1rshall Steam Station
Data from these limit switches was used to obtain stroke and total opening times during the Marshall test. During Wyle testing of this valve, these limit switches began to exhibit sensitivity to test vibrations.
* Tile va.l ve fu 11 y opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles.
Therefore, for all Wyle tests of this valve, stroke times are not reported and estimates of total opening/closing times were obtained utilizing accelerometer and inlet pressure measurements.
WJle Phase III Tile valve fully opened on demand and fully closed on demand in eleven (11) oi the twelve (12) test cycles. The valve did not close on demand when the ftill pressure 2500 psi, water seal simulation test (test number 7-TR-7W) was performed. The water just upstream of the valve was llOOF water. For this test, the valve opened on.demand. Upon de-energizing the valve for closure, the valve remained opened for approximately 12 seconds and then closed at an inlet pressure of 2130 psia. The valve was removed from the tE'st facility and disassembled by the Target Rock representative following this test, test 9-TR-6W and again upon completion of all testing of this valve design. No damage was observed which might affect the ability of the valve to open/close on demand .
This method for estimating opening/tlosng times was confirmed by evaluation of data from other valves tested with direct stem position indication available . 4-25 I N m * "AS TESTED" MARSHALL CONDITIONS VALVE INLET *TEST TEST FLUID PRESS. TEMP. NO. TYPE (PSIA) (OF) STEAM STEAM 2475 (SAT. J 2 STEAM STEAM 2455 (SAT.) STEAM STEAM 2435 (SAT.) 4 STEAM STEAM 2445 (SAT.) STEAM STEAM 2455 (SAT.) STEAM STEAM 2455 (SAT.) STEAM STEAM 2445 (SAT.) 8 STEAM STEAM 2425 (SAT.) 9 STEAM STEAM 2455 (SAT.) 10 STEAM STEAM 2475 (SAT.) 11 STEAM STEAM 2455 (SAT.) NOTES: (I) Maximum Quasi steady discharge pipe pressure.  
* 4-23
(2) Not recorded.
 
EPRI/ MARSHALL PORV TEST DATA (3) TABLE 4.3.l-la TEST MATRIX FOR THE TARGET ROCK RELIEF VALVE AT VALVE OPENING TRANSIENT CONDITIONS IN ACCUMULATOR TEST VALVE INLET MAXIMUM p) DURATION PRESS. WHEN DISCHARG FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS, (PSIA) (OF) TO CLOSE VALVE (PSIA) (PSIA) SAME AS VALVE INLET 68 2310 465 31 2310 465 59 2295 465 25 2320 465 25 2335 475 60 2295 155 28 2305 155 26 2295 155 29 2335 155 30 2335 155 I (2) 2325 455 ' (3) Test results are for evaluation tests only. Total of 23 supplementary valve actuation cycles were performed under similar conditions . * *
Valve Opentng/Closing Times Magnetic limit switches were installed on the casing surrounding the valve stem which provided an indication of stem position. Data from these limit switches was used to obtain stroke and total opening times during the Marshall test. During Wyle testing of this valve, these limit switches began to exhibit sensitivity to test vibrations. Therefore, for all Wyle tests of this valve, stroke times are not reported and estimates of total opening/closing times were obtained utilizing accelerometer and inlet pressure measurements. This method for estimating opening/tlosng times was confirmed by evaluation of data from other valves tested with direct stem position indication available .
* EPRI / MARSHALL PORV TEST DATA ( 3) TABLE 4.3.1-lb SUl+lARY OF TARGET ROCK RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VALVE (1) VAL VE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TrME MEDIA PRESS. TEMP. . RATE NO. TYPE (SEC) (PSIA} (OF) (PSIA) (LBM/HR} (SEC) (PSIA) (OF) (GPM) STEAM 0.440 STEAM 2310 (SAT.) 465 170,000 0.220 2455 n n A pre-operational leakage u.u test showed 0.0 GPM leakage 2 STEAM 0.520 * * * ..
4-25
* 0.210 *
 
* STEAM 0.595 .. * *
EPRI/    MARSHALL          PORV TEST DATA (3)
* 0.200 *
TABLE    4.3.l-la "AS TESTED"     MARSHALL     TEST MATRIX FOR THE TARGET ROCK RELIEF VALVE CONDITIONS AT VALVE OPENING                                        TRANSIENT CONDITIONS
* STEAM 0.600 * *
    *TEST VALVE INLET                         IN ACCUMULATOR                    TEST DURATION VALVE INLET PRESS. WHEN MAXIMUM DISCHARG p)
* 0.200 *
TEST         FLUID       PRESS.       TEMP.       FLUID        PRESS.        TEMP.         (SEC)
* 5 STEAM 0.610 " * * *
NO.          TYPE                                                                                                      SIGNAL GIVEN        PIPE PRESS, (PSIA)      (OF)                     (PSIA)        (OF)                       TO CLOSE VALVE          (PSIA)
* 0.200 SHA'1 2475 (SAT.) o.o 6 STEAM 0.490 STEAM 2295 (SAT.) 155 169,000 0.210 * *
(PSIA)
* STEAM 0.520 .. 0.210 * *
STEAM       STEAM         2475        (SAT. J          SAME AS VALVE INLET                  68              2310                465 2          STEAM       STEAM         2455       (SAT.)                                                 31              2310                465 STEAM        STEAM         2435      (SAT.)                                                   59              2295                465 4          STEAM       STEAM         2445       (SAT.)                                                   25              2320              465 STEAM       STEAM       2455        (SAT.)                                                   25              2335              475 STEAM         STEAM       2455       (SAT.)                                                   60              2295                155 STEAM       STEAM         2445      (SAT.)                                                   28              2305                155
* 8 STEAM 0. 570 * * * *
~
* 0.190 * * * * ..,,. 9 STEAM 0.620 * * *
I      8          STEAM       STEAM         2425      (SAT.)
* 0.170 * " * .. I N JO STEAM 0.650 * * *
N                                                                                                                26              2295                155 m      9          STEAM        STEAM        2455      (SAT.)                                                   29              2335                155 10          STEAM        STEAM        2475      (SAT.)                                                  30              2335                155 11          STEAM        STEAM        2455      (SAT.)                        I                          (2)             2325                455 NOTES:
* 0.190 * .. * * -...J 11 STEAM 0.585 * * *
(I)  Maximum Quasi steady discharge pipe pressure.
* 0.210 STEAM 2460 (SAT.) 0.0 not applicable to this test NOTES: (1) Opening time measured from time of energizing solenoid until valve reaches full open position.  
(2)   Not recorded.
(3)  Test results are for evaluation tests only. Total of 23 supplementary valve actuation cycles were performed under similar conditions .
 
EPRI /
* MARSHALL    PORV TEST DATA ( 3)
TABLE 4.3.1-lb SUl+lARY OF TARGET ROCK RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS                                      LEAKAGE MEASUREMENTS              COMMENTS VALVE TOTAL VALVE (1)         VAL VE INLET            OUTLET    FLOW    TOTAL VALVE (2)               VALVE INLET     LEAKAGE TEST      TEST    OPENING TIME    FLUID    PRESS. TEMP.      PRESS. RATE    CLOSING TrME      MEDIA    PRESS. TEMP.    . RATE NO.      TYPE          (SEC)                (PSIA}    (OF)       (PSIA)   (LBM/HR}      (SEC)                  (PSIA)    (OF)    (GPM)
STEAM        0.440      STEAM      2310    (SAT.)                                                                               A pre-operational leakage 465    170,000    0.220          STE~.M    2455      (SA~.}
n n u.u  test showed 0.0 GPM leakage 2       STEAM      0.520        *          *        *          .
* 0.210            *
* STEAM        0.595                    .        *          *
* 0.200                      *
* STEAM        0.600                    *        *
* 0.200            *
* 5      STEAM      0.610          "          *        *          *
* 0.200          SHA'1      2475      (SAT.)   o.o 6      STEAM       0.490        STEAM     2295    (SAT.)       155    169,000     0.210            *        *
* STEAM       0.520                                         ..                 0.210             *        *
* 8        STEAM       0. 570        *         *       *           *
* 0.190            *         *         *         *
..,,. 9      STEAM      0.620          *                   *           *
* 0.170            *        "          *        .
N I
-...J JO        STEAM       0.650          *          *        *
* 0.190            *         .          *
* 11        STEAM       0.585                    *       *           *
* 0.210          STEAM      2460      (SAT.)    0.0 not applicable to this test NOTES:
(1) Opening time measured from time of energizing solenoid until valve reaches full open position.
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position, (3) Test results are for evaluation tests only. Total of 23 supplementary valve actuation tests were performed under similar conditions.
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position, (3) Test results are for evaluation tests only. Total of 23 supplementary valve actuation tests were performed under similar conditions.
EPRl/WYLE Phase Ill PORV TEST DATA TABLE 4.3.>Zo "AS TESTED" WYLE Pll/\SE Ill TEST Ml\TRIX FOR THE TARGET ROCK RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS Valve Inlet Back-At Valve Inlet In Accumulator Pressure Maximum Maximum Maximum pressure at Discharge Bending Valve Orifice Test Closure Pipe Moment Acceleration Area Temp Press. Temp Press. Duration Signal Press. Induced(l)Induced Test No. Test Type ( in2) Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (in-lb) (g's) 1-TR-lS Steam 9.62 Steam 660 2521 Steam 670 2521 7 2132 320 N/A 5.0 2-TR-lS Steam 9.62 Steam 669 2504 Steam 670 2504 7 2134 330 N/A 8.5 3-TR-3W Water 9.62 Water 447 715 Water 454 715 70 639 170 N/A 8.7 4-TR-5\.1 Water 9.62 Water 645 2536 Water 653 2536 15 2293 450 N/A 3.6 -+:> I N 5-TR-2W Water OJ 9.62 Water 114 690 Water 114 690 10 616 1 N/A 13.3 6-TR-4W Water 9.62 Water 451 2508 Water 461 2508 10 2196 395 N/A 7.4 7-TR-7W Water 9.62 Seal Water 113 2505 Water 656 2505 27 2271 520 N/A 5.6 Simulation 8-TR-5W Water 9.62 Water 648 2494 Water 658 24g4 10 2320 430 N/A 4.4 9-TR-6W 9.62 Water 645 2490 Water 657 2490 10 2302 425 N/A 8.4 17-TR-lS Steam 9.62 Steam 657 2510 Steam 659 2510 10 2028 325 N/A 4.9 18-TR-BS Steam 9.62 (Pre load) Steam 656 2505 Steam 658 2505 10 2020 315 32,900 3.3 l9-TR-9S/W Trans it ion 9.62 Steam 656 2500 Water 642 2500 10 2310 435 N/A 5.2 Notes: (1) Value shown corresponds to maximum moment applied while valve was in opening/closing process * * *
 
* EPRJ/WYLE Phase III PORV TEST DATA TABLE 4.3.l-2b  
EPRl/WYLE Phase Ill PORV TEST DATA TABLE 4.3.>Zo "AS TESTED" WYLE Pll/\SE Ill TEST Ml\TRIX FOR THE TARGET ROCK RELIEF VALVE INITIAL CONDITIONS                                                   TRANSIENT CONDITIONS Valve Inlet Back-           At Valve Inlet                   In Accumulator                   Pressure Maximum     Maximum Maximum pressure                                                                           at       Discharge   Bending Valve Orifice                                                                 Test     Closure Pipe         Moment Area               Temp                                                                                           Acceleration Press.                 Temp       Press. Duration Signal   Press.     Induced(l)Induced Test No. Test Type     ( in2)   Fluid     (OF)       (psi a)     Fluid     (OF)       (psi a) (seconds) (psi a) (psi a)     (in-lb)   (g's) 1-TR-lS     Steam         9.62     Steam     660       2521       Steam       670       2521     7       2132     320       N/A       5.0 2-TR-lS     Steam         9.62     Steam     669       2504     Steam       670       2504     7       2134     330       N/A       8.5 3-TR-3W     Water         9.62     Water     447         715     Water       454         715     70         639   170       N/A       8.7 4-TR-5\.1   Water         9.62     Water     645       2536     Water       653       2536   15
-+:>
2293     450       N/A       3.6 I
N OJ    5-TR-2W       Water         9.62     Water     114         690     Water       114         690   10         616       1       N/A     13.3 6-TR-4W       Water       9.62       Water     451       2508     Water       461       2508   10       2196     395       N/A       7.4 7-TR- 7W     Water       9.62       Water     113       2505     Water       656       2505     27 Seal                                                                                              2271     520       N/A       5.6 Simulation 8-TR-5W     Water         9.62       Water     648       2494       Water       658       24g4     10       2320     430       N/A       4.4 9-TR-6W     ~later        9.62     Water     645       2490       Water       657       2490     10       2302     425       N/A       8.4 17-TR-lS       Steam         9.62     Steam     657       2510       Steam       659       2510     10       2028     325       N/A       4.9 18-TR-BS       Steam         9.62     Steam     656       2505     Steam       658       2505 (Pre load)                                                                              10       2020     315       32,900   3.3 l9-TR-9S/W     Trans it ion 9.62     Steam     656       2500     Water       642       2500   10       2310     435       N/A       5.2 Notes:
(1) Value shown corresponds to maximum moment applied while valve was in opening/closing process
 
EPRJ/WYLE Phase III PORV TEST DATA TABLE 4.3.l-2b


==SUMMARY==
==SUMMARY==
OF TARGET ROCK RELi EF VALVE PERFORMANCE Test 1-2-3-4-5-6-7-8-9-17-18-19-Number TR-lS TR-lS TR-3W TR-SW TR-2W TR-4W TR-7W TR-SW TR-6W TR-lS TR-BS TR-9W/W Pre-Test Leakage (1) Media Steam Steam Water Water Water Water Water Water Water Steam Steam Water Pressure (psia) 2,500 2,512 675 2,515 673 2,545 2,505 2,521 2,478 2,505 2,485 2,500 Temp (OF) 668 666 447 645 114 448 113 583 589 .668 668 590 Leak. Rate (GPM) 0.0013 0.0013 0.0013 0.0013 .0021 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) 0.35 .300 0.28 0.25 0.21 0.26 0.20 0.29 0.27 0.396 0.365 0.30 Valve Flowrate (lb/Hr) 171, 844 167,040 266,400 367 ,200 442,800 698,400 (2) 356,400 360,000 165,600 162,000 377,300 Corresponding Valve I Inlet Press. (psia) 2,339 2,260 669 2,394 N l..D Corresponding Valve 635 2,280 N/A 2,386 2,363 2,243 2,225 2,364 Inlet Temp (OF) 664 659 451 649 115 457 N/A 654 650 644 643 633 Corresponding Valve Outlet Press. (psia) 329 325 167 444 0.6 Corresponding Valve 390 N/I\ 430 423 320 312 430 Outlet Temp: (Of) 416 414 372 460 115 Corresponding Test Time 444 N/A 460 460 411 412 455 Relative to Open CormJand (sec) 2.0 4.8 4.0 5.2 3.2 Inlet Pressure at Beginning 4.4 N/A 4.3 4.3 4.6 4.9 5.1 of Valve Closure (psia) 2,125 2,130 640 2,290 620 Total Valve Closure Time 2,190 130 2,320 2,300 2,025 2,015 2,310 (sec) 0.31 .31 .690 0.44 0.84 Leakage (1) 0.55 12.33 0.46 0.43 0.232 0.24 0.25 Media Steam Steam Water Water Water Water Water Water Water Steam Steam Wate.r Pressure (psia) 2,500 2,500 700 2,515 669 2,523 2,356 2,415 2,405 2,525 2,500 2,482 Temp (OF) 668 665 456 650 112 454 432 552 609 669 668 632 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.12(3) 0.0013 0.0013 0.0013 0*.0013 0.0013 Notes: (1) Recorded leakages of .0013 GPM indicate measured values less than or equal to .0013 GPM (2) VPnturi pressure sensor over-ranQPd (3) This leakage is considered an upper bound as it includes any test facility by-pass valve packing leakage rates.
OF TARGET ROCK RELi EF VALVE PERFORMANCE Test                               1-       2-         3-         4-         5-       6-       7-         8-       9-       17-     18-       19-Number                               TR-lS   TR-lS     TR-3W       TR-SW     TR-2W     TR-4W   TR-7W       TR-SW     TR-6W   TR-lS     TR-BS     TR-9W/W Pre-Test Leakage (1)
' '
Media                         Steam     Steam     Water       Water     Water     Water   Water       Water     Water   Steam     Steam     Water Pressure (psia)                 2,500   2,512         675     2,515         673   2,545   2,505       2,521     2,478   2,505     2,485     2,500 Temp (OF)                         668     666         447         645       114       448     113       583       589     .668       668       590 Leak. Rate (GPM)             0.0013   0.0013     0.0013     0.0013       .0021   0.0013   0.0013     0.0013   0.0013   0.0013   0.0013   0.0013 Transient Performance Total Valve Opening Time (sec)                   0.35     .300       0.28       0.25       0.21       0.26     0.20       0.29     0.27   0.396     0.365     0.30 Valve Flowrate (lb/Hr)                 171, 844 167,040   266,400     367 ,200   442,800 698,400         (2) 356,400   360,000   165,600 162,000   377,300
* 4.4 CON1ROL COMPONENTS RELifF VALVE 4.4.1 "As Tested" Test Matrices and Valve Performance Data Tests were_ performed on the Control Components relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Control Components relief valve tested at each of the test facilities.
~
Test Facility Marsha 11 Wyle (Phase III) 4.4.2 Principal Observations Marsh1ll Steam Station "As Tested" Test Matrix Table 4.4.l-la 4.4.l-2a Valve Performance Data Table 4.4.l-lb 4.4. l-2b The v.ilve fully opened on demand and fully closed on demand for each of the (17) evaluation test cycles. The valve fully opened and closed on demand during all seven (7) tests with normal air supply (air utilized to open Bnd close valve) avail ible. An additional ten (10) tests were performed on this valve utili 'ing the spring force only to close the valve (without air assist on closu*'e).
Corresponding Valve I
During all of these tests, the valve opened fully on demand.
Inlet Press. (psia)       2,339     2,260         669     2,394         635 N
during five (5) of these tests, the valve exhibited delay on closu1'e.
l..D 2,280       N/A     2,386   2,363     2,243   2,225     2,364 Corresponding Valve Inlet Temp (OF)               664     659         451         649         115       457     N/A       654       650     644       643       633 Corresponding Valve Outlet Press. (psia)           329     325         167         444       0.6       390     N/I\       430       423     320       312       430 Corresponding Valve Outlet Temp: (Of)             416     414         372         460       115       444     N/A       460       460     411       412       455 Corresponding Test Time Relative to Open CormJand (sec)                         2.0     4.8         4.0         5.2       3.2       4.4     N/A       4.3       4.3     4.6       4.9       5.1 Inlet Pressure at Beginning of Valve Closure (psia)   2,125     2,130         640       2,290         620   2,190 Total Valve Closure Time                                                                     *~. 130     2,320     2,300   2,025     2,015     2,310 (sec)                       0.31       .31       .690       0.44       0.84     0.55   12.33         0.46     0.43   0.232     0.24     0.25
Closure delay times ranging from two (2) to forty (40) seconds were _c,bserved.
    ~ost-Test Leakage (1)
Closure delays of less than three ( 3) seconds were observed under steam and steam/preload conditions.
Media                      Steam    Steam      Water       Water       Water     Water   Water       Water   Water     Steam   Steam     Wate.r Pressure (psia)               2,500     2,500         700       2,515         669   2,523   2,356       2,415   2,405     2,525   2,500     2,482 Temp (OF)                     668       665       456         650         112       454       432       552     609       669       668     632 Leak Rate (GPM)           0.0013   0.0013     0.0013     0.0013     0.0013   0.0013     0.12(3) 0.0013   0.0013   0.0013   0*.0013   0.0013 Notes:
Closure delays of twenty (20) and iorty (40) seconds were observed under 2500 psia, 6500f water In all cases where valve closure delays were observed, full closui*e occurred at an inlet pressure at or above 2035 psia. 4-31 I I 1 , Tests under each of the conditions which resulted in closure delays were repeated utilizing air for both opening and closing the valve. In all such tests. the valve opened and closed on demand. Following the first test resulting in a significant closure delay and again upon completion of testing, the valve was disassembled and inspected by the Control Components representative.
(1) Recorded leakages of .0013 GPM indicate measured values less than or equal to .0013 GPM (2) VPnturi d~lta pressure sensor over-ranQPd (3) This leakage is considered an upper bound as it includes any test facility by-pass valve packing leakage rates.
No damage was observed which might affect the ability of the valve to open or close on demand. 4-33 I w "AS TESTED" HAR SHALL CONDITIONS VALVE INLET TEST TEST FLUID PRESS. TEMP. NO. TYPE (PSIA) (Of) STEAM. STEAM 2455 (SAT.) STEAM STEAM 2445 (SAT.) STEAM STEAM 2425 (SAT.) STEAM STEAM 2425 (SAT.) STEAM STEAM 2435 (SAT.) 6 STEAM STEAM 2435 (SAT.) STEAM STEAM 2405 (SAT.) 8 STEAM STEAM 2395 (SAT.) 9 STEAM STEAM 2455 (SAT.) 10 STEAM STEAM 2445 (SAT.) 11 STEAM STEAM 2435 (SAT .1 12 STEAM STEAM 2435 (SAT.) 13 STEAM STEAM 2425 (SAT.) 14 STEAM STEAM 2405 (SAT.) 15 STEAM STEAM 2395 (SAT.) 16 STEAM STEAM 2405 (SAT.) 17 STEAM STEAM 2415 (SAT.) NOTES: (I) Maximum Quast steady pipe pressure. ( 2) Not recorded.
* 4.4 CON1ROL COMPONENTS RELifF VALVE 4.4.1 "As Tested" Test Matrices and Valve Performance Data Tests were_ performed on the Control Components relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Control Components relief valve tested at each of the test facilities.
EPRI/ MARSHALL PORV TEST DATA ( 3) TABLE 4.4. I-la TEST MATRIX FOR THE CONTROL COMPONENTS RELIEF VALVE AT VALVE OPENING TRANSIENT CONDITIONS IN ACCUMULATOR TEST VALVE INLET MAXIMUM P'
Test                         "As Tested" Test          Valve Performance Facility                           Matrix Table                Data Table Marsha 11                           4.4.l-la                   4.4.l-lb Wyle (Phase III)                    4.4.l-2a                  4.4. l-2b 4.4.2 Principal Observations Marsh1ll Steam Station The v.ilve fully opened on demand and fully closed on demand for each of the seven~een (17) evaluation test cycles.
* DUflA T ION PRESS. llHEN OISCHARG FLU!O PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS. (PSIA) (OF) TO CLOSE VALVE (PSIA) PSIA) SAME AS VALVE INLET 67 2155 615 30 2175 615 31 2175 615 37 2175 615 37 2195 615 24 2)65 615 25 2145 615 27 2145 615 65 2155 220 18 2095 215 20 2175 215 18 2180 215 23 2170 215 17 2155 215 19 2150 215 22 2155 215 (2) 2170 615 ( 3) Test results are for evaluation tests only. Total of 33 supplementary valve actuation cycles were perfonned under similar conditions . * . -
The valve fully opened and closed on demand during all seven (7) tests perfo~med  with normal air supply (air utilized to open Bnd close valve) avail ible. An additional ten (10) tests were performed on this valve utili 'ing the spring force only to close the valve (without air assist on closu*'e). During all of these tests, the valve opened fully on demand.
EPRI I MARSHALL PORV TEST DATA ( 3) TABLE 4.4.l-lb FLOW MEASUREMENT CONDITIONS HEASUREHENTS COHHENTS VALVE TOTAL VALVE (I) VALVE !NLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING T!ME FLUID PRESS. TEHP. PRESS. RATE CLOSING TIME PRESS. TEHP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM) STEAH I.BO STEAM 2155 (SAT.) 605 225,000 A pre-operational leakage I. 00 .
Howev,~r,  during five (5) of these tests, the valve exhibited delay on closu1'e. Closure delay times ranging from two (2) to forty (40) seconds were _c,bserved. Closure delays of less than three ( 3) seconds were observed under steam and steam/preload conditions. Closure delays of twenty (20) and iorty (40) seconds were observed under 2500 psia, 6500f water condi~ions. In all cases where valve closure delays were observed, full closui*e occurred at an inlet pressure at or above 2035 psia.
2445 (SAT. J 0.026 test showed 0.0 GPM leakage I. 70 *
4-31
 
I I 1 ,
Tests under each of the conditions which resulted in closure delays were repeated utilizing air for both opening and closing the valve. In all such tests. the valve opened and closed on demand.
Following the first test resulting in a significant closure delay and again upon completion of testing, the valve was disassembled and inspected by the Control Components representative. No damage was observed which might affect the ability of the valve to open or close on demand.
4-33
 
EPRI/    MARSHALL        PORV TEST DATA ( 3)
TABLE    4.4. I-la "AS TESTED"   HAR SHALL     TEST MATRIX FOR THE CONTROL COMPONENTS RELIEF VALVE CONDITIONS AT VALVE OPENING                                          TRANSIENT CONDITIONS VALVE INLET                         IN ACCUMULATOR                    TEST
* DUflA TION VALVE INLET PRESS. llHEN    MAXIMUM OISCHARG P'
TEST          TEST          FLUID        PRESS. TEMP.         FLU!O        PRESS.        TEMP.          (SEC)        SIGNAL GIVEN    PIPE PRESS.
NO.         TYPE                       (PSIA)     (Of)                       (PSIA)        (OF)                        TO CLOSE VALVE        (PSIA)
PSIA)
STEAM.       STEAM         2455     (SAT.)           SAME AS VALVE INLET                      67              2155              615 STEAM       STEAM         2445     (SAT.)                                                     30              2175              615 STEAM       STEAM         2425     (SAT.)                                                     31              2175              615 STEAM        STEAM         2425     (SAT.)                                                     37              2175              615 STEAM       STEAM         2435     (SAT.)                                                     37              2195              615
~
I w  6           STEAM       STEAM         2435     (SAT.)                                                     24              2)65              615
~
STEAM       STEAM         2405     (SAT.)                                                     25              2145              615 8           STEAM       STEAM         2395     (SAT.)                                                     27              2145              615 9           STEAM       STEAM         2455     (SAT.)                                                     65              2155              220 10           STEAM       STEAM         2445     (SAT.)                                                     18              2095              215 11           STEAM       STEAM         2435     (SAT .1                                                     20              2175              215 12           STEAM       STEAM         2435     (SAT.)                                                     18              2180              215 13           STEAM       STEAM         2425     (SAT.)                                                     23              2170              215 14           STEAM       STEAM         2405     (SAT.)                                                     17              2155              215 15           STEAM       STEAM         2395     (SAT.)                                                     19              2150              215 16           STEAM       STEAM         2405     (SAT.)                                                     22              2155              215 17           STEAM       STEAM         2415     (SAT.)                                                     (2)            2170              615 NOTES:
(I)
( 2)
Maximum Quast steady disc~arge pipe pressure.
Not recorded.
( 3) Test results are for evaluation tests only. Total of 33 supplementary valve actuation cycles were perfonned under similar conditions .
 
EPRI  I MARSHALL      PORV TEST DATA ( 3)
TABLE    4.4.l-lb FLOW MEASUREMENT CONDITIONS                                      Lo!<~GE  HEASUREHENTS              COHHENTS VALVE TOTAL VALVE (I)        VALVE !NLET          OUTLET    FLOW    TOTAL VALVE (2)                  VALVE INLET     LEAKAGE TEST        TEST    OPENING T!ME    FLUID    PRESS. TEHP. PRESS. RATE      CLOSING TIME      MED!~    PRESS. TEHP.      RATE NO.       TYPE          (SEC)               (PSIA)    (OF)    (PSIA)   (LBM/HR)      (SEC)                     (PSIA)   (OF)     (GPM)
A pre-operational leakage STEAH      I.BO        STEAM    2155     (SAT.)     605    225,000      I. 00          . STEt.~    2445      (SAT. J    0.026 test showed 0.0 GPM leakage STEA.~      I. 70           *
* 1.00
* 1.00
* STEAM I. 70 *
* STEAM       I. 70                                       *
* 1.00 *
* 1.00                         *
* 4 STEAM I. 60
* 4       STEAM       I. 60
* 1.00
* 1.00
* STEAM I. 65
* STEAM       I. 65
* 1.00 2435 [SAT.) 0.026 STEAM !. 70
* 1.00             STE~u      2435     [SAT.)       0.026 STEAM       !. 70
* 1.95
* 1.95
* S7t:AM !. 70 * * *
* S7t:AM     !. 70         *         *       *
* I. 60 * -+::> 8 STEAM !. 65
* I. 60                         *
* I * *
-+::>
* 1. 5D STEAM 2455 (SAT. J 0.108 w (Jl 9 STEAM I. 70 STEAM 2155 (SAT.) 215 225,000 1.00
I      8       STEAM       !. 65                   *       *         *
* 10 STEAM !. 70 * * * * ** l.00 .. *
* 1. 5D           STEAM       2455     (SAT. J 0.108 w
* 11 STEAM 1.60 * * *
(Jl 9       STEAM       I. 70       STEAM     2155     (SAT.)     215     225,000     1.00
* 1.00 *
* 10         STEAM       !. 70         *         *       *         *         **       l.00                         .         *
* 12 STEAM !. 65 *
* 11       STEAM       1.60           *         *       *
* I. DO * * *
* 1.00                                     *
* 13 STEAM 1.60 * * * *
* 12       STEAM       !. 65                   *
* l.00 .. .. 14 STEAM I. 7D * *
* I. DO             *         *         *
* 1. 70 *
* 13         STEAM       1.60           *         *       *         *
* 15 STEAM I. 70 * .. *
* l.00               .                                 .
* I. 65 .. * * .. 16 STEAM 1.65 * " * *
14         STEAM       I. 7D         *         *
* 1.80 *
* 1. 70             *
* 17 STEAM (3) * * *
* 15         STEAM       I. 70         *         .                 *
* I.OD STEAM 2415 (SAT. J 0.026 not applicable to this test !IOTES: (I) Opening time measured from til"e of energizing solenoid until valve reaches full open position.  
* I. 65             .         *         *           .
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position. . . (3) Test results are for evaluation tests only. Total of 33 supplementary va*lve cycles were performed  
16         STEAM       1.65           *         "       *         *
:.nder similar conditions.
* 1.80                                     *
EPRI/WYLE Phase y TESI DAIA TABLE 4 . . -2a "AS TESTED" WYLE PHASE III TEST MATRIX FOR THE CONTROL COMPONENTS RELIEF VALVE INITIAL CONDITIONS(l)
* 17         STEAM         (3)         *         *                                                                           (SAT. J 0.026
TRAnSIENT CONDITIONS Valve Inlet Valve Inlet Accumulator Pressure Maximum Maximum Maximum at Discharge Bending Valve Test Closure Pipe Moment Acceleration Temp Press. Temp Press. Duration Signal Press.(2)
                                                                *
Induced(3)Induced Test No. Test Type Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (in-lb) (g's) 35-CC-lS Steam Steam 683 2,760 Steam 678 2,760 6 2,374 468 N/A 12.5 36-CC-2S Steam Steam 683 2,750 Steam 678 2, 750 6 2,280 416 N/A 5.3 (Failed Air) 37-CC-3S Steam Steam 670 2,535 Steam 665 2,535 4 2,370 377 18,000 6.2 (Preload, Failed Air) 38-CC-5W Water Water 440 2,536 Water 449 2,536 5 2,180 400 N/A 13.5 -!'> (Failed Air) I 39-CC-6W Water Water 103 475 Water 107 475 10 421 15 N/A 9.5 w ---! (Failed Air) 40-CC-4W Water Water 392 524 Water 397 524 15 473 145 N/A 5.1 (Failed Air) 41-CC-7W Water Water 633 2,535 Water 654 2,535 25 2,342 480 N/A 6.1 (Failed Air) 42-CC-lS Steam Steam 683 2, 760 Steam 678 2,760 6 2, 340 450 N/A 11.3 43-CC-7W Water Water 645 2,538 Water 649 2,538 6 2,337 510 N/A 7.7 44-CC-7W Water Water 644 2,540 Water 656 2,540 48 2,330 490 N/A 5.5 (Failed Air) 45-CC-lS Steam Steam 683 2,760 Steam 678 2,760 4 2,408 453 N/A 10.7 46-CC-BS/W Trans it ion Steam 664 2,530 Water 647 2,530 6 2,320 500 N/A 11.0 (Failed Air) 47-CC-3S Steam Steam 683 2,760 Steam 678 2, 760 4 2,410 475 39,000 11.4 (Pre load Failed Air)
* I.OD             STEAM     2415 not applicable to this test
_.,,. I w <.O
      !IOTES:
* EPRl/WYLE Phase Ill PORV TEST DATA TABLE 4.4.l-2a (cont'd) "AS TESTED" WYLE PHl\SE III TEST MATRIX FOR THE CONTROL COMPONENTS RELIEF VALVE (corn' o J INITIAL CONDITIONS(l)
(I) Opening time measured from til"e of energizing solenoid until valve reaches full open position.
Valve Inlet Accumulator Test No. Test Type Fluid Temp Press. (OF) (psi a) Fluid Temp Press. (OF) (psi a) 48-CC-9W/W Water Water 135 2,540 Water 648 2,540 Seal Simulation 49-CC-2S Steam Steam 683 2,760 Steam 678 2, 760 (Failed Air) 50-CC-3S Steam Steam 683 2,760 Steam 678 2,760 (Pre load) 51-CC-3S Steam steain 683 2, 760 Steam 679 2, 760 (Pre load Failed Air) (1) GN 2 PORV Actuation Ullage pressure for all tests was 85 (+/-_ 5) psig. (2) No Back Pressure orifice was used in the Control Components PORV testing. (3) Value shown corresponds to maximum moment applied while valve was in opening/closing process. Valve Inl1;t Pressure at Test Closure Duration Signal (seconds) (psia) 6 2,340 l 2,380 2,410 2,450
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.             .               .
* TRANSIENT CONDITIONS_
(3) Test results are for evaluation tests only. Total of 33 supplementary va*lve cycles were performed :.nder similar conditions.
Maximum Maximum Discharge Bending Pipe Moment Press.(2)
 
Induced (psia) (in-lb) 515 N/A 440 N/A 460 38,000 473 36,800 Maximum Valve Acceleration lriduced (g's) 3.9 11.4 12.2 13.8 EPR!/WYLE Phase Ill PORV TEST DATA TABLE 4.4.l-2b SUMMl\RY OF CONTROL COMPONENTS VALVE PERFORMANCE Test 35-36-37-38-39-40-41-42-43-44-45-46-Number CC-lS CC-25 CC-35 CC-5W CC-6W CC-4W CC-7W CC-lS CC-7W CC-7W CC-lS CC-85/W Pre-Test Leakage ( 1) Media Steam Steam Steam Water Water Water Water Steam Water Water Steam Ii Pressure (psia) 2, 770 2, 760 2,480 2,265 499 520 2,700 2, 740 2,535 2,340 2, 765 2 ,,. ... , ... Temp (OF) 682 680 670 412 94 402 640 679 641 637 683 62Cl Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 o. 0013 Transient Performance Total Valve Opening Time (sec) 1.07 1.15 .78 0.69 0.93 1.07 1.05 1.83 0. 76 0.87 1.27 1. 22 Main Disc Opening Time (sec) 0.42 0.42 .43 0.43 0.75 o. 71 0.39 0.66 0.49 0.42 0.61 0.f3 Valve Flowrate (lb/Hr) .;:::. 257,400 258,500 237,600 900,000 478,800 356,400 489,600 259,200 511,200 482,400 255,600 518,!C*J I Corresponding Valve .;:::. f-' Inlet Press (psia) 2,420 2,407 2,320 2,194 426 482 2,370 2,400 2,352 2,345 2,420 2, 3.!5 Corresponding Valve Inlet Temp (OF) 667 666 664 450 116 399 654 677 649 656 666 6.!0 Corresponding Valve Outlet Press (psia) 380 378 350 400 1. 145 475 380 489 476 375 !83 Corresponding Valve Outlet Temp (OF) 432 430 370 430 105 355 460 432 462 260 433 462 Corresponding Test Time Relative to Open Corrmand (sec) 4.3 4.1 1. 9 4.4 4.5 6.5 4.5 5.0 4.9 5.6 4.5 4.5 Inlet Pressure at Begining of Valve Closure {psia) 2,330 2 ,275 2,225 2 ,180 418 466 2,125 2,320 2,320 2,035 2,380 2,3i0 Total Valve Closure Time (sec) 0.68 1.24 2.65 0.79 1.05 1.66 20.65 0.69 1.09 42.24 0. 71 0. 76 Main Disc Closing Time (sec) 0.20 0.19 0.11 0.27 0.48 0.35 0.:18 0.16 0.21 3.8 0.18 0.20
EPRI/WYLE Phase           y TESI DAIA TABLE 4 . . -2a "AS TESTED" WYLE PHASE III TEST MATRIX FOR THE CONTROL COMPONENTS RELIEF VALVE INITIAL CONDITIONS(l)                                                 TRAnSIENT CONDITIONS Valve Inlet Valve Inlet                     Accumulator                     Pressure Maximum     Maximum Maximum at       Discharge   Bending Valve Test       Closure Pipe         Moment   Acceleration Temp       Press.               Temp       Press. Duration Signal     Press.(2)   Induced(3)Induced Test No. Test Type     Fluid   (OF)       (psi a)   Fluid     (OF)     (psi a) (seconds) (psi a)   (psi a)     (in-lb)   (g's) 35-CC-lS   Steam         Steam     683       2,760     Steam       678     2,760     6     2,374     468       N/A         12.5 36-CC-2S Steam         Steam     683       2,750     Steam       678     2, 750     6       2,280     416       N/A         5.3 (Failed Air) 37-CC-3S Steam         Steam     670     2,535     Steam       665     2,535     4       2,370     377       18,000       6.2 (Preload, Failed Air) 38-CC-5W Water         Water     440     2,536     Water       449     2,536     5       2,180     400       N/A         13.5 (Failed Air)
*
I w    39-CC-6W Water         Water     103         475     Water       107       475   10         421 15       N/A           9.5 (Failed Air) 40-CC-4W   Water         Water     392         524     Water       397       524   15         473     145       N/A           5.1 (Failed Air) 41-CC-7W   Water         Water     633     2,535     Water       654     2,535     25       2,342     480       N/A           6.1 (Failed Air) 42-CC-lS   Steam         Steam     683     2, 760     Steam       678     2,760     6       2, 340     450       N/A         11.3 43-CC-7W   Water         Water     645     2,538     Water       649     2,538             2,337 6                  510       N/A           7.7 44-CC-7W   Water         Water     644       2,540     Water       656     2,540   48       2,330     490       N/A           5.5 (Failed Air) 45-CC-lS   Steam         Steam     683       2,760     Steam       678     2,760     4       2,408     453       N/A         10.7 46-CC-BS/W Trans it ion Steam     664       2,530     Water       647     2,530     6       2,320     500       N/A         11.0 (Failed Air) 47-CC-3S   Steam         Steam     683       2,760     Steam       678     2, 760     4       2,410     475       39,000     11.4 (Pre load Failed Air)
* EPRI/WYLE Phase III PORV TEST DATA TABLE 4.4.l-2b (cont'd)  
 
EPRl/WYLE Phase Ill PORV TEST DATA TABLE 4.4.l-2a (cont'd)
                                                            "AS TESTED" WYLE PHl\SE III TEST MATRIX FOR THE CONTROL COMPONENTS RELIEF VALVE (corn' oJ INITIAL CONDITIONS(l)                                               TRANSIENT CONDITIONS_
Valve Inl1;t Valve Inlet                     Accumulator                   Pressure Maximum    Maximum  Maximum at      Discharge  Bending  Valve Test     Closure  Pipe      Moment  Acceleration Temp      Press.               Temp     Press. Duration Signal    Press.(2) Induced  lriduced Test No.      Test Type                Fluid    (OF)      (psi a)   Fluid     (OF)     (psi a) (seconds) (psia)  (psia)    (in-lb)  (g's) 48-CC-9W/W   Water                   Water       135     2,540     Water     648     2,540     6      2,340    515      N/A        3.9 Seal Simulation 49-CC-2S     Steam                   Steam       683     2,760       Steam     678     2, 760     l      2,380    440      N/A      11.4 (Failed Air) 50-CC-3S     Steam                   Steam       683     2,760       Steam     678     2,760             2,410    460      38,000    12.2 (Pre load)
I w    51-CC-3S     Steam
<.O                                        steain     683     2, 760     Steam     679     2, 760             2,450    473      36,800    13.8 (Pre load Failed Air)
(1) GN 2 PORV Actuation Ullage pressure for all tests was 85 (+/-_ 5) psig.
(2) No Back Pressure orifice was used in the Control Components PORV testing.
(3) Value shown corresponds to maximum moment applied while valve was in opening/closing process.
 
EPR!/WYLE Phase Ill PORV TEST DATA TABLE 4.4.l-2b SUMMl\RY OF CONTROL COMPONENTS VALVE PERFORMANCE Test                          35-      36-      37-        38-         39-      40-      41-      42-      43-      44-    45-      46-Number                          CC-lS    CC-25    CC-35      CC-5W      CC-6W    CC-4W    CC-7W    CC-lS    CC-7W    CC-7W  CC-lS   CC-85/W Pre-Test Leakage ( 1)
Media                      Steam    Steam    Steam      Water      Water    Water    Water    Steam    Water    Water  Steam    Ii ate~
Pressure (psia)             2, 770  2, 760  2,480       2,265         499     520   2,700   2, 740   2,535   2,340   2, 765     ...
2 ,,. , ...
Temp (OF)                     682     680     670         412         94     402     640       679     641     637     683       62Cl Leak Rate (GPM)           0.0013   0.0013   0.0013     0.0013     0.0013   0.0013   0.0013   0.0013   0.0013   0.0013 0.0013   o. 0013 Transient Performance Total Valve Opening Time (sec)             1.07     1.15       .78       0.69       0.93     1.07     1.05     1.83     0. 76   0.87   1.27       1. 22 Main Disc Opening Time (sec)             0.42     0.42       .43       0.43       0.75     o. 71   0.39     0.66     0.49     0.42   0.61       0.f3 Valve Flowrate (lb/Hr)   257,400 258,500 237,600     900,000     478,800 356,400 489,600 259,200  511,200  482,400 255,600  518,!C*J I
Corresponding Valve f-'               Inlet Press (psia)   2,420   2,407   2,320       2,194         426     482   2,370   2,400   2,352   2,345   2,420   2, 3.!5 Corresponding Valve Inlet Temp (OF)         667     666     664         450       116     399     654       677     649     656     666       6.!0 Corresponding Valve Outlet Press (psia)     380     378     350         400         1. 145     475       380     489     476     375       !83 Corresponding Valve Outlet Temp (OF)         432     430     370         430       105     355     460       432     462     260     433       462 Corresponding Test Time Relative to Open Corrmand (sec)           4.3     4.1     1. 9       4.4       4.5     6.5     4.5       5.0     4.9     5.6     4.5       4.5 Inlet Pressure at Begining of Valve Closure {psia)       2,330   2 ,275   2,225       2 ,180       418     466   2,125   2,320   2,320   2,035   2,380     2,3i0 Total Valve Closure Time (sec)             0.68     1.24     2.65       0.79       1.05     1.66   20.65     0.69     1.09   42.24   0. 71     0. 76 Main Disc Closing Time (sec)             0.20     0.19     0.11       0.27       0.48     0.35     0.:18   0.16     0.21     3.8   0.18       0.20
* EPRI/WYLE Phase III PORV TEST DATA TABLE 4.4.l-2b (cont'd)


==SUMMARY==
==SUMMARY==
OF CONTROL COMPONENTS VALVE PERFORMANCE Test 35-36-37-38-39-40-41-42-43-44-45-46-Number CC-IS CC-25 CC-3S CC-.5W CC-6W CC-4W CC-711 CC-lS CC-7W CC-7W CC-15 CC-85/W Post-Test leakage (Spring Closure) (1) Media N/A Steam Steam Water Water Water Water N/A N/A Water N/A N/A Pressure (psia) N/A 2,450 2,575 2,545. 521 535 2,510 N/A N/A 2,445 N/A N/A Temp (OF) N/A 646 630 423 100 375 620 N/A N/A .620 N/A N/A Leak Rate (GPM) N/A 0.05 0.04 0.0013 0.0013 0.0013 0.169 N/A N/A 0.104 N/A N/A Post-Test leakage (Spring and Air Closure) (1) Media Steam Steam Steam Water Water Water Water Steam Water Water Steam Water Pressure (psia) 2,670 2,425 2,575 2,605 521 540 2,525 2,7go 2, 705 2,495 2,680 2,440 Temp (Of) 668 636 630 415 100 35g 610 55g 625 612 678 638 +:> Leak Rate 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0018 0.0013 0.0013 o.002g 0.0013 0.0013 I +:> w EPRI/WYLE Phase III PORV TEST DATA IABLE 4.4.l-2b (cont'd) SUMM/\RY OF CONTROL COMPONENTS V/\LVE PERFORM/\NCE Test 47-48-49-50-51-Number CC-35 CC-9W/W CC-2S CC-3S CC-3S Pre-Test Leakage Media Steam Water Steam Steam Steam Pressure (psia) 2, 780 2,478 2,790 2,788 2, 790 Temp (OF) 685 125 683 684 684 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) .58 1.84 0.50 1.17 0.67 Main Oise Opening Time (sec) .395 1.04 0.302 0.52 0.46 Valve Flowrate (lb/Hr) 255,600 558,000 262,800 262,800 270,000 """' Corresponding Valve I +:> Inlet Press (psia) 2,465 2,365 2,505 2,465 2,525 Ul Corresponding Valve Inlet Temp (OF) 672 587 671 66g 673 Corresponding Valve Outlet Press (psia) 385 500 380 388 397 Corresponding Valve Outlet Temp (OF) 435 460 422 432 410 Corresponding Test Time Relative to Open Command (sec) 2.8 4.2 2.5 3.6 2.2 Inlet Pressure at Beginning of Valve Closure (psia) 2,220 2,335 2,210 2,385 2,390 Total Valve Closure Time (sec) 3.80 o. 78 3.57 0.68 1.17 Main Disc Closing Time (sec) 0.32 0.22 0.26 0.23 0.22
OF CONTROL COMPONENTS VALVE PERFORMANCE Test                             35-     36-       37-         38-       39-     40-     41-       42-     43-     44-       45-     46-Number                             CC-IS   CC-25     CC-3S       CC-.5W   CC-6W   CC-4W   CC-711   CC-lS   CC-7W   CC-7W     CC-15   CC-85/W Post-Test leakage (Spring Closure) (1)
+::> I +::> -...J
Media                         N/A     Steam     Steam       Water   Water   Water   Water     N/A     N/A   Water     N/A     N/A Pressure (psia)               N/A     2,450     2,575       2,545.     521     535   2,510     N/A     N/A     2,445     N/A   N/A Temp (OF)                     N/A       646       630         423       100     375     620   N/A     N/A       .620   N/A   N/A Leak Rate (GPM)               N/A       0.05     0.04     0.0013   0.0013   0.0013   0.169     N/A   N/A     0.104     N/A   N/A Post-Test leakage (Spring and Air Closure) (1)
* Test Number 47-CC-3S Post-Test leakage (Spring Closure) Media Steam Pressure (psia) 2,750 Temp (OF) 654 leak Rate (GPM) 0.085 Post-Test Leakage (Spring & Air Closure) Media Steam Pressure (psi a) 2, 765 Temp (OF) 643 leak Rate 0.0013 48-CC-9W/W N/A N/A N/A N/A Water 2,522 395 0.0013 EPRl/WYLE Phase III PORV TEST DATA TABLE 4.4.l-2b (cont'd}  
Media                     Steam   Steam     Steam       Water     Water   Water   Water   Steam   Water   Water   Steam   Water Pressure (psia)             2,670   2,425     2,575       2,605       521     540   2,525   2,7go   2, 705 2,495     2,680   2,440 Temp (Of)                       668     636       630         415       100     35g     610       55g     625     612       678     638
+:>     Leak Rate I                                  0.0013   0.0013   0.0013     0.0013   0.0013   0.0013 0.0018   0.0013 0.0013
+:>                                                                                                                      o.002g   0.0013 0.0013 w
 
EPRI/WYLE Phase III PORV TEST DATA IABLE 4.4.l-2b (cont'd)
SUMM/\RY OF CONTROL COMPONENTS V/\LVE PERFORM/\NCE Test                           47-       48-         49-         50-       51-Number                           CC-35     CC-9W/W     CC-2S       CC-3S     CC-3S Pre-Test Leakage Media                       Steam     Water       Steam       Steam     Steam Pressure (psia)             2, 780   2,478       2,790       2,788     2, 790 Temp (OF)                     685       125       683         684       684 Leak Rate (GPM)           0.0013   0.0013     0.0013     0.0013   0.0013 Transient Performance Total Valve Opening Time (sec)               .58     1.84       0.50       1.17     0.67 Main Oise Opening Time (sec)             .395     1.04     0.302         0.52     0.46 Valve Flowrate (lb/Hr)   255,600   558,000   262,800     262,800   270,000
"""'I      Corresponding Valve
+:>
Ul              Inlet Press (psia)   2,465     2,365       2,505       2,465     2,525 Corresponding Valve Inlet Temp (OF)         672       587       671         66g       673 Corresponding Valve Outlet Press (psia)     385     500         380         388     397 Corresponding Valve Outlet Temp (OF)       435       460         422         432       410 Corresponding Test Time Relative to Open Command (sec)         2.8       4.2         2.5         3.6       2.2 Inlet Pressure at Beginning of Valve Closure (psia)       2,220     2,335       2,210       2,385     2,390 Total Valve Closure Time (sec)             3.80     o. 78       3.57       0.68     1.17 Main Disc Closing Time (sec)             0.32     0.22       0.26       0.23     0.22
* EPRl/WYLE Phase III PORV TEST DATA TABLE 4.4.l-2b (cont'd}


==SUMMARY==
==SUMMARY==
OF CONTROL COMPONENTS VALVE PERFORMANCE 49-CC-2S Steam 2, 715 679 0.0013 Steam N/A N/A N/A 50-CC-3S N/A N/A N/A N/A N/A 2, 780 672 0.0013 51-CC-3S Steam 2,795 661 0.078 Steam 2, 765 657 0.0013 ( 1) Recorded leakage of 0.0013 GPM indicate measured values less than or equal to 0.0013 GPM.
OF CONTROL COMPONENTS VALVE PERFORMANCE Test                                47-    48-      49-         50-      51-Number                                CC-3S  CC-9W/W  CC-2S       CC-3S    CC-3S Post-Test leakage (Spring Closure)
I ' I * *
Media                            Steam N/A      Steam      N/A        Steam            ( 1) Recorded leakage of 0.0013 GPM indicate measured Pressure (psia)                  2,750  N/A       2, 715      N/A       2,795                  values less than or equal to 0.0013 GPM.
* 4.5 MASONE1LAN RELIEF VALVE 4.5.1 "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Masoneilan relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Masoneilan relief valve tested at each of the test facilities.
Temp (OF)                          654  N/A         679      N/A         661 leak Rate (GPM)                  0.085  N/A       0.0013      N/A       0.078 Post-Test Leakage (Spring &
Test Facility Marsha 11 Wyle (Phase III) 4.5.2 Principal Observations Marshall Steam Station "As Tested" Test Matrix Table 4.5. 1-la 4.5.l-2a Valve Performance Data Table 4.5.l-lb 4.5.l-2b The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles. During several supplementary tests performed prior to the evaluation tests, the valve opening stroke times were in excess of three (3) seconds. The regulated air supply pressure to the air operator was increased from approximately 55 to 60 psig for all evaluation tests. Wyle Phase III A total of eleven were performed.
Air Closure)
For all tests, the valve opened and closed on demand. The valve was disassembled and inspected by the Masoneilan valve representative.
Media                        Steam    Water    Steam      N/A     Steam Pressure (psi a)                2, 765  2,522      N/A       2, 780   2, 765 Temp (OF)                          643    395    N/A          672       657 leak Rate                      0.0013 0.0013      N/A      0.0013   0.0013
No damage was observed that would affect future valve performance.
+::>
The cage to body gasket had partially "washed out" during testing . 4-49 The valv(' opening time exhibited a sensitivity to the air supply system pressure supplied to the valve's air actuator.
I
For the tests performed, air supply accumulator pressures were varied between 54+1 and 59+1 PSIG resulting in total valve opening times ranging from 1.6 to 6.4 seconds. Valve opening times were also found to be sensitive to the size of tubing. used in the air supply system. Figure 4.5.2-1 depicts the air supply system utilized during testing. The original air supply system utilized during the checkout of the Masoneilan valve had 1/4" tubing between the solenoid valve and the air actuator, as recommended in the valve manufacturer's instruction manual. When the tubing size was increased to 1/2", dry stroke times in the range of 2 seconds were obtained.
+::>
Table 4.5.2-1 summarize'., the observed relationship between accumulator pressure, actuator inlet pressure, and valve opening stroke times. 4-50 ' .
-...J
* I I ) I
 
* TABLE 4.5.2-1  
~ I ' I
* 4.5   MASONE1LAN RELIEF VALVE 4.5.1 "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Masoneilan relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Masoneilan relief valve tested at each of the test facilities.
Test                         "As Tested" Test         Valve Performance Facility                          Matrix Table             Data Table Marsha 11                        4.5. 1-la               4.5.l-lb Wyle (Phase III)                  4.5.l-2a                4.5.l-2b 4.5.2 Principal Observations Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles.
During several supplementary tests performed prior to the evaluation tests, the valve opening stroke times were in excess of three (3) seconds.
The regulated air supply pressure to the air operator was increased from approximately 55 to 60 psig for all evaluation tests.
Wyle Phase III A total of eleven te~.ts were performed. For all tests, the valve opened and closed on demand. The valve was disassembled and inspected by the Masoneilan valve representative. No damage was observed that would affect future valve performance. The cage to body gasket had partially "washed out" during testing .
* 4-49
 
The valv(' opening time exhibited a sensitivity to the air supply system pressure supplied to the valve's air actuator. For the tests performed, air supply accumulator pressures were varied between 54+1 and 59+1 PSIG resulting in total valve opening times ranging from 1.6 to 6.4 seconds.
Valve opening times were also found to be sensitive to the size of tubing.
used in the air supply system. Figure 4.5.2-1 depicts the air supply system utilized during testing. The original air supply system utilized during the checkout of the Masoneilan valve had 1/4" tubing between the solenoid valve and the air actuator, as recommended in the valve manufacturer's instruction manual. When the tubing size was increased to 1/2", dry stroke times in the range of 2 seconds were obtained.
Table 4.5.2-1 summarize'., the observed relationship between accumulator pressure, actuator inlet pressure, and valve opening stroke times.
4-50
 
I I   ) I TABLE 4.5.2-1


==SUMMARY==
==SUMMARY==
OF RELATIONSHIP BETWEEN AIR SUPPLY PRESSURE AND MASONEILAN RELIEF VALVE OPENING TIME 5:l-MN-2S 54-MN-4W 56-MN-SW 5?-MN-3W SB-MN-SW 60-MN-7S/W 61-MN-SW/W 62-MN-9W Conditions See Air Supply Accumulator Pressure (Equal to Regulator Setting) (Psig) TABLE 4.5.l-2a 54+/-1 54+/-1 54+/-1 54+/-1 56+/-1 scr:.1 59+/-1 59.:!:.l 59.:!:.l 59.:!:.l Air Actuator Total Inlet Press Valve 2 Seconds Opening After Actuation Time Signal (Psig) (Sec) 53.0 1.64 52.0 1.84 51.5 3. 7J 48.5 6.39 52.5 3.08 53.0 2.54 52.0 1.95 53.0 1. 81 53.0 1.97 53.5 3.08 Note: All tests shown above utilized 1/2 11 (.435 11 I.D.) diameter:
OF RELATIONSHIP BETWEEN AIR SUPPLY PRESSURE AND MASONEILAN RELIEF VALVE OPENING TIME Air Supply Accumulator Pressure                     Air Actuator            Total (Equal to                   Inlet Press            Valve Regulator                     2 Seconds              Opening Setting)                     After Actuation        Time Conditions      (Psig)                      Signal (Psig)           (Sec)
air supply t11hinn hPtwPPn c::.nlPnnirl  
See TABLE 4.5.l-2a 5;~-MN-lS                  54+/-1                         53.0                    1.64 5:l-MN-2S                  54+/-1                         52.0                   1.84 54-MN-4W                    54+/-1                          51.5                   3. 7J 5~i-MN-3W                  54+/-1                          48.5                   6.39 56-MN-SW                    56+/-1                          52.5                   3.08 5?-MN-3W                    scr:.1                        53.0                   2.54 SB-MN-SW                    59+/-1                          52.0                   1.95 60-MN-7S/W                  59.:!:.l                    53.0                   1. 81 61-MN-SW/W                  59.:!:.l                    53.0                   1.97 62-MN-9W                    59.:!:.l                    53.5                   3.08 Note:       All tests shown above utilized 1/2               11
;mrl .:iir .:1rt11.:1tnr 4-51
(.435 11 I.D.) diameter: air supply t11hinn hPtwPPn c::.nlPnnirl ;mrl .:iir .:1rt11.:1tnr 4-51
.. * *
 
/A uC(; Power In .0 / __ L? cY PS-5 P' 'I B '---------** 6 ,, PORV Solenoid (1" orifice) ____ _,_I , ..... ! c A= 1 2 11 Tubing to !4 11 Pipe Reducer(.172" IIJ) B=. .435 ID Tubing 14' 6" C= . 935 ID Tubing NC= Normally Closed Figure Air Supp'y System {Wyle Phase III) Ma so neil an PORV 4-53 -L' Regulator 100 psi supply Nitrogen Accumulator 3 (Volume, 4F+ )
      ,--~1                  /A                             ,--~    uC(;   Power In
EPRI/ MARSHALL PORV TEST DATA (3) TABLE 4.5.1-la "AS TESTED" MARSHALL TEST MATRIX FOR THE MASONEILAN RELIEF VALVE CONDITIONS AT VAL VE OPEN I NG TRANSIENT CONDITIONS VALVE INLET IN ACCUMULATOR TEST VALVE INLET MAXIMUM pl DURATION PRESS. WHEN DISCHARG TEST TEST FLUID PRESS. TEMP. FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS. NO. TYPE (PSIA) (OF) (PSIA) (OF) TO CLOSE VALVE (PSIA) (PSIA STEAM STEAM 2495 (SAT.) SAME AS VALVE INLET 66 2205 525 STEAM STEAM 2475 (SAT.) 32 2215 535 STEAM STEAM 2455 (SAT.) 32 2205 535 4 STEAM STEAM 2455 (SAT.) 33 2215 535 STEAM STEAM 2495 (SAT.) 33 2245 545 6 STEAM STEAM 2485 (SAT.) 64 2195 175 STEAM STEAM 2505 (SAT.) 31 2235 185 8 STEAM STEAM 2475 (SAT.) 35 2215 175 STEAM STEAM 2455 (SAT.) 41 2205 175 I CJ1 10 STEAM (SAT.) STEAM 2465 36 2215 185 11 STEAM STEAM 2485 (SAT.) (2) 2225 545 NOTES: (1) Maximum Quasi steady discharge pipe pressure.  
        .0
(2) Not recorded. . (3) Test results are for evaluation tests only. Total of 18 supplementary valve actuation cycles were performed under similar conditions . * * * 
_ _ L?
* * &#xa3;PR! I "MARSHALL PORV TEST DATA (3) TABLE 4.5.1-lb SUMl"ARY OF MASONEILAN RELIEF VALVE PERFORMANCE:
                            /
FLO\/ MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS "COMMENTS TOTAL VALVE (1) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLU!D PRESS. . TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (;>SIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM) STEAM 2.000 STEAM 2205 (SAT.) 525 199,000 1.700 STEAM 2445 (SAT.) 0.025 A pre-operational leakage test showed 0.0 GPM leakage 2 STEAM 1. 900 * .. * *
cY PS-5                                     Solenoid P'
* 1.600 " ..
(1" orifice)
* STEAM 1. 750 .. .. " 1.600 * .. ..
                              'I B
* STEAM 1.800 1. 600
                '----- ----**   6 ,,       ____ _,_I,.....
* STEAM 1.800 *
c
* 1.600 STEAM 2485 (SAT.) 0.022 6 +=> STEAM 2.100 STEAM 2195 (SAT.) 175 197,000 1. 700 *
* PORV A=
* I (.J1 STEAM 1.800 * * .. .. 1.600 * * .. .. U1 8 STEAM 1. 650
                '~
1211  Tubing to   !4 11 Pipe Reducer(.172" IIJ)       14' 6" B=.   .435 ID Tubing C=   . 935 ID Tubing Regulator NC=     Normally Closed
                                                                                  -L          100 psi supply Nitrogen Accumulator (Volume, 4F+ 3 )
Figure 4.5.2~1 Air Supp'y System
{Wyle Phase III)
* 4-53 Ma so neil an PORV
 
EPRI/     MARSHALL       PORV TEST DATA (3)
TABLE 4.5.1-la "AS TESTED"       MARSHALL   TEST MATRIX FOR THE       MASONEILAN RELIEF VALVE CONDITIONS AT VAL VE OPEN I NG                                       TRANSIENT CONDITIONS TEST        TEST          FLUID VALVE INLET PRESS.
IN ACCUMULATOR                 TEST DURATION VALVE INLET PRESS. WHEN MAXIMUM DISCHARG pl NO.                                               TEMP.       FLUID         PRESS.     TEMP.         (SEC)         SIGNAL GIVEN TYPE                     (PSIA)       (OF)                                                                               PIPE PRESS.
(PSIA)     (OF)                         TO CLOSE VALVE     (PSIA)
(PSIA STEAM         STEAM       2495         (SAT.)           SAME AS VALVE INLET                 66                 2205           525 STEAM       STEAM       2475       (SAT.)                                                 32                 2215           535 STEAM       STEAM       2455       (SAT.)                                                 32                 2205           535 4         STEAM       STEAM       2455       (SAT.)                                                 33                 2215           535 STEAM         STEAM       2495       (SAT.)                                                 33                 2245           545 6       STEAM         STEAM       2485         (SAT.)                                                 64                 2195           175 STEAM         STEAM       2505       (SAT.)                                                 31                 2235           185 8         STEAM       STEAM       2475       (SAT.)                                                 35                 2215           175
~
I                STEAM       STEAM       2455       (SAT.)
CJ1 41                 2205           175
~      10         STEAM       STEAM        2465        (SAT.)                                                 36                 2215           185 11         STEAM       STEAM       2485       (SAT.)                                                 (2)               2225           545 NOTES:
(1) Maximum Quasi steady discharge pipe pressure.
(2) Not recorded.       .
(3) Test results are for evaluation tests only. Total of 18 supplementary valve actuation cycles were performed under similar conditions .
 
                                                                        &#xa3;PR! I   "MARSHALL   PORV TEST DATA (3)
TABLE 4.5.1-lb SUMl"ARY OF MASONEILAN RELIEF VALVE PERFORMANCE:
FLO\/ MEASUREMENT CONDITIONS                                     LEAKAGE MEASUREMENTS           "COMMENTS V~LVE TOTAL VALVE (1)         VALVE INLET         OUTLET     FLOW     TOTAL VALVE (2)               VALVE INLET     LEAKAGE TEST     TEST     OPENING TIME     FLU!D   PRESS. . TEMP.     PRESS. RATE     CLOSING TIME     MEDIA     PRESS. TEMP. RATE NO.     TYPE         (SEC)               (PSIA)     (OF)     (;>SIA)   (LBM/HR)     (SEC)                   (PSIA)   (OF)   (GPM)
STEAM       2.000       STEAM     2205     (SAT.)     525     199,000     1.700         STEAM     2445     (SAT.)   0.025 A pre-operational leakage test showed 0.0 GPM leakage 2       STEAM       1. 900         *         .       *         *
* 1.600                       "         .
* STEAM       1. 750         .         .       "                             1.600             *         .         .
* STEAM       1.800                                                             1. 600
* STEAM       1.800           *
* 1.600         STEAM     2485     (SAT.)   0.022
+=>
6      STEAM       2.100       STEAM     2195     (SAT.)     175     197,000     1. 700           *
* I
(.J1 U1 STEAM       1.800           *                 *         ..       .         1.600             *         *         .       .
8       STEAM       1. 650
* 1. 600
* 1. 600
* 9 STEAM 1.600 .. .. *
* 9       STEAM       1.600         .                   .         *
* 1.600 .. .. *
* 1.600             .         .         *
* 10 STEAM 1. 700 * .. 1.600 * * .. 11 STEAM 1.900 *
* 10       STEAM       1. 700                             *                   .         1.600           *                     *       .
* 1.700 "STEAM 2485 (SAT.) 0.065 not applicable to this test NOTES: (I) Opening time measured from t me of energizing solenoid until valve reaches full open position.  
11       STEAM       1.900                             *
* 1.700         "STEAM     2485     (SAT.)   0.065 not applicable to this test NOTES:
(I) Opening time measured from t me of energizing solenoid until valve reaches full open position.
(2) Closing time measured from t me of de-energizing solenoid until valve reaches full closed position, (3) Test results are for evaluat on tests only. Total of 18 supplementary valve cycles were performed under similar conditions._
(2) Closing time measured from t me of de-energizing solenoid until valve reaches full closed position, (3) Test results are for evaluat on tests only. Total of 18 supplementary valve cycles were performed under similar conditions._
EPR!/WYLE Phase III PORV TEST DATA TnP1 t" /4 C i ") ... '* J' \ -t.. 'C "AS TESTED" WYLE Pll/\SE Ill TEST MATRIX FOR THE . MASONEILAN RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS Valve Inlet At .Valve Inlet In Accumulator Pressure Maximum Maximum Maximum Air at Discharge Bending Valve Accum. Test Closure Pipe_ *Moment Acceleration Press. Temp Press. Temp Press. Duration Signal Press.(2)
 
Induced(4)Induced Nn. Test Type (psig)(l)
EPR!/WYLE Phase III PORV TEST DATA TnP1 t" /4   C i     ") ...
Fluid (Of) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psia) (in-lb) (g's) 52-MN-lS Steam 54 Steam 683 2,765 Steam 679 2,765 7 2,415 358 N/A 13.4 53-MN-2S Steam 54 Steam 683 2,758 Steam (Pre load) 678 2, 758 . 8 2,370 346 . 35,600 3.9 54-MN-4W Water 54 Water 444 2,530 Water 448 2,530 12 2,150 396 N/A 9.1 .+::> I (JI (j) 55-MN-3W Water 54 Water 445 678 Water 450 678 11 652 153 N/A 11.2 56-MN-5W Water 56 Water 104 675 Water 116 675 11 593 38 N/A 4.5 57-MN-3W Water 58 Water 444 . 674 Water 445 674 11 640 156 N/A 2.0 58-MN-5W Water 59 Water 101 675 Water 101 675 20 570 14.7 N/A 5.0 59-MN-6W Water 59 Water 648 2,533 Water 650 2,533 9 2,355 435 N/A 4.6 60-MN-7S/W Transition 59 Steam 670 2,535 Water 647 2,535 9 2,350 425 N/A 4.0 61-MN-BW/W Water 59 Water 115 2,640 Water Seal 656 2,640 17 (3) 450 N/A 5.9 Simulation 62-MN-9W Water 59 Water 327 2,672 Water 325 2,672 6 2,340 112 N/A 10.3 *
                                                                                "~ ~  '* J'   \ - t.. 'C "AS TESTED" WYLE Pll/\SE Ill TEST MATRIX FOR THE
* I 1 I 1
                                                                      . MASONEILAN RELIEF VALVE INITIAL CONDITIONS                                                                 TRANSIENT CONDITIONS Valve Inlet At .Valve Inlet                     In Accumulator                               Pressure Maximum Maximum Maximum Air                                                                                               at     Discharge Bending Valve Accum.                                                                                 Test     Closure Pipe_       *Moment   Acceleration Press.               Temp       Press.                     Temp               Press. Duration Signal   Press.(2) Induced(4)Induced Te~t  Nn. Test Type (psig)(l) Fluid     (Of)       (psi a)     Fluid         (OF)               (psi a) (seconds) (psi a) (psia)     (in- lb) (g's) 52-MN-lS   Steam       54     Steam       683       2,765       Steam           679               2,765       7     2,415     358       N/A       13.4 53-MN-2S Steam         54     Steam       683       2,758       Steam           678               2, 758 . 8     2,370     346     . 35,600     3.9 (Pre load) 54-MN-4W Water         54     Water       444       2,530       Water           448             2,530     12       2,150     396       N/A       9.1
* TABLE 4.5.1-2a (Cont'd) MASONEILAN Notes: (1) All values+ 1 psi. (2) No back pressure orifice used during Masoneilan valve testing. (3) Inlet pressure transducer failure. (4) Value shown corresponds to the maximum moment applied while the valve was in the opening/closing process . 4-57 EPRl/WYLE Phase III TEST DATA TABLE 4.5.l-Zo  
.+::>
I (JI (j)   55-MN-3W Water         54     Water       445         678     Water           450                 678   11           652   153       N/A     11.2 56-MN-5W   Water         56     Water       104         675     Water           116                 675     11           593     38       N/A       4.5 57-MN-3W   Water         58     Water       444 .       674     Water           445                 674     11         640   156       N/A       2.0 58-MN-5W   Water       59       Water       101         675     Water           101                 675     20         570   14.7       N/A       5.0 59-MN-6W   Water       59       Water       648       2,533       Water           650             2,533       9       2,355     435       N/A       4.6 60-MN-7S/W Transition   59       Steam     670       2,535       Water           647               2,535       9       2,350     425       N/A       4.0 61-MN-BW/W Water       59       Water     115       2,640       Water           656               2,640     17             (3) 450       N/A Seal                                                                                                                                        5.9 Simulation 62-MN-9W   Water       59     Water       327       2,672       Water           325               2,672       6     2,340     112     N/A       10.3
 
I 1 I 1 TABLE 4.5.1-2a (Cont'd)     MASONEILAN Notes:
(1) All values+ 1 psi.
(2) No back pressure orifice used during Masoneilan valve testing.
(3) Inlet pressure transducer failure.
(4) Value shown corresponds to the maximum moment applied while the valve was in the opening/closing process .
* 4-57
 
EPRl/WYLE Phase III       POR~  TEST DATA TABLE 4.5.l-Zo


==SUMMARY==
==SUMMARY==
  .OF MASONEILAN RELIEF VALVE PERFORMANCE Test 52-53-54-55-56-57-58-59-60-MN-61-MN-62-Number MN-lS MN-25 MN-4W MN-3W MN-SW MN-3W MN-SW MN-6W 75/W 8W/W MN-9W Pre-Test Leakage(!)
  .OF MASONEILAN RELIEF VALVE PERFORMANCE Test                               52-       53-       54-           55-         56-         57-       58-       59-       60-MN-     61-MN-   62-Number                               MN-lS     MN-25     MN-4W       MN-3W       MN-SW       MN-3W     MN-SW     MN-6W     75/W       8W/W     MN-9W Pre-Test Leakage(!)
Media Steam Steam Water Water Water Water Water Water Water Water Water Pressure (psia) 2,745 2,780 2,515 830 707 765 685 2, 771 2,565 2,615 . 2,690 Temp (OF) 682 678 437 422 90 450 96 646 645 J04 316 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0021 Transient Performance Total Valve Opening Time (sec) 1.64 1. 84 3. 73 6.39 3.08 2.54 2.39 1. 95 1. 81 1.97 3.08 Main Disc Opening Time (sec) 1.49 1.69 3.54 6.00 2. 74 2.20 2.05 1. 79 1.63 1.80 2.92 Valve Flow Rate (lb/Hr) 228,600 230,400 846,000 324,000 525,600 338,400 532,800 460,800 468,000 478,800 (3) .j:::. Corresponding Valve I Inlet Press (psia) 2,480 2,510 2,220 652 593 642 5go 2,395 2,400 (2) (3) U1 co Corresponding Valve Inlet Temp (OF) 670 672 451 450 117 Corresponding Valve 445 113 650 653 650 (3) Outlet Press (psia) 340 335 362 148 2.0 Corresponding Valve 152 2.0 420 410 430 (3) Outlet Temp (OF) 415 417 424 353 109 355 103 445 435 450 (3) Corresponding Test Time Relative to Open Command (sec) 4.2 3.8 4.9 5.5 5.7 4.7 8.6 4.2 3.r 8.0 (3) Inlet Pressure at Beginning of Valve Closur*e (psi a) 2,420 2,360 2,125 648 580 635 550 2,350 2,350 (2) 2,350 Total Valve Closure Time (sec) 1.87 1.88 1. 79 1. 33 1. 39 1.4 1.46 1.89 1. 93 1.94 1.80 Main Disc Closing Time (sec) 1. 59 1.60 1.68 1.22 1.23 Post-Test Leakage(!)
Media                           Steam     Steam     Water       Water       Water       Water     Water     Water     Water     Water     Water Pressure (psia)                 2,745     2,780     2,515           830         707         765       685   2, 771   2,565     2,615 . 2,690 Temp (OF)                         682       678       437           422         90         450       96       646       645       J04       316 Leak Rate (GPM)               0.0013   0.0013   0.0013       0.0013     0.0013     0.0013   0.0013   0.0013   0.0013     0.0013   0.0021 Transient Performance Total Valve Opening Time (sec)                 1.64     1. 84     3. 73       6.39         3.08       2.54     2.39     1. 95     1. 81     1.97     3.08 Main Disc Opening Time (sec)                 1.49     1.69     3.54         6.00         2. 74     2.20       2.05     1. 79     1.63       1.80     2.92 Valve Flow Rate (lb/Hr)     228,600   230,400   846,000     324,000     525,600     338,400   532,800   460,800   468,000   478,800         (3)
1.2 1.26 1.58 1 .. 60 1.62 1. 73 Media Steam Steam Water Water Water Water Water Water Water Water(4) Water(5) Pressure (psia) 2,775 2,780 2,425 765 663 685 640 2,575 2,417 2,635 2,645 Temp (OF) 672 678 433 435 117 434 134 638 640 485 313 * (GPM) 0.0013 0.0013 0.0013 0.0013 0. 0.0013 0.0013 0.0013 0.0013 0.37 0.04 I f ) I
.j:::.       Corresponding Valve I
* TABLE 4.5.l-2b (Cont'd) (1) Recorded leakages of .0013 GPM indicate measured leakages of less than or equal to .0013 GPM. (2) Inlet pressure transducer not thermally isolatedo (3) Venturi delta pressure sensor improperly isolated.  
U1                Inlet Press (psia)       2,480     2,510     2,220           652         593         642       5go co                                                                                                                        2,395     2,400         (2)       (3)
(4) .. Leakage decreased to .066 GPM in 45 minutes. (5) *Leakage increased to .079 GPM in 109 minutes
Corresponding Valve Inlet Temp (OF)             670       672       451           450         117         445       113       650       653       650       (3)
* 4-59 I l ' t *
Corresponding Valve Outlet Press (psia)         340       335       362           148         2.0         152       2.0       420       410       430       (3)
* 4.6 COPES-VULCAN RELIEF VALVE (316 W/STELLITE PLUG.AND 17-4PH CAGE) 4.6.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Copes-Vulcan relief valve model (316 w/Stellite Plug and 17-4PH Cage) at the Marshall Steam Station and during Phase III of the Wyle Test . Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Copes-Vulcan relief valve tested at each of the test facilities.
Corresponding Valve Outlet Temp (OF)           415       417       424           353         109         355       103       445       435       450       (3)
Te*;t F ac i Ii ty Marshall Wyle (Phase III) "As Tested" Test Matrix Table 4.6.1-la 4.6. l-2a Valve Performance Data Table 4.6.l-lb 4.6.l-2b It should lie noted that no preload test was performed on this valve design since the capability of the Copes-Vulcan valve to operate under an applied bending moment was demonstrakd during testing of the same valve body with a 17-4PH plug and cage (see section 4.:7). 4.6.2 Principal Observations Mars fl a 1 1 Ste am St at i on The valve fully opened on demand and fully closed on demand for each of eleven (11) evaluation test cycles. Wyl e Phase II I A total of nine (9) tests were performed on this valve design. For all tests the valve fully opened and fully closed on demand. Following test completion, the valve was disassembled and inspected by the Vulcan representative.
Corresponding Test Time Relative to Open Command (sec)               4.2       3.8     4.9           5.5         5.7       4.7       8.6       4.2       3.r       8.0       (3)
No damage was observed that would affect future valve performance.
Inlet Pressure at Beginning of Valve Closur*e (psi a) 2,420     2,360     2,125           648         580         635       550   2,350     2,350           (2) 2,350 Total Valve Closure Time (sec)                 1.87     1.88     1. 79       1. 33       1. 39       1.4     1.46     1.89     1. 93     1.94     1.80 Main Disc Closing Time (sec)                 1. 59     1.60     1.68         1.22         1.23         1.2      1.26     1.58     1 ..60   1.62     1. 73 Post-Test Leakage(!)
4-61 ' " 
Media                         Steam     Steam     Water         Water       Water       Water     Water     Water     Water     Water(4) Water(5)
.;:::. I (J) N * "AS TESTED" TEST MATRJX CONDITIONS VALVE INLET TEST TEST FLUID PRESS. TEMP. NO. TYPE {PSIA) (OF) STEAM STEAM 2475 {SAT.) STEAM STEAM 2460 {SAT.) STEAM STEAM 2450 (SAT.) 4 STEAM STEAM 2455 (SAT.) STEAM STEAM 2465 {SAT.) STEAM STEAM 2460 (SAT.) STEAM STEAM 2435 {SAT.) 8 STEAM STEAM 2450 {SAT.) 9 STEAM STEAM 2455 {SAT.) 10 STEAM STEAM 2465 (SAT.) 11 STEAM STEAM 2460 (SAT.) NOTES: (1) Maximum Quasi steady discharge pipe pressure.  
Pressure (psia)               2,775     2,780     2,425           765         663         685       640   2,575     2,417     2,635     2,645 Temp (OF)                         672       678       433           435         117         434       134       638       640       485     313
{ 2) Not recorded.  
          ~ate (GPM) 0.0013   0.0013   0.0013       0.0013       0.         0.0013   0.0013   0.0013   0.0013       0.37     0.04
"*****------*
 
... --**-----** --EPRI/ MARSHALL r'GRV TEST DATA (3) TABLE 4.6.1-la FOR THE COPES-VULCAN (316 W/STELLITE PLUG CAGE) RELIEF VALVE AT VALVE OPEUING TRANSIENT CONDITIONS IN ACCUMULATOR TEST VALVE lf,LET MAW'UM pl DUP.A TION PRESS. WHEN DI FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS. (PSIA) (Of) TO CLOSE VALVE {PSIA) {PSIA) SAME AS VALVE INLET 41 2155 635 18 2155 635 16 2155 635 16 2165 635 20 2165 635 55 2135 215 18 2155 215 17. 2155 215 23 2165 215 17 2175 215 (2) 2160 635 (3) Test results are for evaluation tests only. Total of 16 supplementary valve actuation tests were perfonned under similar conditions . * * 
I f ) I TABLE   4.5.l-2b (Cont'd)
*
(1)   Recorded leakages of .0013 GPM indicate measured leakages of less than or equal to .0013 GPM.
* EPRI I MARSHALL PORV TEST DATA ( 3) TABLC: .*
(2)   Inlet pressure transducer not thermally isolatedo (3)   Venturi delta pressure sensor improperly isolated.
(4) .. Leakage decreased to .066 GPM in 45 minutes.
(5) *Leakage increased to .079 GPM in 109 minutes
* 4-59
 
I l ' t 4.6   COPES-VULCAN RELIEF VALVE (316 W/STELLITE PLUG.AND 17-4PH CAGE)                 "
4.6.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Copes-Vulcan relief valve model (316 w/Stellite Plug and 17-4PH Cage) at the Marshall Steam Station and during Phase III of the Wyle Test
    . Program.
The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Copes-Vulcan relief valve tested at each of the test facilities.
Te*;t                       "As Tested" Test         Valve Performance Fac i Ii ty                      Matrix Table             Data Table Marshall                        4.6.1-la                 4.6.l-lb Wyle (Phase III)                4.6. l-2a                4.6.l-2b
* It should lie noted that no preload test was performed on this valve design since the capability of the Copes-Vulcan valve to operate under an applied bending moment was demonstrakd during testing of the same valve body with a 17-4PH plug and cage (see section 4.:7).
4.6.2   Principal Observations Mars fl a 11 Ste am St at i on The valve fully opened on demand and fully closed on demand for each of eleven (11) evaluation test cycles.
Wyl e Phase II I A total of nine (9) tests were performed on this valve design.
For all tests the valve fully opened and fully closed on demand. Following test completion, the valve was disassembled and inspected by the Copes-Vulcan representative. No damage was observed that would affect future valve performance.
4-61
 
EPRI/    MARSHALL            r'GRV TEST DATA (3)
TABLE    4.6.1-la "AS TESTED" ~ARSHALL  TEST MATRJX FOR THE COPES-VULCAN (316 W/STELLITE PLUG              4~0 17-~PH CAGE) RELIEF VALVE CONDITIONS AT VALVE OPEUING                                                    TRANSIENT CONDITIONS VALVE INLET                        IN ACCUMULATOR                              TEST DUP.A TION VALVE lf,LET PRESS. WHEN MAW'UM DI SC.-l~.RG pl TEST        TEST        FLUID      PRESS.      TEMP.       FLUID        PRESS.             TEMP.               (SEC)           SIGNAL GIVEN  PIPE PRESS.
NO.         TYPE                    {PSIA)       (OF)                     (PSIA)              (Of)                                TO CLOSE VALVE      {PSIA)
{PSIA)
STEAM       STEAM       2475        {SAT.)         SAME AS VALVE INLET                                41                2155              635 STEAM        STEAM        2460        {SAT.)                                                             18                2155              635 STEAM        STEAM        2450        (SAT.)                                                            16                2155              635 4          STEAM        STEAM        2455        (SAT.)                                                            16                2165              635 STEAM        STEAM        2465        {SAT.)                                                            20                2165              635 STEAM        STEAM        2460        (SAT.)                                                            55                2135              215 STEAM        STEAM        2435        {SAT.)                                                            18                2155              215
.;:::. 8          STEAM        STEAM        2450        {SAT.)                                                            17.                2155              215 I
(J) 9          STEAM        STEAM        2455        {SAT.)                                                            23                2165              215 N
10          STEAM        STEAM        2465        (SAT.)                                                             17                2175              215 11          STEAM        STEAM        2460        (SAT.)                                                             (2)               2160              635 NOTES:
(1) Maximum Quasi steady discharge pipe pressure.
{2) Not recorded.
(3) Test results are for evaluation tests only. Total of 16 supplementary valve actuation tests were perfonned under similar conditions .


==SUMMARY==
==SUMMARY==
OF COPES-VULCAN ( 316 W/STELLITE PLUG A,D 17-4?H CAGE) RELIEF PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VALVE (1) VALVE INLET OUTLET FLOW TOTAL VAL'IE [2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLUID PRESS. TEMP. PRESS. RATE CLOS iNG TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM) STEAM 1. 70 STEAM 2155 (SAT.) 635 236,000 1. 60 STEAM 2435 (SAT.) 0.066 A pre-operational leakage test showed 0.0 GPM leakage STEAM 1. 70 * * *
OF COPES-VULCAN EPRI I
* 1. 50 *
( 316 MARSHALL TABLC:  ~.6 W/STELLITE PLUG A,D PORV TEST DATA
* STEAM . 1. 75 * * *
                                                                                                .* -i~
* 1. SJ *
17-4?H
* 4 STEAM 1.65 * * * * .. 1. 55 * * *
( 3)
* STEAM 1. 85 * * * *
CAGE) RELIEF V~LVE  PERFORMANCE FLOW MEASUREMENT CONDITIONS                                       LEAKAGE MEASUREMENTS             COMMENTS VALVE TOTAL VALVE (1)         VALVE INLET           OUTLET     FLOW   TOTAL VAL'IE [2)                 VALVE INLET     LEAKAGE TEST       TEST     OPENING TIME   FLUID     PRESS. TEMP.     PRESS. RATE     CLOS iNG TIME     MEDIA   PRESS.       TEMP. RATE NO.       TYPE           (SEC)               (PSIA)     (OF)     (PSIA)   (LBM/HR)       (SEC)                   (PSIA)       (OF) (GPM)
* 1. 60 STEAM 2455 (SAT.) 0.058 6 STEAM 1.80 STEAM 2135 (SAT.) 205 232,000 1. 50 * * *
A pre-operational leakage STEAM         1. 70   STEAM     2155     (SAT.)       635     236,000       1. 60       STEAM     2435     (SAT.)   0.066 test showed 0.0 GPM leakage STEAM         1. 70     *         *         *
* STEAM 1.40 * *
* 1. 50                               *
* 1. 60 * *
* STEAM       . 1. 75       *         *         *
* 8 STEAM 1.40 * * *
* 1. SJ                     *
* 1. 55 * * * +:> I 9 STEAM 1.40 * * * *
* 4         STEAM         1.65       *         *         *           *         .           1. 55         *         *         *
* 1. 60 * * *
* STEAM         1. 85     *         *         *           *
* O'I 10 STEAM w l. 70 " * * *
* 1. 60       STEAM     2455     (SAT.)   0.058 6         STEAM         1.80     STEAM     2135     (SAT.)       205     232,000       1. 50         *         *         *
* 1. 65 * * *
* STEAM         1.40       *         *
* 11 STEAM 1.45 *
* 1. 60                     *         *
* 1. 50 STEAM 2465 (SAT.) 0.054 not applicable to this test NOTES: (1) time measured from time of energizing solenoid until valve reaches full open position.  
* 8         STEAM         1.40                 *         *           *
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.  
* 1. 55                     *         *       *
+:>
I 9         STEAM         1.40       *         *         *           *
* 1. 60         *         *         *
* O'I w    10         STEAM         l. 70
                                          "         *         *           *
* 1. 65         *         *         *
* 11         STEAM         1.45       *
* 1. 50       STEAM     2465       (SAT.)   0.054 not applicable to this test NOTES:
(1) Op~ning time measured from time of energizing solenoid until valve reaches full open position.
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.
(3) Test results are for evaluation tests only. Total of 16 supplementary valve actuation tests were also performed under similar conditions.
(3) Test results are for evaluation tests only. Total of 16 supplementary valve actuation tests were also performed under similar conditions.
EPRl/WYLE Phase Ill PORV TEST DATA TM! E "AS TESTED" WYLE PHASE Ill ltST MATRIX FOR THE COPES VULCAN(316 W/STELLITE PLUG AND 17-4 PB CAGE)RELIEF Vl\LVE INITIAL CONDITIONs(l)
 
TRANSIENT CONDITIONS Valve Inlet At Valve Inlet In Accumulator Pressure Maximum Maximum Maximum at Discharge Bending Valve Test Closure Pipe Moment Acceleration Temp. Press. Temp Press. Duration Signal Press.(2)
EPRl/WYLE Phase Ill PORV TEST DATA TM! E 4.6.1-2~
Induced Induced Test No. Test Type Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (in-lb) (g's) 71-CV-316-lS Steam Steam 682 2, 715 Steam 677 2, 715 6 2,333 460 N/A 7.0 72-CV-316-3W i..,::!te!"' ? WJt2:"" 2,545 4 2,170 387 N/A 4.6 ... , .........
                                                                  "AS TESTED" WYLE PHASE Ill ltST MATRIX FOR THE COPES VULCAN(316 W/STELLITE PLUG AND 17-4 PB CAGE)RELIEF Vl\LVE INITIAL CONDITIONs(l)                                                         TRANSIENT CONDITIONS Valve Inlet At Valve Inlet                         In Accumulator                   Pressure Maximum     Maximum Maximum at       Discharge   Bending Valve Test     Closure Pipe         Moment   Acceleration Temp.       Press.                     Temp       Press. Duration Signal   Press.(2)   Induced   Induced Test No.           Test Type       Fluid           (OF)       (psi a)         Fluid       (OF)       (psi a) (seconds) (psi a)   (psi a)     (in-lb)   (g's) 71-CV-316-lS       Steam           Steam             682       2, 715           Steam       677       2, 715   6       2,333   460         N/A       7.0 72-CV-316-3W       w~tPr            i..,::!te!"'     ~~6      ...? , .........
73-CV-316-4W Water Water 442 675 Water 442 675 10 626 193 N/A 7.7 74-CV-316-5W Water Water 105 675 Water 92. 675 10 562 174 N/A 8.6 _.,, I 75-CV-316-6W Water Water 274 2,710 CJ) .p. Water 261 2, 710 5 2,230 (3) N/A 7.6 76-CV-316-2W Water Water 647 2,535 Water 654 2,535 5 2,350. 531 N/A 3.9 77-CV-316-75/W Transition Steam 670 2,532 Water 657 2,532 6 2,343 555 N/A 12.6 78-CV-3i.6-8W/W Water Water 134 2, 725 Water 554 2, 725 16 2,350 640 N/A 7.8 Seal Simulation 79-CV-316-9N/W Transition GN 2 262 1,533 Water 299 1,533 6 1,300 150 N/A 5.1 (1) GNz PORV Actuation Ullage Pressure for all Tests was 86 (: 1) psig. (2) No Back Pressure Orifice was used in the Copes-Vulcan 316 PORV Testing. (3) PS-4 In operative during this test. * * 
                                                                              ~~~
*
WJt2:""     ~~2      2,545     4       2,170   387         N/A       4.6 73-CV-316-4W       Water           Water             442             675       Water       442         675   10         626   193         N/A       7.7 74-CV-316-5W       Water           Water             105             675       Water         92.       675   10         562   174         N/A         8.6 I
* EPRI/WYLE Phase III PORV TEST DATA lABLE 4.6.l-2b  
CJ)  75-CV-316-6W       Water           Water             274     2,710             Water       261     2, 710     5       2,230     (3)       N/A
.p.                                                                                                                                                              7.6 76-CV-316-2W         Water           Water             647     2,535             Water       654     2,535     5       2,350. 531         N/A         3.9 77-CV-316-75/W       Transition     Steam             670     2,532             Water       657     2,532     6       2,343   555         N/A       12.6 78-CV-3i.6-8W/W     Water           Water             134     2, 725           Water       554     2, 725   16       2,350   640         N/A         7.8 Seal Simulation 79-CV-316-9N/W     Transition       GN 2               262     1,533             Water       299     1,533       6       1,300   150         N/A         5.1 (1) GNz PORV Actuation Ullage Pressure for all Tests was 86 (: 1) psig.
(2) No Back Pressure Orifice was used in the Copes-Vulcan 316 PORV Testing.
(3) PS-4 In operative during this test.
* EPRI/WYLE Phase III PORV TEST DATA lABLE 4.6.l-2b


==SUMMARY==
==SUMMARY==
OF COPES W/STELLITE PLUG AND 17-4 PH CAGE} RELIEF VALVE PERFORMANCE 71-CV 72-CV 73-CV 74-CV 75-CV 76-CV 77-CV *78-CV 79-CV 316-lS 316-3W 316-4W 316-5W 316-6W 316-2W 316-75/W 316-BW/W 316-9N/W Pre-Test Leakage(!)
OF COPES VULCA~(316 W/STELLITE PLUG AND 17-4 PH CAGE} RELIEF VALVE PERFORMANCE 71-CV     72-CV     73-CV     74-CV   75-CV     76-CV     77-CV     *78-CV     79-CV 316-lS     316-3W     316-4W   316-5W   316-6W   316-2W   316-75/W 316-BW/W 316-9N/W Pre-Test Leakage(!)
Media Steam Water Water Water Water Water Water Water Water Pressure (psia) 2,755 2,530 923 805 2,695 2,573 2,605 2,730 1,600 Temp (OF) 685 470 441 100 270 643 624 116 299 Leakage (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0040 0.0013 Transient Performance Total Valve Opening Time (sec) 0.60 0.55 1.01 0.98 0.64 0. 72 0.70 0.61 0.78 Main Disc Opening Time (sec) 0.39 0.48 0.66 0.60 0.55 0.56 0.60 0.53 0.56 Valve Flow Rate (lb/Hr) 255,600 1,008,000 388,800 619,200 1,173,600 540,000 540,000 612,000 864,000 -+::> Corresponding Valve I Inlet Press (psia) 2,443 2,190 638 580 2,270 2,_390 2,365 2,480 O"> t.n Corresponding Valve Inlet Temp (OF) 669 449 444 100 281 649 651 632 299 Corresponding Valve Outlet Press (psia) 410 387 188 0 (2) 531 540 610 82 Corresponding Valve Outlet Temp (OF) 427 350 362 90 250 400 448 482 278 Corresponding Test Time Relative to Open Command (sec) 2.7 1.6 2.8 .4.2 1. 8 1. 7 2.2 4.0 2.5 Inlet Pressure at Beginning of Valve Closing (psia) 2,310 2, 160 628 565 2,220 2,350 2,345 2,320 1,300 Total Valve Closing Time (sec) 1.43 1. 31 0.60 0.66 1.44 1.38 1. 37 1.44 0.88 Main Disc Closing Time (sec) 1.16 1.16 0.49 0.53 1.28 1.16 1.16 1.24 0. 76 Post-Test Leakage(l)
Media                       Steam     Water     Water     Water   Water     Water     Water     Water   Water Pressure (psia)             2,755         2,530     923       805   2,695   2,573     2,605     2,730   1,600 Temp (OF)                       685           470   441       100       270     643     624       116       299 Leakage (GPM)               0.0013       0.0013 0.0013     0.0013   0.0013   0.0013   0.0013   0.0040   0.0013 Transient Performance Total Valve Opening Time (sec)             0.60         0.55   1.01     0.98     0.64     0. 72     0.70       0.61     0.78 Main Disc Opening Time (sec)             0.39         0.48   0.66     0.60     0.55     0.56     0.60       0.53     0.56 Valve Flow Rate (lb/Hr)   255,600   1,008,000 388,800   619,200 1,173,600 540,000   540,000   612,000   864,000 Corresponding Valve
Media Steam Water Water Water Water Water Water Water Water Pressure (psia) 2,185 2,615 735 675 2,630 2,518 2,475 2,625 1,560 Temp (OF) 647 426 427 100 257 608 631 445 281 Lr:>ak Rate (psia) 0.035 0.0013 0.0013 0.0013 o.orm 0.015 O.Oln 0.0011
-+::>
--------------*
I O">
*-** TABLE 4.6.l-2b (Cont'd) Notes: (i) Rec1Jrded leakages of 0.0013 indicate values of less than or equal to 0. 0013. (2) ,PS-4 .in-operative during this test. 4-66 ' ' * * * 
Inlet Press (psia)   2,443       2,190     638       580     2,270   2,_390   2,365     2,480   1~330 t.n       Corresponding Valve Inlet Temp (OF)         669           449   444       100       281     649     651       632       299 Corresponding Valve Outlet Press (psia)     410         387     188         0       (2)     531     540       610         82 Corresponding Valve Outlet Temp (OF)         427         350     362         90       250     400     448       482       278 Corresponding Test Time Relative to Open Command (sec)           2.7         1.6     2.8       .4.2       1. 8     1. 7     2.2       4.0       2.5 Inlet Pressure at Beginning of Valve Closing (psia)       2,310       2, 160     628       565     2,220   2,350     2,345     2,320   1,300 Total Valve Closing Time (sec)             1.43         1. 31   0.60     0.66     1.44     1.38     1. 37     1.44     0.88 Main Disc Closing Time (sec)             1.16       1.16     0.49     0.53     1.28     1.16     1.16       1.24     0. 76 Post-Test Leakage(l)
' ' ** * * ' ' 4.7 COPES-VULCAN RELIEF VALVE (17-4PH PLUG AND CAGE) 4.7.1 "As Tested" Test Mat.rices and Valve Performance Data Tests were performed on the Copes-Vulcan relief valve model with the 17-4PH Plug and Cage at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Copes-Vulcan relief valve tested at each of the test facilities.  
Media                       Steam     Water     Water     Water   Water     Water     Water     Water   Water Pressure (psia)             2,185       2,615       735     675     2,630   2,518     2,475     2,625     1,560 Temp (OF)                     647         426     427       100       257     608     631       445       281 Lr:>ak Rate (psia)           0.035     0.0013   0.0013   0.0013   o.orm     0.015   0.00~2      O.Oln   0.0011
: 4. 7. 2 Test FacilJ!t Ma,rshall Wy le ( Phase I I I ) Principal Observations Marshall Steam Station "As Tested" Test Matrix Table 4.7.l-la 4.7.l-2a*
 
Valve Performance Data Table 4.7.l-lb .4. 7. l -2b The valve fully opened on demand and closed on demand for each of the eleven (11) evaluation test cycles. After these tests were completed, a new set'of 'the same design cage and plug parts were installed and the valve was cycled to investigate the cage to body gasket performance and to support other Marshall Steam Station test functions.
TABLE   4.6.l-2b (Cont'd)
The valve fully opened on demand and fully clos.ed on demand for the next 43 cycles. Six (6) of these cycles were performed under full pressure/flow conditions.
Notes:
The remaining cycles were either dry, surized actuations or openings/closings performed in conjunction with other valve testing. During the next 5 full pressure/flow tests performed, the valve did not fully close on demand. However, the valve always closed to within 13% of the full closed position.
(i) Rec1Jrded leakages of 0.0013 indicate values of less than or equal to
Disassembly showed galling of the cage and plug guiding surfaces.
: 0. 0013.
4-67 .
(2) ,PS-4 .in-operative during this test.
* I I 
4-66
' ' * *
 
* Wyle Phase III A total of eight (8) were performed on this valve design. During all tests, the valve fully opened and fully closed on demand. Following completion of testing, the valve was disassembled and inspected by the Copes-Vu 1 can representative.
                                                                                              ~.  .
The cage to body gasket had partially "washed out" during testing .. No damage was observed that would affect future valve performance . 4-69 *.*!* 
**     4.7     COPES-VULCAN RELIEF VALVE (17-4PH PLUG AND CAGE) 4.7.1 "As Tested" Test Mat.rices and Valve Performance Data Tests were performed on the Copes-Vulcan relief valve model with the 17-4PH Plug and Cage at the Marshall Steam Station and during Phase III of the Wyle Test Program.
.+::> I ....... 0
* I The following is the list of tables that contain the "as tested" test matrices and           I valve performance data for the Copes-Vulcan relief valve tested at each of the test facilities.
* EPRI/ MARSHALL PORV TEST DATA (3) TABLE 4.7.1-la "AS TESTED" MARSHALL TEST MATRIX FOR THE COPES-VULCAN (17-4PH PLUG AND CAGE) RELIEF VALVE CONDITIONS VALVE INLET TEST TEST FLUID PRESS. NO. TYPE (PSIA) STEAM STEAM 2455 2 STEAM STEAM 2455 3 STEAM STEAM 2430 4 STEAM STEAM 2475 STEAM STEAM 2475 6 STEAM STEAA 2445 7 STEAM STEAM 2435 8 STEAM STEAM 2445 9 STEAM STEAM 2505 10 STEAM STEAM 2445 ll STEAM STEAM 2455 NOTES: (1) Maximum Quasi steady pipe pressure.  
Test                       "As Tested" Test       Valve Performance FacilJ!t                        Matrix Table           Data Table Ma,rshall                        4.7.l-la                 4.7.l-lb Wy le ( Phase I I I )            4.7.l-2a*              .4. 7. l -2b
* 4. 7. 2        Principal Observations Marshall Steam Station The valve fully opened on demand and closed on demand for each of the eleven (11) evaluation test cycles.
After these tests were completed, a new set'of 'the same design cage and plug parts were installed and the valve was cycled to investigate the cage to body gasket performance and to support other Marshall Steam Station test functions. The valve fully opened on demand and fully clos.ed on demand for the next 43 cycles. Six (6) of these cycles were performed under full pressure/flow conditions. The remaining cycles were either dry, unpres-surized actuations or openings/closings performed in conjunction with other valve testing. During the next 5 full pressure/flow tests performed, the valve did not fully close on demand. However, the valve always closed to within 13% of the full closed position. Disassembly showed galling of the cage and plug guiding surfaces.
4-67
* Wyle Phase III A total of eight (8) te~ts were performed on this valve design.
tests, the valve fully opened and fully closed on demand.
During all Following completion of testing, the valve was disassembled and inspected by the Copes-Vu 1can representative. The cage to body gasket had partially "washed out" during testing . . No damage was observed that would affect future valve performance .
* 4-69
 
EPRI/     MARSHALL       PORV TEST DATA (3)
TABLE     4.7.1-la "AS TESTED" MARSHALL TEST MATRIX FOR THE COPES-VULCAN (17-4PH PLUG AND CAGE) RELIEF VALVE CONDITIONS AT VALVE' OPENING                                      TRANSIENT CONDITIONS VALVE INLET                         IN ACCUMULATOR                TEST          VALVE INLET        MAXIMUM ~l)
TEST       TEST         FLUID                                                                     DURATION        PRESS. WHEN        DISCHARG PRESS.      TEMP.      FLUID        PRESS.      TEMP.        (SEC)          SIGNAL GIVEN      PIPE PRESS.
NO.       TYPE                     (PSIA)      (OF)                    (PSIA)       (OF)                        TO CLOSE VALVE        (PSIA)
PSIA)
STEAM       STEAM       2455       (SAT.)        SAME AS VALVE INLET                    77                2145              595 2         STEAM       STEAM       2455       (SAT.)                                              32                2175              605 3         STEAM       STEAM       2430       (SAT.)                                              33                2185              615 4       STEAM         STEAM       2475       (SAT.)                                                37                2210              615 STEAM       STEAM         2475       (SAT.)                                                30                2195              615
.+::>
6       STEAM       STEAA         2445       (SAT.)                                                71                2135              195 I
.......      7       STEAM       STEAM         2435       (SAT.)                                                38                2165 0                                                                                                                                                      195 8       STEAM       STEAM         2445       (SAT.)                                                38                2195              195 9       STEAM       STEAM         2505       (SAT.)                                                49                2195              195 10       STEAM       STEAM         2445       (SAT.)                                                46                2175              195 ll       STEAM       STEAM         2455       (SAT.)                                                (2)              2185              615 NOTES:
(1) Maximum Quasi steady d~scharge pipe pressure.
(2) Not recorded.
(2) Not recorded.
TEMP. (OF) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) AT VALVE' OPENING TRANSIENT CONDITIONS IN ACCUMULATOR TEST VALVE INLET DURATION PRESS. WHEN FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN (PSIA) (OF) TO CLOSE VALVE PSIA) SAME AS VALVE INLET 77 2145 32 2175 33 2185 37 2210 30 2195 71 2135 38 2165 38 2195 49 2195 46 2175 (2) 2185 MAXIMUM DISCHARG PIPE PRESS. (PSIA) 595 605 615 615 615 195 195 195 195 195 615 (3) Test results are for evaluation tests only. Total of 22 supplementary valve actuation cycles were performed under similar conditions  
(3) Test results are for evaluation tests only. Total of 22 supplementary valve actuation cycles were performed under similar conditions *
* * * 
* EPRI/
*
MARSHALL       ?ORV TEST DATA (J)
* EPRI/ MARSHALL ?ORV TEST DATA (J) TABLE 4.7.1-lb  
TABLE 4.7.1-lb


==SUMMARY==
==SUMMARY==
OF COPES-VULCAN (17-4PH PLUG AND CAGE) RELIEF VALVE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VALVE (I) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPEN ING TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM) STEAM 1. 600 STEAM 2145 (SAT.) 595 221,000 1. 950 STEAM 2445 (SAT.) 0.788 A pre-operational leakage test showed 0.0 GPl-4 leakage 2 STEAM 1.300 * * *
OF COPES-VULCAN (17-4PH PLUG AND CAGE) RELIEF VALVE FLOW MEASUREMENT CONDITIONS                                       LEAKAGE MEASUREMENTS               COMMENTS VALVE TOTAL VALVE (I)           VALVE INLET           OUTLET     FLOW TEST      TEST    OPEN ING TIME                                                    TOTAL VALVE (2)                 VALVE INLET       LEAKAGE FLUID   PRESS. TEMP. PRESS. RATE     CLOSING TIME       MEDIA NO.       TYPE         (SEC)               (PSIA)     (OF)                                                     PRESS. TEMP.      RATE (PSIA)   (LBM/HR)     (SEC)                   (PSIA)     (OF)     (GPM)
* 2.000 .. * .. 3 STEAM 1.100 * .. *
STEAM       1. 600       STEAM     2145       (SAT.)     595   221,000     1. 950         STEAM       2445       (SAT.)   0.788 A pre-operational leakage test showed 0.0 GPl-4 leakage 2       STEAM       1.300                     *         *         *
* 2.100 *
* 2.000               .                     *           ..
* 4 STEAM 1.300 * * * * .. 2.000 * * * .. 5 STEAM 1. 400 * * .. ..
3       STEAM       1.100                     *           .         *
* 2.000 STEAM 2455 {SAT.) 0.304 6 STEAM 1.400 STEAM 2135 (SAT.) 195 220,000 1.700 .. * * * -+:> I STEAM 1. 300 * * .. *
* 2.100               *
* 1. 700 * * * * ---.I f-' 8 STEAM 1. 300 * .. * *
* 4       STEAM       1.300             *       *           *       *       .       2.000             *           *         *         .
* 1.655 ..
5       STEAM       1. 400           *       *         .         .
* 9 STEAM 1. 400 * * .. ..
* 2.000           STEAM       2455       {SAT.)   0.304
* 1.700 .. " .. 10 STEAM 1.400 * .. * *
-+:>
* 1.600 * * *
6       STEAM       1.400         STEAM     2135     (SAT.)     195   220,000     1.700               .         *           *
* 11 STEAM 1. 500 .. " * *
* I
* 1. 700 STEP.M 2435 (SAT.) 0.280 not applicable to this test NOTES: (!) Opening time measured from time of energizing solenoid until valve reaches full open position.  
---.I STEAM       1. 300           *         *         .       *
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.  
* 1. 700             *
(3) Test results are for evaluation tests only. Total of 22 supplementary valve actuation tests were performed under similar conditions.  
* f-'                                                                                                                                       *
----
* 8       STEAM       1. 300           *       ..         *       *
_____ _
* 1.655             .
EPRI/WYLE Phase Ill PORV TEST noTn TABLE 4.7.l-2a TESTED" WYLE PHASE l I I TEST M/\TR IX FOR THE COPES VULCAN {l 7-4 Plf PLUG AND CAGE)RELIEF VALVE INITIAL CONDITIONS(!)
* 9       STEAM       1. 400           *       *         .         .
TRANSIENT CONDITIONS Valve At Valve Inlet In Accumulator Inlet Pressure Maximum Maximum Maximum at Discharge Bending Valve Test Closure Pipe Moment Acceleration Temp Press. Temp Press. Duration Signal Press.(2)
* 1.700             .                                 .
Induced(3)!nduced Test No. Test Type Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (ln-lb) (g's) 63-CV-174-lS Steam Steam 682 2, 745 Steam 676 2, 745 6 2,365 450 N/A 7.2 64-CV-174-2S Steam Steam 682 2, 745 Steam 677 2,745 6 2,365 470 43,000 10.4 (Pre load) ..,. 65-CV-174-4W Water Water 455 2,535 Water 452 2,535 4 2, 180 425 N/A 5.9 I -....i N 66-CV-174-3W Water Water 442 675 Water 441 675 10 630 193 N/A 11.6 67-CV-174-5W Water Water 106 675 Water 109 675 10 572 8.8 N/A 7.7 68-CV-l 74-6W Water Water 647 2,545 Water 653 2,545 5 2,340 537 . N/A 10.9 69-CV-174-7S/W Trans it ion Steam 671 2,545 Water 648 2,545 5 2,332 546 N/A 11.8 70-CV-174-BW/W Water Water 115 2, 715 Water 651 2, 715 16 2,293 618 N/A 12.2 Seal Simulation (1) GN 2 PORV Actuation Ullage pressure for all tests was 86 .:!: 1 psig. (2) No back pressure orifice was used in the Copes-Vulcan (17-4) PORV testing. (3) Value shown corresponds to the maximum moment applied while the valve was in the opening/closing process. * *
10       STEAM       1.400           *         ..         *         *
* EPR!/WYLE II PORV TEST DATA TABLE 4.7.l-Zb SUW*IARY OF COPES-VULCAN (17-4 PH PLUG AND CAGE)RELIEF VALVE PERFORMANCE Test 63-CV 64-CV 65-CV 66-CV 67-CV 68-CV 69-CV 70-CV Number 174-lS 174-25 174-4W l 74-3W 174-5W l 74-6W 174-BW/W (1) Media Steam Steam Water Water Water Water Water Water Pressure (psia) 2,802 2,745 2,861 1, 185 765 2,615 2,620 2,805 Temp (OF) 684 681 445 442 104 636 634 105 Leak Rate (GPM) 0.0013 0.046 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) 0.57 0.49 0.57 0.97 0.90 0.66 0.52 0.50 Main Disc Opening Time (sec) 0.45 0.40 0.44 0.58 0.52 0.54 0.41 0.41 Valve Flow Rate (lb/Hr) 255,600 265,700 997,200 399,600 630,000 547 ,200 576,000 601,200 Corresponding Valve Inlet Press (psia) 2,477 2,505 2,210 638 585 2, 385 . 2,352 2,430 +:> Corresponding Valve I Inlet Valve (OF) "" w 670 671 455 444 112 648 649 641 Corresponding Valve Outlet Pressb(psia) 375 390 415 191 1.0 525 540 570 Corresponding Valve Outlet Temp (OF) 418 415 400 371 102 400 420 479 Corresponding Test Time Relative to Open CormJand (sec) 2.6 2.1 2.0 3.8 4.1 1. 7 1. 9 5.7 Inlet Pressure at Beginning of Valve Closure (psia) 2,345 2,345 2, 180 632 575 2,340 2,330 2,290 Total Valve Closure Time (sec) 1. 34 1. 34 1.15 0.54 0.61 1.29 1.27 1. 35 Main Disc Closing Time (sec) 0.98 o.g5 0.82 0.35 0.40 0.97 0.97 1.35 Post-Test Leakage(!)
* 1.600             *           *         *
Media Steam Steam Water Water Water Water Water Water Pressure (psia) 2. 747 2, 760 2,685 750 665 2,470 2,240 2,420 Temp (OF) 680 682 422 423 110 593 605 443 Leak Rate (GPM) 0.04 0.073 0.0013 0.0013 0.0016 0.0164 0.011 0.023 Notes: (1) Recorded leakages of .0013 GPM indicate measured values less than nr equal to .0013 GPM. 
* 11       STEAM       1. 500           .       "           *         *
* 1. 700         STEP.M     2435       (SAT.)     0.280 not applicable to this test NOTES:
(!) Opening time measured from time of energizing solenoid until valve reaches full open position.
(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.
(3) Test results are for evaluation tests only. Total of 22 supplementary valve actuation tests were performed under similar conditions.
                                                                                                                                              ~~~----     ----                                   _ _ _ _ __
                                                                                                                                                                ~-=c==c'----'='-'*=-=-=*-::_::-_c-*


===4.8 MUESCO===
EPRI/WYLE Phase Ill PORV TEST noTn TABLE 4.7.l-2a
CONTROLS RELIEF VALVE
                                                              ~/IS  TESTED" WYLE PHASE l I I TEST M/\TR IX FOR THE COPES VULCAN {l 7-4 Plf PLUG AND CAGE)RELIEF VALVE INITIAL CONDITIONS(!)                                                      TRANSIENT CONDITIONS Valve Inlet At Valve Inlet                    In Accumulator                        Pressure Maximum      Maximum Maximum at       Discharge  Bending    Valve Test     Closure    Pipe        Moment    Acceleration Temp        Press.              Temp        Press. Duration Signal      Press.(2)  Induced(3)!nduced Test No.             Test Type        Fluid    (OF)        (psi a)  Fluid      (OF)        (psi a)    (seconds) (psi a)    (psi a)    (ln-lb)    (g's) 63-CV-174-lS        Steam            Steam      682        2, 745    Steam        676      2, 745        6      2,365      450        N/A        7.2 64-CV-174-2S        Steam            Steam      682        2, 745    Steam        677      2,745 (Pre load)                                                                            6      2,365      470        43,000    10.4 I
* 4.8.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the MUESCO Controls relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the MUESCO Controls relief valve tested at each of the test facilities.
65-CV-174-4W        Water            Water      455        2,535    Water      452        2,535        4       2, 180    425        N/A          5.9
Test Facility Marshall Wyle (Phase Ill) 4.8.2 Principal Observations Marshall Steam Station "As Tested" Test Matrix Table 4.8. l-la 4.8. l-2a Valve Performance Data Table 4.8.l-lb 4.8.l-2b The valve fully opened on demand and fully closed on demand for each of the initial eleven (11) evaluation test cycles. An additional eleven (11) evaluation tests were performed on the valve with a replacement stem, plug and gaskets. These parts had exhibited wear and the stem was observed to be bent slightly following the first set of tests and a second set of tests was by MUESCO Controls for information purposes.
-....i N
The valve fully opened on demand and fully closed on demand for each of the evaluation test cycles. Similar wear patterns were found and the replacement stem was bent slightly.
66-CV-174-3W        Water            Water      442          675    Water        441          675      10          630    193        N/A        11.6 67-CV-174-5W          Water          Water      106          675    Water        109          675      10          572    8.8         N/A          7.7 68-CV-l 74-6W        Water          Water      647        2,545    Water        653      2,545        5      2,340    537 .       N/A        10.9 69-CV-174-7S/W      Trans it ion    Steam      671        2,545    Water        648      2,545        5      2,332      546        N/A      11.8 70-CV-174-BW/W      Water            Water      115        2, 715    Water      651        2, 715      16      2,293      618        N/A      12.2 Seal Simulation (1) GN 2 PORV Actuation Ullage pressure for all tests was 86 .:!: 1 psig.
During supplementary tests prior to the initial evaluation tests, valve opening times as long as* ten (10) seconds and closing times as long as twenty (20) seconds were observed.
(2) No back pressure orifice was used in the Copes-Vulcan (17-4) PORV testing.
The air supply solenoid valve supplied by MUESCO was replaced prior to evaluation testing with the solenoid valve 4-75 
(3) Value shown corresponds to the maximum moment applied while the valve was in the opening/closing process.


at Marshall for all other air operated relief valve tests. The Marshall air supply line solenoid valve had a larger orifice area than the solenoid valve which was supplied by MUESCO with the test valve. Wyle Phase III A total of seven (7) tests were performed on this valve design. During all tE*sts the valve fully opened and fully closed on demand. Following completion of testing, the valve was disassembled and inspected by the MUESCO Controls representative.
EPR!/WYLE            II PORV TEST DATA TABLE 4.7.l-Zb SUW*IARY OF COPES-VULCAN (17-4 PH PLUG AND CAGE)RELIEF VALVE PERFORMANCE Test                              63-CV      64-CV    65-CV      66-CV      67-CV    68-CV    69-CV        70-CV Number                              174-lS    174-25    174-4W    l 74-3W    174-5W    l 74-6W    174-75/I~  174-BW/W Pre-Te~t  L'!akaa~ (1)
Scratches were observed on the plug gLiding surface.*
Media                        Steam      Steam    Water      Water      Water    Water    Water      Water Pressure (psia)              2,802      2,745    2,861      1, 185        765    2,615    2,620        2,805 Temp (OF)                        684        681        445      442        104      636      634          105 Leak Rate (GPM)              0.0013      0.046    0.0013    0.0013      0.0013  0.0013    0.0013      0.0013 Transient Performance Total Valve Opening Time (sec)              0.57      0.49      0.57      0.97        0.90      0.66      0.52        0.50 Main Disc Opening Time (sec)                0.45      0.40      0.44      0.58        0.52      0.54      0.41        0.41 Valve Flow Rate (lb/Hr)    255,600    265,700 997,200      399,600 630,000 547 ,200 576,000            601,200 Corresponding Valve Inlet Press (psia)    2,477      2,505      2,210        638        585    2, 385 . 2,352      2,430
No damage was observed that wo.uld affect future valve performance.
+:>      Corresponding Valve I
4-77
Inlet Valve (OF)          670        671        455 w                                                                          444        112        648      649        641 Corresponding Valve Outlet Pressb(psia)        375        390        415        191        1.0        525      540        570 Corresponding Valve Outlet Temp (OF)          418        415        400        371        102        400      420        479 Corresponding Test Time Relative to Open CormJand (sec)        2.6        2.1        2.0        3.8        4.1        1. 7      1. 9        5.7 Inlet Pressure at Beginning of Valve Closure (psia)      2,345      2,345      2, 180      632        575    2,340      2,330      2,290 Total Valve Closure Time (sec)                1. 34      1. 34    1.15      0.54        0.61      1.29      1.27        1. 35 Main Disc Closing Time (sec)              0.98      o.g5      0.82      0.35        0.40      0.97      0.97        1.35 Post-Test Leakage(!)
.i:::. I -....J (X) EPRI/ MARSHALL PORV TEST DATA ( 3) TABLE 4.B.1-la "AS MARSHALL TESi MATRIX FOR THE MUESCO RELIEF VALVE CONDITIONS VALVE INLET TEST TEST FLUID PRESS. TEMP. NO. TYPE (PSIA) (OF) STEAM STEAM 2435 (SAT.) 2 STEAM STEAM 2425 (SAT.) 3 STEAM STEAM 2415 (SAT.) 4 STEAM STEAM 2415 (SAT.) STEAM STEAM 2415 (SAT.) 6 STEAM STEAM 2455 (SAT.) STEAM STEAM 2455 (SAT.) 8 STEAM STEAM 2455 (SAT.) 9 STEAM STEAM 2455 (SAT.) IO STEAM STEAM 2445 (SAT.) 11 STEAM STEAM 2455 (SAT.) NOTES: (1) Maximum Quasi steady discharge pipe pressure.  
Media                    Steam      Steam    Water      Water      Water    Water    Water        Water Pressure (psia)                2. 747    2, 760    2,685          750        665    2,470      2,240      2,420 Temp (OF)                        680        682        422      423        110      593        605        443 Leak Rate (GPM)                0.04    0.073    0.0013    0.0013      0.0016    0.0164    0.011        0.023 Notes:
(2) Not recorded.
(1) Recorded leakages of .0013 GPM indicate measured values less than nr equal to .0013 GPM.
AT VALVE OPENING IN ACC.JMULATOR TEST DURATION FLUID PRESS. TEMP. (SEC) (PSIA) (DF) SAME AS VALVE INLET 59 17 16 20 16 55 16 i I 17 j 17 18 (2) TRANSIENT CONDITIONS VALVE INLET MAXIMUM pl PRESS. \.:HEN DISCHARG SIGNAL GIVEN PIPE PRESS. TO CLOSE VALVE (PSIA) (PSIA) 2385 255 2375 255 2375 255 2375 255 2375 255 2427 80 2415 85 2415 85 2no5 85 2400 75 2405 85 (3) Test-results are for evaluation tests only. Total of 14 supplementary valve actuation cycles were performed under similar conditions . * 
 
.;:,. I -....J I.Cl * .EPRI I MARSHALL*
~ 4.8  MUESCO CONTROLS RELIEF VALVE 4.8.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the MUESCO Controls relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program.
PORV TEST DATA (3) TABLE 4.8.l-lb  
The following is the list of tables that contain the "as tested" test matrices and valve performance data for the MUESCO Controls relief valve tested at each of the test facilities.
Test                        "As Tested" Test      Valve Performance Facility                          Matrix Table          Data Table Marshall                          4.8. l-la              4.8.l-lb Wyle (Phase Ill)                  4.8. l-2a              4.8.l-2b 4.8.2 Principal Observations Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the initial eleven (11) evaluation test cycles.
An additional eleven (11) evaluation tests were performed on the valve with a replacement stem, plug and gaskets. These parts had exhibited wear and the stem was observed to be bent slightly following the first set of tests and a second set of tests was reco~mended by MUESCO Controls for information purposes. The valve fully opened on demand and fully closed on demand for each of the evaluation test cycles. Similar wear patterns were found and the replacement stem was bent slightly.
During supplementary tests prior to the initial evaluation tests, valve opening times as long as* ten (10) seconds and closing times as long as twenty (20) seconds were observed. The air supply solenoid valve supplied by MUESCO was replaced prior to evaluation testing with the solenoid valve
* 4-75
 
u~;ed at Marshall for all other air operated relief valve tests. The Marshall air supply line solenoid valve had a larger orifice area than the solenoid valve which was supplied by MUESCO with the test valve.
Wyle Phase III A total of seven (7) tests were performed on this valve design. During all tE*sts the valve fully opened and fully closed on demand.       Following completion of testing, the valve was disassembled and inspected by the MUESCO Controls representative.     Scratches were observed on the plug gLiding surface.* No damage was observed that wo.uld affect future valve performance.
4-77
 
EPRI/     MARSHALL       PORV TEST DATA ( 3)
TABLE   4.B.1-la "AS TESTE~" MARSHALL TESi MATRIX FOR THE MUESCO RELIEF VALVE CONDITIONS AT VALVE OPENING                                      TRANSIENT CONDITIONS VALVE INLET                         IN ACC.JMULATOR                  TEST DURATION VALVE INLET PRESS. \.:HEN MAXIMUM DISCHARG pl TEST          TEST         FLUID       PRESS.     TEMP.       FLUID        PRESS.        TEMP.          (SEC)      SIGNAL GIVEN        PIPE PRESS.
NO.         TYPE                     (PSIA)       (OF)                     (PSIA)        (DF)                      TO CLOSE VALVE          (PSIA)
(PSIA)
STEAM       STEAM       2435       (SAT.)           SAME AS VALVE INLET                  59              2385                255 2         STEAM       STEAM         2425       (SAT.)                                                 17              2375                255 3         STEAM       STEAM         2415       (SAT.)                                                 16              2375                255 4         STEAM       STEAM         2415       (SAT.)                                                 20              2375              255 STEAM       STEAM         2415       (SAT.)                                                 16              2375              255 6         STEAM       STEAM         2455       (SAT.)                                                 55              2427                80 STEAM       STEAM         2455       (SAT.)                                                 16            2415                  85 8                                                                           i
.i:::.              STEAM       STEAM         2455       (SAT.)                                                 17            2415                  85 I
-....J 9         STEAM       STEAM         2455       (SAT.)
I (X)                                                                                                              17            2no5                  85 IO 11 STEAM STEAM STEAM STEAM 2445 2455 (SAT.)
(SAT.)
j                          18 (2) 2400 2405 75 85 NOTES:
(1) Maximum Quasi steady discharge pipe pressure.
(2) Not recorded.
(3) Test-results are for evaluation tests only. Total of 14 supplementary valve actuation cycles were performed under similar conditions .
 
        *                                                               .EPRI I MARSHALL* PORV TEST DATA (3)
TABLE 4.8.l-lb


==SUMMARY==
==SUMMARY==
OF MUESCO RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS TEST NO. 6 8 9 10 11 VALVE TOTAL VALVE (l) VALVE INLET OUTLET FLOW TOTAL VALVE (2) TEST OPEN it<G T iME FLviD PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) STEAM 2.800 STEAM 2385 (SAT.) 255 100,000 1.750 STEAM STEAM 2.900 * * *
OF MUESCO RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS                                 LEAKAGE MEASUREMENTS               COMMENTS VALVE TOTAL VALVE (l)           VALVE INLET       OUTLET     FLOW   TOTAL VALVE (2)               V1~L VE INLET    LEAKAGE TEST     TEST      OPEN it<G TiME  FLviD     PRESS. TEMP. PRESS. RATE     CLOSING TIME     MEDIA   PRESS.      TEMP. RATE NO.      TYPE           (SEC)                 (PSIA)     (OF) (PSIA)   (LBM/HR)     (SEC)                 (PSIA)      (OF)    (GPM)
STEAM       2.800         STEAM                                                                                                 A pre-operational leakage 2385     (SAT.)   255   100,000     1.750         STEAM     2485        (SAT.) 0.056  test showed 0.0 GPM leakage STEAM       2.900                       *       *       *
* l. 600
* l. 600
* STEAM 2.300. * * *
* STEAM       2.300.         *         *         *
* l. 550
* l. 550           *                      *
* STEAM 2.000 1.550
* STEAM       2.000                                                         1.550             *          .*          *
* STEAM 2.500 * ..
* STEAM       2.500                     *         .
* I. 550 STEAM STEAM 2.100 2427 (SAT.) 80 101,000 1.700
* I. 550         STEAM     2475        (SAT.)    0.046 6      STEAM       2.100         STE~!"    2427     (SAT.)     80   101,000     1.700           *
* STEAM 2.700 * *
* I
* 1.500
-....J STEAM       2.700                     *         *
* STEAM 2.500 *
* 1.500           *                      *
* 1.600
* I.Cl 8      STEAM       2.500                               *
* STEAM 2.800 * *
* 1.600                                   *
* 1.500
* 9      STEAM       2.800                     *       *
* STEAM 3.900 .. * *
* 1.500             *                      *
* 1.600
* 10      STEAM       3.900                     .       *       *
* STEAM 2.000 * * ..
* 1.600             *                      *
* 1.700 STEAM not applicable to this test Opening time measured from of energizing solenoid until valve reaches full open position.
* 11      STEAM       2.000                     *       *       .
Closing time measured from time of de-energizing.solenoid until valve reaches full closed position, VE INLET LEAKAGE PRESS. TEMP. RATE (PSIA) (OF) (GPM) 2485 (SAT.) 0.056 * * .* *
* 1.700           STEAM     2455        (SAT.)    0.075 not applicable to this test NOTES:
* 2475 (SAT.) 0.046 " * * * " * * * * *
(1)  Opening time measured from ti~e of energizing solenoid until valve reaches full open position.
* 2455 (SAT.) 0.075 COMMENTS A pre-operational leakage test showed 0.0 GPM leakage NOTES: (1) (2) (3) Test results are for evaluation tests only. Total of 14supplementary valve actuation tests were performed under similar conditions.
(2)  Closing time measured from time of de-energizing.solenoid until valve reaches full closed position, (3)   Test results are for evaluation tests only. Total of 14supplementary valve actuation tests were performed under similar conditions.
.j::> I co 0 At Valve Temp Test No. Test Type Fluid (OF) 80-MU-lS Steam Steam 683 81-MU-2S Steam . Steam 670 (Pre load) 82-MU-3W Water Water 455 83-MU-4W Water Water 449 84-MU-5W Water Water 106 85-MU-6W Water Water 645 86-MU-75/W Transition Steam 670 EPRI/WYLE Phase Ill PORV TEST DATA TABLE 4.8.l-2a "AS TESTED" WYLE Plll\SE Ill TEST MATRIX FOR THE MUESCO CONTROLS RELIEF VALVE INITIAL CONDITIONS(!)
 
Inlet Jn Accumulator Test Press. Temp Press. Duration (psi a) Fluid (OF) (psia) (seconds) 2, 755 Steam 678 2, 755 12 2,535 Steam 665 2,535 6 2,536 Water 453 2,536 9 674 Water 452 674 11 677 Water 99 677 11 2,534 Water 651 2,534 12 2,540 Water 652 2,540 12 (1) GN 2 PORV Actuation Ullage pressure for all tests 49 ! 1 psig. (2) No back pressure orifice was used in the Muesco PORV testing. (3) Values shown corresponds to the maximum moment induced while valve is in the opening/closing process. ** TRANSIENT CONDITIONS Valve Inlet Pressure Maximum Maximum Maximum at Discharge*
EPRI/WYLE Phase Ill PORV TEST DATA TABLE 4.8.l-2a "AS TESTED" WYLE Plll\SE Ill TEST MATRIX FOR THE MUESCO CONTROLS RELIEF VALVE INITIAL CONDITIONS(!)                                                 TRANSIENT CONDITIONS Valve Inlet At Valve Inlet                   Jn Accumulator                 Pressure Maximum Maximum          Maximum at      Discharge* Bending Valve Test     Closure  Pipe        Moment      Acceleration Temp      Press.                 Temp       Press. Duration Signal    Press. ( 2) Induced ( 3) Induced Test No.            Test Type        Fluid    (OF)      (psi a)     Fluid     (OF)       (psia) (seconds) (psi a)  (psi a)    (in-lb)      (g's) 80-MU-lS            Steam            Steam      683      2, 755     Steam       678       2, 755 12       2,500    550        N/A          5.1 81-MU-2S            Steam          . Steam      670      2,535       Steam       665       2,535   6       2,418    50          24,000        5.0 (Pre load) 82-MU-3W            Water            Water      455      2,536       Water       453       2,536   9      2,410. 184        N/A          9.6
Bending Valve Closure Pipe Moment Acceleration Signal Press. ( 2) Induced ( 3) Induced (psi a) (psi a) (in-lb) (g's) 2,500 550 N/A 5.1 2,418 50 24,000 5.0 2,410. 184 N/A 9.6 674 78 N/A I. 7 649 84 N/A 20.2 2,442 llO N/A. 4.4 2,440 106 N/A 4.3 *
.j::>
* Test
I  83-MU-4W            Water            Water      449          674     Water       452         674 11         674  78          N/A          I. 7 co 0
* 80-81-Number Mu.::is M0-25 Pre-Test Leakage (1) Media Steam Steam Pressure (psia) 2,765 2,620 Temp (OF) 680 660 Leak Rate (GPM) 0.0013 0.0026 Transient Performance Total Valve Opening Time (sec) 2.09 2.03 Main Disc Opening Time (sec) 1.88 1. 77 Valve Flow Rate (lb/Hr) 112,300 93,600 Corresponding Valve I ():> Inlet Press (psia) 2,625 2,432 ...... Corresponding Valve Inlet Temp (OF) 677 666 Corresponding Valve Outlet Press (psia) 540 50 Corresponding Valve Outlet Temp (OF) 304 295 Corresponding Test Time Relative to Open Command (sec) 5.1 3.4 Inlet Pressure at Beginning of Valve Closure (psia) 2,490 2,410 Total Valve Closure Time (sec) 2.32 2.09 Main Disc Closing Time (sec) 2.26 1.93 Post-Test Leakage (1) Media Steam Steam Pressure (psia) 2,760 2,600 Temp (OF) 661 669 (r,PM) 0.00it5 0.0048 EPRI/WYLE Phase , PORV TEST DATA TABLE 4.8.I-2b  
84-MU-5W            Water            Water      106          677     Water       99         677 11         649  84          N/A          20.2 85-MU-6W            Water            Water      645      2,534       Water       651       2,534   12       2,442    llO        N/A.          4.4 86-MU-75/W          Transition        Steam      670      2,540       Water       652       2,540   12       2,440    106        N/A          4.3 (1) GN   PORV Actuation Ullage pressure for all tests wa~ 49 ! 1 psig.
(2) No 2back pressure orifice was used in the Muesco PORV testing.
(3) Values shown corresponds to the maximum moment induced while valve is in the opening/closing process.
* EPRI/WYLE Phase , PORV TEST DATA TABLE 4.8.I-2b


==SUMMARY==
==SUMMARY==
OF MUESCO CONTROLS RELIEF VALVE PERFORMANCE 82-83-84-85-86-MU-3W MU-4W MU-SW MU-6W Mu-;1s;w Water Water Water Water Water 2,605 . 705 780 2,590 2,560 421 447 100 532 6411 0.033 0.0026 0.0013 0.032 0.0238 2.20 2 .10 2.50 2.12 1.91 1.94 1.65 2.04 1.88 1.68 435,600 171,000 280,800 226,800 223,200 2,445 674 654 2,465 2,484 453 452 117 650 657 182 75 3 108 98 370 308 107 340 330 3.8 4.5 5.9 6.5 3.6 2,410 672 648 2,435 2,430 1.95 1.46 1.47 2.31 2.21 1.88 1.42 1.44 2.23 1.98 Water Water Water Water Water 2,665' 785 685 2,480 435 436 100 610 6241 O.fJ38 0.0013 0.0011 OJM9 0.02113 * ...  
OF MUESCO CONTROLS RELIEF VALVE PERFORMANCE Test
..........  
* 80-      81-      82-         83-         84-       85-     86-Number                          Mu.::is  M0-25    MU-3W       MU-4W     MU-SW     MU-6W   Mu-;1s;w Pre-Test Leakage (1)
-..
Media                      Steam    Steam    Water       Water     Water     Water   Water Pressure (psia)            2,765    2,620    2,605 .       705         780     2,590   2,560 Temp (OF)                      680      660      421       447         100       532     6411 Leak Rate (GPM)            0.0013  0.0026    0.033     0.0026     0.0013     0.032 0.0238 Transient Performance Total Valve Opening Time (sec)              2.09    2.03      2.20       2 .10       2.50     2.12     1.91 Main Disc Opening Time (sec)              1.88    1. 77    1.94       1.65       2.04     1.88     1.68 Valve Flow Rate (lb/Hr)  112,300  93,600  435,600   171,000     280,800   226,800 223,200
TABLE 4.8.l-2b (Cont'd) Notes: (1) Recorded leakages of .0013 GPM indicate a measured value of less than or equal to .0013 GPM. I . 4-82 *
~          Corresponding Valve I
* 4.9 FISHER CONTROLS RELIEF VALVE 4.9.1 "As Tested" Test Matrices and Valve Performance Data Tests performed on the Fisher Controls relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Fisher Controls relief valve tested at each of the test facilities.
():>
Test Facility Marshall Wyle (Phase III) 4.9.2 Principal Marshall Steam Station "As Tested" Test Matrix Table 4.9.l-la 4.9.l-2a Valve Performance Data Table 4.9.l-lb 4.9.l-2b The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles. At the conclusion of these tests, the v a l v e w a s d i s as s em b l e d and g a 11 i n g was observed on the p l u g and c age mat i n g surfaces.
......            Inlet Press (psia)    2,625    2,432    2,445         674         654     2,465   2,484 Corresponding Valve Inlet Temp (OF)          677    666        453       452         117       650     657 Corresponding Valve Outlet Press (psia)      540      50      182         75         3       108       98 Corresponding Valve Outlet Temp (OF)        304    295        370       308         107       340     330 Corresponding Test Time Relative to Open Command (sec)          5.1      3.4      3.8       4.5         5.9       6.5     3.6 Inlet Pressure at Beginning of Valve Closure (psia)      2,490    2,410     2,410        672         648     2,435   2,430 Total Valve Closure Time (sec)            2.32    2.09      1.95       1.46       1.47     2.31     2.21 Main Disc Closing Time (sec)            2.26    1.93      1.88       1.42       1.44     2.23     1.98 Post-Test Leakage (1)
In addition to the evaluation tests, three other sets of cycles were performed on the valve. The first two sets of cycles were performed on a set of cage and plug parts which did not represent the correct Fisher Controls design for the PORV application.
Media                      Steam    Steam    Water       Water     Water     Water   Water Pressure (psia)            2,760    2,600    2,665'         785       685     2,480   2,43~*
During the first set of cycles, the valve always closed on demand to within 4% of the full closed position on each cycle. After the cycles were completed, the valve was disassembled and galling was observed on the plug and cage mating surfaces.
Temp (OF)                      661    669        435       436         100       610     6241 LP~k R~t.<> (r,PM)        0.00it5  0.0048    O.fJ38     0.0013     0.0011     OJM9   0.02113
The galling was more severe than the evaluation test cycle galling pattern. A second set of tests were then performed using the same internals after they had been refurbished.
                                                                                                              ... --~,_ ..........- ..
For those tests, the valve fully opened on demand and fully closed on demand for each of 14 cycles. 4-83
 
* The evaluation tests were then performed on a set of cage and plug parts with correct clearances.
Notes:
These are the tests discussed in the first paragraph cif this section and they represent Fisher Controls PORVs sup-* plied to PWR plants with the correct internals.
TABLE   4.8.l-2b (Cont'd)
A fourth set of cycles were performed on a set of trim with the correct design clearances.
(1) Recorded leakages of .0013 GPM indicate a measured value of less than or equal to .0013 GPM.
The *valve fully opened on demand and fully closed on demand for each cycle. A galling pattern similar to that observed in the evaluation tests was observed.
I .
Again, it was less severe than the pattern observed when the valve did not fully close on demand Wyle Phase III During all ten (10) tests performed, the valve fully opened arid fully closed on demand. Fisher Controls Incorporated authorized the Control Specialists Company to perform maintenance on Fisher valves during the Wyle tests. Following completion of testing a Control Specitlists representative disassembled and inspected the Fisher PORV. Scratches were observed on the plug and cage guiding surfaces.
4-82
At EPRI request, each relief valve manufacturer 1 s representative made an engineering assessment of the potential effects of observed *damage on futur*e valve operation for all other PORVs tested. Prior to initiation of Wyle testing of the Fisher valve, Fisher Controls and Control Specialists took the position that no such assessment would be made for this valve and therrfore, none was made upon completion of testing. 4-85
* 4.9   FISHER CONTROLS RELIEF VALVE 4.9.1 "As Tested" Test Matrices and Valve Performance Data Tests performed on the Fisher Controls relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program.
.+:::> I Co CJ) EPRI/ MARSHALL PORV TEST DATA (3) TABLE 4. 9. I-la "AS TESTED" MARSHALL TEST MATRIX FOR THE FISHER CONTROLS RELIEF VALVE CONDITIONS VALVE INLET TEST TEST FLUllJ PRESS. NO. TYPE (PSIA) STEAM STEAM 2435 2 STEAM STEAi'! 2420 3 STEAM STEAM 2395 4 STEAM STEAM 2415 STEAM STEAM 2415 6 STEAM STEAM 2415 7 STEAM STEAM 2430 8 STEAM STEAM 2415 9 STEAM STEAM 2410 10 STEAM STEAM 2415 11 STEAM STEAM 2435 NOTES: (1) Maximum Quasi steady discharge pipe pressure.  
The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Fisher Controls relief valve tested at each of the test facilities.
(2) Not recorded.
Test                                 "As Tested" Test             Valve Performance Facility                                    Matrix Table                 Data Table Marshall                                    4.9.l-la                     4.9.l-lb Wyle (Phase III)                            4.9.l-2a                    4.9.l-2b 4.9.2 Principal    Observ~tions Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles. At the conclusion of these tests, the va l ve was d i s as s em bl e d and ga11 i ng was observed on the p l ug and c age mat i ng surfaces.
TEMP. (OF) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) (SAT.) AT VALVE OPENING TRANSIENT CONDITIONS IN ACCUMULATOR TEST VALVE INLET DURATION PRESS. WHEN FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN (PSIA) (OF) TO CLOSE VALVE PSIA) SAME AS VALVE INLET ' 88 2235 I I 39 2235 I 34 2250 48 2255 37 2255 72 2230 20 2265 24 2255 23 2255 22 2255 (2) 2275 MAXIMUM pl DISCHARG PIPE PRESS. (PSIA) 490 485 485 495 495 155 155 155 155 160 495 (3) Test results are for evaluation tests only. 7otal of 21 supplementary valve actuation cycles were performed under similar conditions . * 
In addition to the evaluation tests, three other sets of cycles were performed on the valve. The first two sets of cycles were performed on a set of cage and plug parts which did not represent the correct Fisher Controls design for the PORV application. During the first set of cycles, the valve always closed on demand to within 4% of the full closed position on each cycle. After the cycles were completed, the valve was disassembled and galling was observed on the plug and cage mating surfaces. The galling was more severe than the evaluation test cycle galling pattern. A second set of tests were then performed using the same internals after they had been refurbished. For those tests, the valve fully opened on demand and fully closed on demand for each of 14 cycles.
+::> I ():) ........
4-83
* EPRI I .MARSHALL PORV TEST DATA (3) TABLE 4.9. !-lb  
 
The evaluation tests were then performed on a set of cage and plug parts with correct clearances. These are the tests discussed in the first paragraph cif this section and they represent Fisher Controls PORVs sup-*
plied to PWR plants with the correct internals.
A fourth set of cycles were performed on a set of trim with the correct design clearances. The *valve fully opened on demand and fully closed on demand for each cycle. A galling pattern similar to that observed in the evaluation tests was observed. Again, it was less severe than the pattern observed when the valve did not fully close on demand Wyle Phase III During all ten (10) tests performed, the valve fully opened arid fully closed on demand.
Fisher Controls Incorporated authorized the Control Specialists Company to perform maintenance on Fisher valves during the Wyle tests. Following completion of testing a Control Specitlists representative disassembled and inspected the Fisher PORV. Scratches were observed on the plug and cage guiding surfaces.
At EPRI request, each relief valve manufacturer 1 s representative made an engineering assessment of the potential effects of observed *damage on futur*e valve operation for all other PORVs tested. Prior to initiation of Wyle testing of the Fisher valve, Fisher Controls and Control Specialists took the position that no such assessment would be made for this valve and therrfore, none was made upon completion of testing.
4-85
 
EPRI/   MARSHALL         PORV TEST DATA (3)
TABLE 4. 9. I- la "AS TESTED"     MARSHALL   TEST MATRIX FOR THE FISHER CONTROLS RELIEF VALVE CONDITIONS AT VALVE OPENING                                        TRANSIENT CONDITIONS TEST VALVE INLET                         IN ACCUMULATOR                    TEST DURATION VALVE INLET PRESS. WHEN MAXIMUM DISCHARG pl TEST         FLUllJ     PRESS.       TEMP.      FLUID        PRESS.        TEMP.        (SEC)
NO.         TYPE                                                                                                     SIGNAL GIVEN        PIPE PRESS.
(PSIA)      (OF)                    (PSIA)        (OF)                      TO CLOSE VALVE          (PSIA)
PSIA)
STEAM       STEAM         2435       (SAT.)        SAME AS VALVE INLET                      88            2235                490 2           STEAM       STEAi'!       2420       (SAT.)                  I' I                              39            2235                485 3           STEAM       STEAM         2395       (SAT.)                  I                              34            2250                485 4           STEAM       STEAM         2415       (SAT.)                                                  48            2255                495 STEAM       STEAM         2415       (SAT.)                                                  37            2255                495 6           STEAM       STEAM       2415       (SAT.)                                                  72            2230                155 7           STEAM       STEAM         2430       (SAT.)                                                  20            2265                155
.+:::>
8           STEAM       STEAM         2415       (SAT.)
I 24            2255                155 Co        9           STEAM       STEAM         2410       (SAT.)
CJ)                                                                                                                  23            2255                155 10           STEAM       STEAM         2415       (SAT.)                                                  22            2255                160 11           STEAM       STEAM         2435       (SAT.)                                                  (2)            2275                495 NOTES:
(1) Maximum Quasi steady discharge pipe pressure.
(2)   Not recorded.
(3) Test results are for evaluation tests only. 7otal of 21 supplementary valve actuation cycles were performed under similar conditions .
 
EPRI I .MARSHALL       PORV TEST DATA (3)
TABLE 4.9. !-lb


==SUMMARY==
==SUMMARY==
OF FISHER CONTROLS RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS .LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VALVE (1) VALVE INLET OUTLET FLOW VALVE INLET LEAKAGE TOTAL VALVE (2) TEST TEST OPENING TIME FLUID PRESS. TEMP. PRESS. RATE CLOS ING TIME MEDIA PRESS. TEMP. RATE so. TYPE (SEC) (PSIA) (OF) (PS!A) (LBM/HR) (SEC) (PS!A) (OF) (GPM) STEAM 12. 300 (4) STEAM 2235 (SAT.) 485 180,000 I .200 STEAM 2455 (SAT.) 0.243 A pre-operational leakage test showed a.a GPM leakage STEAM 13. 350 (4) * * * *
OF FISHER CONTROLS RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS                                     .LEAKAGE MEASUREMENTS               COMMENTS VALVE TOTAL VALVE (1)         VALVE INLET           OUTLET     FLOW   TOTAL VALVE (2)               VALVE INLET      LEAKAGE TEST       TEST     OPENING TIME   FLUID   PRESS. TEMP. PRESS. RATE     CLOS ING TIME     MEDIA   PRESS. TEMP. RATE so.       TYPE         (SEC)               (PSIA)     (OF)     (PS!A)   (LBM/HR)     (SEC)                 (PS!A)     (OF)     (GPM)
* 1.200 * *
A pre-operational leakage STEAM       12. 300 (4) STEAM     2235     (SAT.)       485     180,000     I .200         STEAM     2455       (SAT.)   0.243 test showed a.a GPM leakage STEAM       13. 350 (4)     *       *         *         *
* STEAM 16.200 (4) * * *
* 1.200           *         *
* 1.000 .. *
* STEAM       16.200 (4)     *       *         *
* 4 STEAM. 17.400 (4) * *
* 1.000           .         *
* 1.100 *
* 4       STEAM.       17.400 (4)               *         *
* STEAM 13.600 (4). * * !. 100 STEAM 2415 (SAT.) 0. 112 6 STEAM 2.650 STEAM 2230 (SAT.) 155 178,000 1.100 * " *
* 1.100             *
* STEAM 2.800 * *
* STEAM       13.600 (4).             *         *                             !. 100         STEAM   2415       (SAT.)   0. 112
* 1.000 * * *
+::>
* 8 STEAM 2.200 * * * *
6       STEAM         2.650       STEAM     2230     (SAT.)       155     178,000     1.100           *         "         *
* 0.950 * * *
* I
* 9 STEAM 2.100 * * * *
():)                STEAM         2.800         *                 *
* 0.950 * *
* 1.000           *         *         *
* IO STEAM 2.300 * * *
* 8       STEAM         2.200         *       *         *         *
* 0.800 * ..
* 0.950             *         *         *
* Il STEAM 3.300 * * *
* 9       STEAM         2.100         *       *         *         *
* 0.900 STEAM 2415 (SAT.) 0. 108 not applicable to this test NOTES: (I) Opening time measured from time of energizing solenoid unti'l valve reaches full open. position. . (2) Closing time measured from time of de-energizing solenoid until valve reaches full .closed posltfon. . ; , (3) Test results are for evaluation tests only. Total of 21 supplementary valve*actuat1on cycles were perfonned under similar cond1t1ons.  
* 0.950             *                   *
* IO       STEAM         2.300                 *         *         *
* 0.800             *                   .
* Il       STEAM         3.300                 *         *         *
* 0.900           STEAM   2415       (SAT.) 0. 108 not applicable to this test NOTES:
(I) Opening time measured from time of energizing solenoid unti'l valve reaches full open. position.                                       .
(2) Closing time measured from time of de-energizing solenoid until valve reaches full .closed posltfon.                   .           ; ,
(3) Test results are for evaluation tests only. Total of 21 supplementary valve*actuat1on cycles were perfonned under similar cond1t1ons.
(4) The valve opened slowly because the Fisher Controls representative had increased the spring force to insure minimum seat leakage.
(4) The valve opened slowly because the Fisher Controls representative had increased the spring force to insure minimum seat leakage.
EPRI/WYLE Phase III PORV TEST DATA TABLE 4.9.l-2a "AS TESTED" WYLE PHASE II I TEST Ml\ TRIX FOR THE FISHER CONTROLS RELIEF VALVE INITIAL CONDITIONS(l}
EPRI/WYLE Phase III PORV TEST DATA TABLE 4.9.l-2a "AS TESTED" WYLE PHASE II I TEST Ml\ TRIX FOR THE FISHER CONTROLS RELIEF VALVE INITIAL CONDITIONS(l}
TRANSIENT CONDITIONS Valve Inlet At _/'id lve Inlet In Accumulator Pressure Maximum Maximum Maximum at Discharge Bending Valve Test Closure Pipe Moment Acceleration Temp Press. Temp Press. Duration Signal Press.(2)
TRANSIENT CONDITIONS Valve At _/'id lve Inlet                                                        Inlet In Accumulator                     Pressure Maximum       Maximum Maximum at         Discharge   Bending Valve Temp                                                    Test       Closure Pipe           Moment     Acceleration Test No.                                                        Press.                   Temp     Press. Duration Signal Test Type         Fluid       (OF)         (psi a)   Fluid       (OF)                                     Press.(2)  Induced(3}Induced (psi a) (seconds) (psi a}     (psi a)     (in-lb)   (g's) 87-FS-lS           Steam             Steam         683       2, 760     Steam         678     2,760       6       2,395     370         N/A         2.1 88-FS-2S             Steam             Steam         683       2, 760     Steam         678     2,760       6       2,400     330 (Pre load)                                                                                                                38,300     2.0 89-FS-3W             Water
Induced(3}Induced Test No. Test Type Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a} (psi a) (in-lb) (g's) 87-FS-lS Steam Steam 683 2, 760 Steam 678 2,760 6 2,395 370 N/A 2.1 88-FS-2S Steam Steam 683 2, 760 Steam 678 2,760 6 2,400 330 38,300 2.0 (Pre load) 89-FS-3W Water
* Water         452
* Water 452 2,664 Water 454 2,664 5 2,430 350 N/A 2.1 -+::> I o:i 90-FS-411 Water Water 447 685 Water 456 685 10 666 138 N/A 1. 7 co 91-FS-5W Water Water 101 684 Water 94 684 10 612 N/A 1.8 92-FS-611 Water Water 264 2,668 Water 257 2,668 4 2,390 410 N/A 3.2 93-FS-7W Water Water 648 2,536 Water 650 2,536 6 2,395 400 N/A 2.5 94-FS-8S/W Trans it ion Steam 669 2,530 Water 653 2,530 6 2,380 372 N/A 7.4 95-FS,-9W/W Water Water 203 2,704 Water 655 2. 704 15 2,420 450 N/A 19.5 Seal Simulation 96-FS-lOW/W Water Water 123 2,700 Water 657 2, 700 15 2,400 450 N/A 11.2 Seal Simulation ( 1) PORV Actuation Ullage pressure for all tests wa5 69 (!) 1 psig. ( 2) No back pressure orifice was used in the Muesco PORV ( 3) Value shown corresponds L, the 111aximum moment induced while valve 1s in the opening/closing process .
-+::>
* EPRI/WYLE Ph as ORV TEST DATA TABLE 4.9.l-2b  
2,664       Water         454     2,664       5     2,430 I
350         N/A         2.1 o:i co      90-FS-411           Water             Water         447         685       Water         456       685     10         666     138         N/A         1. 7 91-FS-5W             Water             Water         101           684       Water         94       684     10         612                 N/A         1.8 92-FS-611             Water           Water         264       2,668       Water       257     2,668       4       2,390     410         N/A         3.2 93-FS-7W             Water           Water         648       2,536       Water       650     2,536       6     2,395     400         N/A       2.5 94-FS-8S/W           Trans it ion     Steam         669       2,530       Water       653     2,530       6     2,380     372         N/A         7.4 95-FS,-9W/W           Water             Water         203       2,704       Water       655     2. 704     15 Seal                                                                                              2,420     450         N/A       19.5 Simulation 96-FS-lOW/W           Water           Water         123         2,700       Water       657     2, 700     15 Seal                                                                                              2,400     450         N/A       11.2 Simulation
( 1) G~ PORV Actuation Ullage pressure for all tests wa5 69 2                                                            (!) 1
( 2) No back pressure orifice was used in the Muesco PORV t~sting. psig.
( 3) Value shown corresponds L, the 111aximum moment induced while valve 1s in the opening/closing process .
 
EPRI/WYLE Ph as             ORV TEST DATA TABLE 4.9.l-2b


==SUMMARY==
==SUMMARY==
*OF FISHER VALVE PERFORMANCE Test 87-88-89-90-91-92-93-94-95-96-Number FS-lS FS-2S FS-3W FS-4W FS-5W FS-6W FS-7W FS-85/W FS-9\.//W FS-lOW/W Pre-Jest Leakage(!)
*OF FISHER VALVE PERFORMANCE Test                           87-       88-       89-         90-         91-         92-       93-       94-Number                                                                                                                            95-           96-FS-lS     FS-2S     FS-3W       FS-4W       FS-5W       FS-6W     FS-7W     FS-85/W     FS-9\.//W     FS-lOW/W Pre-Jest Leakage(!)
Media Steam Steam Water Water Water Water Water Water Water Water Pressure (psia) 2,780 2, 785 2,680 705 710 2, 715 2;535 2,575 2, 765 2, 715 Temp (OF) 682 682 455 431 96 262 649 643 191 112 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) 0.34 0.38 0.64 1.05 2.32 0. 70 0.54 0.41 0.65 0.65 Main Disc Opening Time (sec) 0.24 0.27 0.53 0.82 2.10 0.58 0.42 0.29 0.54 0.54 Valve Flow Rate (lb/fir) 216,000 216,000 756,000 284,400 460,800 853,200 410,400 385,200 432,000 432,000 Corresponding Valve .j:::> Inlet Press (psia) 2,555 2,559 2,460 670 625 2,430 2,426 2,400 2,493 2,490 I OJ Corresponding Valve <.o Inlet Temp (OF) 674 674 453 453 102 268 649 656 648 650 Corresponding Valve Outlet Press (psia) 295 295 308 138 340 380 372 410 410 Corresponding Valve Outlet Temp (OF) 390 385 275 350 91 230 435 434 445 445 Corresponding Test Time Relative to Open Command (sec) 2.5 2.9 . 1.2 4.3 4.0 1. 7 3.1 4.2 8.4 8.4 Inlet Pressure at Beginning of Valve Closure (psia) 2,380 2,390 2,420 665 615 2,390 2,395 2,390 2,420 2,410 Total Valve Closure Time (sec) 0.33 0.33 0.38 0.25 0.27 0.36 0.35 0.35 0.36 0.36 Main Disc Closing Time (sec) 0.17 0.18 0.22 0.13 0.15 0.22 0.17 0.16 0.18 0.18 Post-Test Leakage( I). Media Steam Steam Water Water Water Water Water Water Water Water Pressure (psia) 2,780 2, 765 2, 715 745 670 2,700 2,605 2,460 2,620 2,700 Temp (OF) 683 677 443 435 101 250 637 670 468 457 leak Rate (GPM} 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0. 001.3 0.0013 0.0013 0.0013
Media                       Steam       Steam     Water       Water       Water       Water       Water     Water     Water         Water Pressure (psia)             2,780     2, 785     2,680           705         710       2, 715     2;535     2,575       2, 765       2, 715 Temp (OF)                       682       682       455         431           96         262       649       643         191 Leak Rate (GPM)                                                                                                                             112 0.0013     0.0013     0.0013       0.0013       0.0013       0.0013     0.0013     0.0013     0.0013       0.0013 Transient Performance Total Valve Opening Time (sec)             0.34       0.38       0.64         1.05         2.32         0. 70     0.54       0.41       0.65         0.65 Main Disc Opening Time (sec)               0.24       0.27     0.53         0.82         2.10         0.58     0.42       0.29       0.54         0.54 Valve Flow Rate (lb/fir) 216,000   216,000   756,000     284,400     460,800     853,200   410,400   385,200     432,000       432,000 Corresponding Valve
' I 1: ' TABLE 4.9.l-2b (Cont'd) (1) Recorded leakages of 0.0013 indicates values of less than or equal to 0.0013. 4,...90 *
.j:::>
* 4.10 GARRETT RELIEF VALVE *
I                Inlet Press (psia)   2,555     2,559     2,460           670 OJ                                                                                          625       2,430     2,426     2,400       2,493         2,490
* 4.10.1 "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Garrett relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Garrett relief valve tested at each of the test facilities.
<.o           Corresponding Valve Inlet Temp (OF)           674       674       453         453         102         268       649       656         648           650 Corresponding Valve Outlet Press (psia)       295       295       308         138                       340       380       372         410           410 Corresponding Valve Outlet Temp (OF)         390         385       275         350           91         230       435         434         445         445 Corresponding Test Time Relative to Open Command (sec)         2.5       2.9     . 1.2         4.3         4.0         1. 7       3.1       4.2         8.4           8.4 Inlet Pressure at Beginning of Valve Closure (psia)     2,380     2,390     2,420           665         615       2,390     2,395     2,390       2,420         2,410 Total Valve Closure Time (sec)             0.33       0.33       0.38         0.25         0.27         0.36       0.35       0.35       0.36         0.36 Main Disc Closing Time (sec)             0.17       0.18       0.22         0.13         0.15         0.22       0.17       0.16       0.18         0.18 Post-Test Leakage( I).
Test Facility Marshall Wyle (Phase III) t .10.2 Principal Observations Marshall Steam Station "As Tested" Test Matrix Table 4.10.1-la 4.10.l-2a Valve Performance Data Table 4.10.1-lb 4.10.l-2b The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles. Additional cycles were performed on the valve. Following 46 of these cycles, body to bonnet gasket leakage developed.
Media                       Steam     Steam     Water       Water       Water       Water     Water     Water       Water Pressure (psia)                                                                                                                         Water 2,780     2, 765     2, 715         745         670       2,700 Temp (OF)                                                                                          2,605     2,460       2,620         2,700 683       677       443         435         101         250       637 leak Rate (GPM}                                                                                                   670        468          457 0.0013     0.0013     0.0013       0.0013       0.0013       0.0013     0. 001.3   0.0013     0.0013       0.0013
In all cycles, the valve fully closed on demand. Disassembly showed wash-out of the cage to body gaskd. As a result of the test observations, Garrett incorporated design modifications into the test valve for Wyle Phase III tests and into valves being supplied to PWR plants. Wyle Phase III The valve fully opened and fully closed on demand during all ten (10) tests performed.
 
Upon completion of testing, the valve was disassembled and inspected by the Garrett Corporation representative.
(1)
observed which would affect future operation.
TABLE     4.9.l-2b (Cont'd)
4-91 No damage was 
Recorded leakages of 0.0013 indicates values of less than or equal 0.0013.
+:> I l.O N "AS TESTED" MARSHALL CONDITIONS VALVE INLET TEST TEST FLUID PRESS. TEMP. NO. TYPE (PSIA) (OF) STFAM STEAM 2435 (SAT.) 2 STEAM STEAM 2435 (SAT.) STEAM STEAM 2415 (SAT.) 4 STEAM STEAM 2415 (SAT.) STEAM STEAM 2425 (SAT.) 6 STEAM STEAM 2450 (SAT.)
to I '
STEAM 2465 (SAT.) 8 STEAM STEAM (SAT.) STEAM STEAM 2445 (SAT.) 10 STEAM STEAM 2435 (SAT.) 11 STEAM STEAM 2455 (SAT.) NOTES: (1) Maximum Quasi steady discharge pipe pressure.  
1:
(2) Not recorded.
4,...90
AT EPRI/ MARSHALL PORV TEST DATA (3) TABLE 4.10.1-la TEST MATRIX FOR THE GARRETT RELIEF VALVE VALVE OPENING TRANSIENT CONDITIONS IN ACCUMULATOR TEST VALVE INLET MAXIMUM pl PRESS. WHEN OISCHARG FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS. (PSIA) (OF) TO CLOSE VALVE (PSIA) PS!A) SAME AS VALVE INLET 79 1995 815 23 2035 820 25 2015 815 28 2030 815 30 2050 825 44 2015 335 15 2075 355 12 2055 340 16 2055 345 17 2.055 345 (2) 2075 815 (3) Test results are for evaluation tests only. Total of 68 supplementary valve actuation cycles were performed under similar.conditions.  
* 4.10 GARRETT RELIEF VALVE 4.10.1 "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Garrett relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program.
*
The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Garrett relief valve tested at each of the test facilities.
* I l.O w *
Test                     "As Tested" Test               Valve Performance Facility                    Matrix Table                   Data Table Marshall                    4.10.1-la                     4.10.1-lb Wyle (Phase III)            4.10.l-2a                      4.10.l-2b t .10.2 Principal Observations
* EPRI / MARSHALL PORV TEST DATA (4) TABLE 4.10.1-lb  
* Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles.
Additional cycles were performed on the valve. Following 46 of these cycles, body to bonnet gasket leakage developed. In all cycles, the valve fully closed on demand. Disassembly showed wash-out of the cage to body gaskd. As a result of the test observations, Garrett incorporated design modifications into the test valve for Wyle Phase III tests and into valves being supplied to PWR plants.
Wyle Phase III The valve fully opened and fully closed on demand during all ten (10) tests performed. Upon completion of testing, the valve was disassembled and inspected by the Garrett Corporation representative.         No damage was
* observed which would affect future operation.
4-91
 
EPRI/      MARSHALL      PORV TEST DATA (3)
TABLE 4.10.1-la "AS TESTED"     MARSHALL   TEST MATRIX FOR THE      GARRETT RELIEF VALVE CONDITIONS AT VALVE OPENING                                          TRANSIENT CONDITIONS TEST          TEST VALVE INLET                           IN ACCUMULATOR                  TEST OUllATIO~
VALVE INLET PRESS. WHEN MAXIMUM OISCHARG pl FLUID      PRESS.        TEMP.      FLUID         PRESS.       TEMP.         (SEC)        SIGNAL GIVEN NO.         TYPE                   (PSIA)       (OF)                                                                                 PIPE PRESS.
(PSIA)      (OF)                        TO CLOSE VALVE        (PSIA)
PS!A)
STFAM       STEAM       2435       (SAT.)         SAME AS VALVE INLET                    79              1995            815 2           STEAM       STEAM       2435       (SAT.)                                                   23              2035            820 STEAM       STEAM       2415       (SAT.)                                                   25              2015            815 4           STEAM       STEAM       2415       (SAT.)                                                   28              2030            815 STEAM       STEAM       2425       (SAT.)
+:>                                                                                                                30              2050            825 I
l.O    6           STEAM       STEAM       2450       (SAT.)
N                                                                                                                44              2015            335 STEAi~      STEAM       2465       (SAT.)                                                   15              2075            355 8           STEAM       STEAM       ~455      (SAT.)                                                   12              2055            340 STEAM       STEAM       2445       (SAT.)                                                   16              2055            345 10           STEAM       STEAM       2435       (SAT.)                                                   17              2.055            345 11           STEAM       STEAM       2455       (SAT.)                                                   (2)              2075            815 NOTES:
(1)   Maximum Quasi steady discharge pipe pressure.
(2)   Not recorded.
(3) Test results are for evaluation tests only. Total of 68 supplementary valve actuation cycles were performed under similar.conditions.
* EPRI /   MARSHALL     PORV TEST DATA (4)
TABLE 4.10.1-lb


==SUMMARY==
==SUMMARY==
OF GARRETT RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONOITIONS LEAKAGE MEASUREMENTS TOTAL VALVE (1) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM) STEAM 0.195 STEAM 19g5 (SAT.) 800 293,000 2.350 STEAM 2445 (SAT.) 0.006 2 STEAM 0.205 * * * ..
OF GARRETT RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONOITIONS                                         LEAKAGE MEASUREMENTS                   COMMENTS
* 1.990 * *
                                                                      '!.~~VE TOTAL VALVE (1)         VALVE INLET         OUTLET     FLOW   TOTAL VALVE (2)                     VALVE INLET     LEAKAGE TEST       TEST     OPENING TIME     FLUID   PRESS. TEMP. PRESS.     RATE     CLOSING TIME         MEDIA       PRESS. TEMP. RATE NO.       TYPE           (SEC)               (PSIA)     (OF)   (PSIA)   (LBM/HR)       (SEC)                         (PSIA)   (OF)     (GPM)
* 3 STEAM 0. 195 .. * * *
A pre-operational leakage STEAM       0.195       STEAM     19g5 2        STEAM      0.205          *          *
* l. 760 .. * *
(SAT.)
* 4 STEAM 0.215 * *
800     293,000 2.350 1.990 STEAM 2445       (SAT.)
* l.895 * * *
0.006 test showed 0.0 GPM leakage 3        STEAM       0. 195          .         *       *       *
* 5 STEAM 0.205 .. * *
* l. 760               .           *         *
* 2.015 STEAM 2615 (SAT.) 0.008 6. STEAM 0.205 STEAM 2015 (SAT.) 335 292,000 1.750 * * *
* 4       STEAM       0.215                                                                                 *           *
* 7 STEAM 0.215 *
                                                        *                  *
* l.600 .. * * .. 8 STEAM 0.210 * .. * *
* l.895                                         *
* 1.630 * * *
* 5       STEAM       0.205           .         *         *
* 9 STEAM 0.220 * * *
* 2.015             STEAM         2615     (SAT.)   0.008
* 1. 730 * * *
: 6.     STEAM       0.205       STEAM
* 10 STEAM 0.215 * * * * .. 1. 700 * * *
* 2015     (SAT.)     335   292,000     1.750                             *         *
* 11 STEAM (3) * * * * * (3) STEAM 2495 (SAT.) 0.010
* 7       STEAM       0.215                             *
* not applicable to this test NOTES: ( l) (2) ( 3) (4) (5) Opening time measured from time of energizing solenoid until valve reaches full open position.
* l.600                 .           *         *       .
Closing time measured from time of de-energizing solenoid until valve reaches full closed position.
8       STEAM       0.210         *         .       *         *
Not recorded The results are for evaluation tests only. Total of 68 supplementary valve cycles The leakage test was conducted after 66 supplementary tests were performed under s 1 m 1 ar con
* 1.630                 *           *         *
* similar conditions.
* 9       STEAM       0.220                     *       *         *
COMMENTS A pre-operational leakage test showed 0.0 GPM leakage (5) 
* 1. 730               *           *         *        *
+::> I l.O +::> At Valve Temp Test No. Test Type Flu.id (OF) 97-GA-lS.
~
Steam Steam* 683 98-GA-2S Stearn Steam 683 (Pre load) 99-GA-3W Water Water 438 100-GA-4W Water Water 447 101-GA-5W .Water Water 104 102-GA-6W Water Water 249 103-GA-7W Water Water 648 104-GA-8S/W Transition Steam 682 105-GA-9W/W Water Water 293 Seal Simulation 106-GA-lOW/W Water Water 130 Seal Simulation Notes: EPRI/WYLE Phase III PORV TEST DATA TABLE 4.10.l-2a "AS TESTED" WYLE PHASE I!! TEST MATRIX FOR THE GARRETT RELIEF VALVE INITIAL CONDITIONS Inlet In Accumulator Test Press. Temp Press. Duration (psia) Fluid (OF) (psi a) (seconds) 2, 760 Steam 682 2,760 4 2, 760 Steam 679 2, 760 4 2, 760 Water 461 2,760 4 683 Water 460 683 12 686 Water 94 686 11 2,640 Water 258 2,640 3 2,758 Water 653 2,758 3 2, 760 Water 653 2, 760 6 2, 755 Water 651 2,755 16 2, 760 Water 650 2, 760 16 TRANSIENT CONDITIONS Valve Inlet Pressure Maximum Maximum. Maximum at Discharge Bending Valve Closure Pipe Moment Acceleration Signal Press.(1) lnduced(3)Induced (psi a) (psia)(2)  
I l.O 10       STEAM       0.215         *         *       *         *         .       1. 700               *           *         *
*(in-lb) (g's) 2,346 580 N/A 12.2 2,275 623 33,200 8.7 2,030 485 N/A 7.2 610 255 N/A 12.3 495 25 N/A 12.2 1,880 92 N/A 12.6 780 N/A 6.8 2,420 800 N/A 5.2 2,225 875 N/A 5.8 2,210 860. N/A 8.7 (1) Values shown were measured 50" downstream of valve exit (same location as for all other PORV's tested). For this valve an discharge pipe pressure sensor (PS-6) was mounted irnnediately downstream of the valve, (see section 5.0 for plot of observed pressure).
* w      11       STEAM         (3)           *         *       *         *         *         (3)             STEAM         2495     (SAT.)   0.010 (5)
(2) No back orifice was used in the Garrett PORV testing . . (3) Value shown corresponds to maximum moment applied whfle. valve was in the opening/closing process. * * * -----
* not applicable to this test NOTES:
----------------
( l) Opening time measured from time of energizing solenoid until valve reaches full open position.
-----------
(2)  Closing time measured from time of de-energizing solenoid until valve reaches full closed position.
--------------
( 3) Not recorded (4) The results are for evaluation tests only. Total of 68 supplementary valve cycles "".er.~  perfo';l'j~~ounnsder similar conditions.
-----*------------------
(5) The leakage test was conducted after 66 supplementary tests were performed under s m ar con
*
* 1 1
* EPRI/WYLE Phase III PORV TEST DATA TABLE 4.10.l-2b SUMMllRY OF-GARRETT RELIEF VALVE PERFORMANCE
 
'* . *rest 97-98-99-100-101-102-103-104-105-106-Number GA-15 GA-2S GA-3W GA-4W GA-5W !JA-6W GA-7W GA-8S/W GA-9W/W GA-lOW/W Pre-Test Leakage (1) Media Steam Steam
EPRI/WYLE Phase III PORV TEST DATA TABLE 4.10.l-2a "AS TESTED" WYLE PHASE I!! TEST MATRIX FOR THE GARRETT RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS Valve At Valve Inlet                                                        Inlet In Accumulator                    Pressure Maximum Maximum. Maximum at          Discharge Bending Valve Temp                                                   Test      Closure Pipe          Moment    Acceleration Test No.                                                       Press.                  Temp      Press. Duration Signal Test Type         Flu.id       (OF)       (psia)     Fluid        (OF)                                      Press.(1) lnduced(3)Induced (psi a)  (seconds) (psi a)    (psia)(2) *(in-lb)    (g's) 97-GA-lS.            Steam              Steam*        683      2, 760    Steam          682    2,760        4      2,346      580        N/A      12.2 98-GA-2S            Stearn            Steam        683      2, 760    Steam        679      2, 760        4      2,275      623        33,200 (Pre load)                                                                                                                          8.7 99-GA-3W            Water              Water        438      2, 760
* Water Water Water Water Water Water Water Water Pressure (psi a)* 2,820 2,665 2,770 775 690 2,610 2,820 2,795 2,815 2,785 Temp (OF) 676 675 414 395 98 222 611 599 282 122 Leak Rate (GPM) 0.0013 0.0013 0.0021 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) 1.24 0.59 0.40 0.59 0.68 0.38 0.37 0.54 0.38 0.43 Main Disc Opening Time (sec) 0.13 0.13 0.26 0.59 0.25 0.22 0.29 0.26 0.25 Valve Flow Rate (lb/Hr) 378,000 372,600 (2) 489,600 900,000 1,681,200 813,600 792,000 784,800 792,000 Corresp.onding Valve I '&deg; Inlet Press (psia) 2,415 2,386 (2) 618 510 1,900 2,486 2,460 2,390 . 2,360* U'l Corresponding Valve Inlet Temp (OF) 674 669 (2) 461 106 266 648 650 646 642 Corresponding Valve Outlet Press (psia) 573 562 (2) 255 14.7 92 770 765 750 745 Corresponding Valve Outlet Temp (OF) 350 390 (2) 400 96 228 330 497 508 505 Corresponding Test Time Relative to Open Command (sec) 2.1 1.8 (2) 4.5 4.0 1.6 L2 2.9 5.4 6.6 Inlet Pressure at Beginning of Valve Closure (psia) 2,310 2,240 2,030 610 490 1,860 2,1180 2,410 2,220 2,210 Total Valve Closure Time (sec) 0.60 0.58 0.78 1.42 1.04. 0.75 0.85 1.18 0.92 0.90 Main Disc Closing Time (sec) 0.25 0.24 0.47 1.09 0.81 0.48 0.56 0.52 0.58 o .. 61 Post-Test Leakage (l) Media Steam Steam Water . Water Water Water Water Water Water Water Press (psi a) 2,825 2,755 2,850 805 685 2,560 2,695 2,725 2, 775 2,780 Temp (OF) 681 681 405 399 97 221 583 592 470 415 (GPM) 0.0011 o.orn 1 0.l'JQ] 3 0.1')013 O.OOlJ 0:0011 0.0011 o.nn1J 0.0011 0.0013 TABLE 4.l0.1.-2b (Cont'd).
      +::>                                                                                  Water         461      2,760        4      2,030      485        N/A I                                                                                                                                                                  7.2 l.O
N ates: (1) Recorded leakages of .0013 .GP M indicates measured values less than or equal to .0013 GP M .. (2) Venturi delta pressure sensor over-ranged 4-96 * '*. * .. * *
      +::>      100-GA-4W            Water              Water         447        683      Water         460        683      12        610      255        N/A        12.3 101-GA-5W          .Water              Water        104        686    Water            94      686      11        495    25          N/A        12.2 102-GA-6W            Water              Water          249      2,640      Water          258    2,640        3      1,880      92          N/A      12.6 103-GA-7W            Water              Water        648      2,758      Water        653      2,758        3      2,4~0      780        N/A        6.8 104-GA-8S/W          Transition        Steam        682      2, 760      Water         653      2, 760        6      2,420      800        N/A          5.2 105-GA-9W/W          Water              Water         293      2, 755     Water         651     2,755       16       2,225      875        N/A Seal                                                                                                                                5.8 Simulation 106-GA-lOW/W        Water              Water        130      2, 760      Water        650      2, 760     16       2,210    860.       N/A Seal                                                                                                                                8.7 Simulation Notes:
* 1. 2. 3. 4. 5.
(1) Values shown were measured 50" downstream of valve exit (same location as for all other PORV's tested).
* Section 5 REFERENCES "Valve Selection/Justification Report," Interim Report, December 1981, EPRI Valve Test Program staff, et al. "Test Condition Justification Report," Interim Report, April 1982, EPRI Valve Test Program Staff, et al. Valve Inlet Fluid Conditions for Pressurizer Safety and Relief Valves in B&W 177FA and 205FA Plants, March 1982. Valve Inlet Fluid Condit ions for Pressurizer Safety and Relief Valves in Combustion Engineering Plants, March 1982. Valve Inlet Fluid Conditions for pressurizer Safety and Relief Valves in Westinghouse Plants, January 1982 . 5-1
pressure sensor (PS-6) was mounted irnnediately downstream of the valve,                                                  For this valve an  addition~l  discharge pipe (see section 5.0 for plot of observed pressure).
*
(2) No back pressur~ orifice was used in the Garrett PORV testing .
* APPENDIX A DEFINITION OF KEY TERMS AND PARAMETERS F6R SAFETY VALVES . The definitions are provided for each of the Safety Valve tables presented in section 3.0. The following definitions apply to Tables 3.1.1.a, 3.2. l .a, 3.3.1.a, 3.4.1.a, 3.5.1.a, 3.6.1.a and 3.7.1.a: KEY TERMS AND PARAMETERS Valve Description Inlet Piping Configuration DEFINITION The valve description is a list of design and plate information for the test valve. Each element of the piping between the accumulator tank (tank 1) and the valve inlet is listed along with its length and inside diameter.
              . (3)  Value shown corresponds to maximum moment applied whfle. valve was in the opening/closing process.
The elements are listed sequentially from the tank (nozzle) to the valve inlet (inlet flange). Letter designations have been assigned to each configuration and that letter is referenced in this table . A-1 The following definitions apply to Tables 3.1.1.b, 3.2.l.b, 3.3.1.b, 3.4.1.b, 3.5.1.b, 3.6.1.b and 3.7.1.b: KEY TERMS AND PARAMETERS Test No. T1 *st Type DEFINITION There is a unique identification number for each test. These numbers were assigned in ascending order to the tests when they were conducted; however, the numbers are not continuous.
----- ----*--~
For example, tests on one of the valves were numbered 403, 406, 408 .... Every valve test performed is in the tables. For some of the tests, the valves were cycled opened and closed more than once. The test procedure ically called for continued system pressurization to obtain three-to-five minutes of test time for each test. If the .valve closed within seconds after opening, system repressurization .was permitted to continue and the valve was cycled open and closed
* EPRI/WYLE Phase III PORV TEST DATA TABLE 4.10.l-2b SUMMllRY OF-GARRETT RELIEF VALVE PERFORMANCE
* through multiple cycles until the planned test tion was completed.
      *rest                                97-      98-      99-          100-        101-      102-      103-      104-      105-      106-Number                                GA-15    GA-2S      GA-3W        GA-4W        GA-5W    !JA-6W      GA-7W    GA-8S/W    GA-9W/W    GA-lOW/W Pre-Test Leakage (1)
In the case of transition tests, system repressurization was again permitted and the valve cycled as often as required in order to obtain the transition.
Media                            Steam    Steam
For the tests which resulted in multiple cyqles of the test valve, all of the data for the first cycle has been listed in the tables. For the subsequent cycles, the data has been provided for the key valve test parameters related to the fluid type, valve opening, peak and closing pressures, back pressures and valve stability.
* Water        Water        Water    Water      Water    Water      Water      Water Pressure (psi a)*                2,820    2,665      2,770            775        690      2,610 2,820        2,795      2,815      2,785 Temp (OF)                          676      675        414          395          98        222      611      599        282        122 Leak Rate (GPM)                0.0013    0.0013    0.0021        0.0013      0.0013      0.0013 0.0013    0.0013    0.0013    0.0013 Transient Performance Total Valve Opening Time (sec)                  1.24    0.59      0.40        0.59        0.68        0.38    0.37      0.54      0.38      0.43 Main Disc Opening Time (sec)                  0.13      0.13      0.26        0~51        0.59        0.25    0.22      0.29      0.26      0.25 Valve Flow Rate (lb/Hr)      378,000  372,600        (2)     489,600      900,000    1,681,200 813,600    792,000    784,800    792,000
The first cycle of the multiple cycles has been designated as cycle 11 a 11 and the remaining cycles have been designated as 11 b, c, d .... 11* The following types of tests were performed:
~
Steam -the fluid at the valve inlet and in the accumulator tank (tank 1) at test initiation and throughout the test was steam. L.S. -these tests were loop seal tests. Just prior to test initiation, the fluid at the valve inlet was subcooled water and the fluid in the accumulator was steam. Once the loop seal water was discharged, the test fluiu was steam. Trans. -these tests were transition tests. Prior to test initiation, the fluid at the valve inlet was steam and the fluid in the upper and lower portions of the accumulator tank were steam and saturated water, respectively.
I        Corresp.onding Valve
The valve opened on steam and closed on saturated water during the transition test . A-2 * * * 
'&deg; U'l              Inlet Press (psia)      2,415    2,386        (2)          618          510      1,900  2,486    2,460      2,390    . 2,360*
-, .<<l' 1',
Corresponding Valve Inlet Temp (OF)             674      669      (2)          461        106          266      648      650        646        642 Corresponding Valve Outlet Press (psia)          573      562      (2)           255        14.7            92    770      765        750        745 Corresponding Valve Outlet Temp (OF)              350      390      (2)          400          96        228      330      497        508        505 Corresponding Test Time Relative to Open Command (sec)             2.1      1.8      (2)            4.5        4.0         1.6      L2        2.9        5.4        6.6 Inlet Pressure at Beginning of Valve Closure (psia)   2,310    2,240    2,030            610        490        1,860  2,1180    2,410      2,220      2,210 Total Valve Closure Time (sec)                  0.60    0.58      0.78        1.42        1.04.        0.75    0.85      1.18      0.92      0.90 Main Disc Closing Time (sec)                 0.25    0.24      0.47        1.09        0.81        0.48    0.56      0.52      0.58      o.. 61 Post-Test Leakage (l)
* Ring Settings TiTTue disc ring is not an adjusting ring L.S. Trans. these tests were loop seal transition tests. The test was the same as a transition test except that the fluid immediately upstream of the safety valve was subcooled water. Water -the fluid at the valve inlet and in the accumulator tank at test initiation and throughout the test was approximately saturated water, 550&deg;F water or 400&deg;F water. The water tests progressed from ted water to the 55QOF water test and finally the 400&deg;F water test. Target Rock test included cold loop seals. Valve ring positions are listed for the safety valve adjusting rings. Descriptions of the reference tion for each of the safety valve manufacturer's valves tested are as follows: Crosby Valves have two adjusting rings, an upper or guide ring and a lower or nozzle ring. Positions in the table are given in notches relative to the level position.
Media                          Steam    Steam    Water        . Water      Water      Water      Water    Water      Water      Water Press (psi a)                   2,825    2,755      2,850            805        685      2,560    2,695    2,725      2, 775    2,780 Temp (OF)                           681      681        405          399          97        221      583      592        470        415 i_,,~~ R~tP  (GPM)             0.0011    o.orn 1  0.l'JQ] 3    0.1')013    O.OOlJ      0:0011  0.0011  o.nn1J      0.0011    0.0013
 
Nates:
TABLE    4.l0.1.-2b  (Cont'd).
(1) Recorded leakages of .0013 .GP M indicates measured values less than or equal to .0013 GP M..
(2) Venturi delta pressure sensor over-ranged 4-96                                          *
* 1.
Section 5 REFERENCES "Valve Selection/Justification Report," Interim Report, December 1981, EPRI Valve Test Program staff, et al.
: 2. "Test Condition Justification Report," Interim Report, April 1982, EPRI Valve Test Program Staff, et al.
: 3. Valve Inlet Fluid Conditions for Pressurizer Safety and Relief Valves in B&W 177FA and 205FA Plants, March 1982.
: 4. Valve Inlet Fluid Condit ions for Pressurizer Safety and Relief Valves in Combustion Engineering Plants, March 1982.
: 5. Valve Inlet Fluid Conditions for pressurizer Safety and Relief Valves in Westinghouse Plants, January 1982 .
* 5-1
* APPENDIX A DEFINITION OF KEY TERMS AND PARAMETERS F6R SAFETY VALVES .
The definitions are provided for each of the Safety Valve tables presented in section 3.0.
The following definitions apply to Tables 3.1.1.a, 3.2. l .a, 3.3.1.a, 3.4.1.a, 3.5.1.a, 3.6.1.a and 3.7.1.a:
KEY TERMS AND PARAMETERS                            DEFINITION Valve Description              The valve description is a list of design and name-plate information for the test valve.
Inlet Piping                    Each element of the piping between the accumulator Configuration                  tank (tank 1) and the valve inlet is listed along with its length and inside diameter. The elements are listed sequentially from the tank (nozzle) to the valve inlet (inlet flange). Letter designations have been assigned to each configuration and that letter is referenced in this table .
* A-1
 
The following definitions apply to Tables 3.1.1.b, 3.2.l.b, 3.3.1.b, 3.4.1.b, 3.5.1.b, 3.6.1.b and 3.7.1.b:
KEY TERMS AND PARAMETERS Test No.
DEFINITION There is a unique identification number for each test.
These numbers were assigned in ascending order to the tests when they were conducted; however, the numbers are not continuous. For example, tests on one of the valves were numbered 403, 406, 408 .... Every valve test performed is li~ted in the tables.
For some of the tests, the valves were cycled opened and closed more than once. The test procedure typ-ically called for continued system pressurization to obtain three-to-five minutes of test time for each test. If the .valve closed within seconds after opening, system repressurization .was permitted to continue and the valve was cycled open and closed
* through multiple cycles until the planned test dura-tion was completed. In the case of transition tests, system repressurization was again permitted and the valve cycled as often as required in order to obtain the stea~-to-water transition. For the tests which resulted in multiple cyqles of the test valve, all of the data for the first cycle has been listed in the tables. For the subsequent cycles, the data has been provided for the key valve test parameters related to the fluid type, valve opening, peak and closing pressures, back pressures and valve stability. The first cycle of the multiple cycles has been designated as cycle 11 a 11 and the remaining cycles have been designated as b, c, d . . . .
11            11 T1 *st Type                   The following types of tests were performed:
Steam - the fluid at the valve inlet and in the accumulator tank (tank 1) at test initiation and throughout the test was steam.
L.S. - these tests were loop seal tests. Just prior to test initiation, the fluid at the valve inlet was subcooled water and the fluid in the accumulator was steam. Once the loop seal water was discharged, the test fluiu was steam.
Trans. - these tests were transition tests. Prior to test initiation, the fluid at the valve inlet was steam and the fluid in the upper and lower portions of the accumulator tank were steam and saturated water, respectively. The valve opened on steam and closed on saturated water during the transition test .
A-2                                          *
 
        -,                                                                                     1*
.<<l' 1',
* L.S. Trans. ~ these tests were loop seal transition tests. The test was the same as a transition test except that the fluid immediately upstream of the safety valve was subcooled water.
Water - the fluid at the valve inlet and in the accumulator tank at test initiation and throughout the test was approximately saturated water, 550&deg;F water or 400&deg;F water. The water tests progressed from satura-ted water to the 55QOF water test and finally the 400&deg;F water test. Target Rock test included cold loop seals.
            ~alve Ring Settings          Valve ring positions are listed for the safety valve adjusting rings. Descriptions of the reference posi-tion for each of the safety valve manufacturer's valves tested are as follows:
Crosby Valves have two adjusting rings, an upper or guide ring and a lower or nozzle ring. Positions in the table are given in notches relative to the level position.
For the upper ring, the level position (O notches) is the position when the bottom of the upJ!er ring is flush with the bottom of the disc ringll). For the lower ring, the level position (O notches) is the position when the top surface of the lower ring is in contact with the bottom of the disc ring. Positive ring positions are positions where the rings have been moved up from the level position and negative ring positions are positions where the rings have been moved down from the level position.
For the upper ring, the level position (O notches) is the position when the bottom of the upJ!er ring is flush with the bottom of the disc ringll). For the lower ring, the level position (O notches) is the position when the top surface of the lower ring is in contact with the bottom of the disc ring. Positive ring positions are positions where the rings have been moved up from the level position and negative ring positions are positions where the rings have been moved down from the level position.
Field positions for the upper ring are provided by Crosby in notches relative to the "highest locked position" which is the upper limit of the ring's travel. The lower ring field positions are the same as the level positions.
Field positions for the upper ring are provided by Crosby in notches relative to the "highest locked position" which is the upper limit of the ring's travel. The lower ring field positions are the same as the level positions.       Both of the ring field positions are marked by Crosby on the valve.
Both of the ring field positions are marked by Crosby on the valve. Dresser Valves have three adjusting rings, termed upper, middle and lower rings. Positions for the upper ring are given in notches relative to the position where the top of the upper ring is flush with the top of the holes in the guide. Positions for the bottom surface of the middle ring and the top surface of the lower ring are relative to the seat plane. The term "level position" is not applicable to the Dresser safety valves. A-3 1*
Dresser Valves have three adjusting rings, termed upper, middle and lower rings.       Positions for the upper ring are given in notches relative to the position where the top of the upper ring is flush with the top of the holes in the guide. Positions for the bottom surface of the middle ring and the top surface of the lower ring are relative to the seat plane. The term "level position" is not applicable to the Dresser safety valves.
Inlet* Piping Configuration Condition at Valve Opening Transient Conditions.
TiTTue  disc ring is not an adjusting ring A-3
Field settings may be provided by Dresser relative to the bottom of the disc holder instead of the seat plane. The Dresser Instruction Manual re-lates the disc holder* plane to the seat plane in terms of notches for the lower and middle rings. The Target Rock Valve does not have adjustment rings so the ring setting column is not applicable.
 
Refer to the definitions applicable to Tables 3.1.l.a through 3.7.l.a. The fluid type, pressure, temperature and surization rate are listed for tank 1 and the fluid and temperature are tabulated for the valve inlet. All conditions are listed at the point in time when the valve initially begins to open. Specific parameters are as follows: Fluid -the fluid types are described under the definition for test type. For transition tests, two fluids are listed fo1* tank 1. The first fluid listed is the fluid in the top of the tank and the second fluid listed is the fluid in the lower portion of the tank. Pressure -the pressure is the valve main disc initial opening pressure.
Field settings may be provided by Dresser relative to the bottom of the disc holder instead of the seat plane. The Dresser Instruction Manual re-lates the disc holder* plane to the seat plane in terms of notches for the lower and middle rings.
Temperature  
The Target Rock Valve does not have adjustment rings so the ring setting column is not applicable.
-the temp9ratures for steam ditions correspond to the state reached by surizing steam which was initially saturated at a nominal pressure of 2300 psia. Note (1) is used in the tables instead of a ni.;merical temperature value for these cases. Pressurization Rate -The pressurization rate is determined from the accumulator (tank 1) pressure at the time the test valve began to open. The peak inlet pressure, back pressure, and liquid flow which occur while the valve is open are tabulated.
Inlet* Piping Configuration Refer to the definitions applicable to Tables 3.1.l.a through 3.7.l.a.
In addition, the induced bending moments are tabulated.
Condition at Valve Opening  The fluid type, pressure, temperature and pres-surization rate are listed for tank 1 and the fluid and temperature are tabulated for the valve inlet.
Specific parameter definitions are as follows: A-4 * 
All conditions are listed at the point in time when the valve initially begins to open.         Specific parameters are as follows:
*
Fluid - the fluid types are described under the definition for test type. For transition tests, two fluids are listed fo1* tank 1. The first fluid listed is the fluid in the top of the tank and the second fluid listed is the fluid in the lower portion of the tank.
* Peak Tank 1 Pressure -This is the maximum pressure observecr---;-r; tank 1 during a test. P2ak Back Prssure -This is the maximum sustained outlet pressure just downstream of the test valve which was observed during a test. During transition and water tests, the same back pressure orifice was used in the discharge piping as was used in the high back pressure steam tests with the exception of the Dresser 31709NA safety valve. For this valve, the intermediate back pressure orifice was used. Induced Bending Moment Opening/Closing  
Pressure - the pressure is the valve main disc initial opening pressure.
-The ments tabulated are the maximum bending moments imrosed on the test valve discharqe flange by the discharge piping. The first value listed is the larger of the bending moments during valve ing or valve closing when both values were able. If only one moment was available, that value was listed. Maximum Steady Liquid Flow -The maximum water flow rate for which a flow measurement was obtained . A-5   
Temperature - the temp9ratures for steam con-ditions correspond to the state reached by pres-surizing steam which was initially saturated at a nominal pressure of 2300 psia. Note (1) is used in the tables instead of a ni.;merical temperature value for these cases.
-he following definitions apply to Tables 3.1.1.c, 3.2.1.c, 3.3.1.c, 3.4.1.c, : : . 5. 1 . c, 3. 6. 1 . c and 3. 7. 1 . c : KEY TERMS AND PARAMETERS Test No. Test . Type Pre-Test Valve Leakage Valve Opening Closing DEFINITION Refer to the definitions applicable to Tables . 3. 1. l. b through 3. 7. l. b. Refer to the definitions applicable to Tables 3.1.l.b through 3.7.l.b. Pre-test valve leakage was measured before each test. The purpose of the valve leakage ments were to insure that leakage during the multiple tests of a test series was within a range that the valve manufacturer assessed would provide representative valve performance.
Pressurization Rate - The pressurization rate is determined from the accumulator (tank 1) pressure at the time the test valve began to open.
The leakage procedure and leakage range were only related to the safety valve tests and were not based on PWR plant leakage procedures.
Transient Conditions.      The peak inlet pressure, back pressure, and liquid flow which occur while the valve is open are tabulated. In addition, the induced bending moments are tabulated. Specific parameter definitions are as follows:
The leakage test and leakage range were included as part of the test procedure in order to determine whether or not a test should be performed.
A-4
If leakage occurred which exceeded the manufacturer's recommended test range, the valve was disassembled and the seats were normally lapped and in some cases replaced.
* Peak Tank 1 Pressure - This is the maximum pressure observecr---;-r; tank 1 during a test.
P2ak Back Prssure - This is the maximum sustained outlet pressure just downstream of the test valve which was observed during a test.
During transition and water tests, the same back pressure orifice was used in the discharge piping as was used in the high back pressure steam tests with the exception of the Dresser 31709NA safety valve. For this valve, the intermediate back pressure orifice was used.
Induced Bending Moment Opening/Closing - The mo-ments tabulated are the maximum bending moments imrosed on the test valve discharqe flange by the discharge piping. The first value listed is the larger of the bending moments during valve open-ing or valve closing when both values were avail-able. If only one moment was available, that value was listed.
Maximum Steady Liquid Flow - The maximum water flow rate for which a stabl~ flow measurement was obtained .
A-5
 
  - he following definitions apply to Tables 3.1.1.c, 3.2.1.c, 3.3.1.c, 3.4.1.c,
::. 5. 1 . c, 3. 6. 1 . c and 3. 7. 1 . c :
KEY TERMS AND PARAMETERS                                                     DEFINITION Test No.                                       Refer to the definitions applicable to Tables
                                            . 3. 1. l. b through 3. 7. l. b.
Test . Type                                    Refer to the definitions applicable to Tables 3.1.l.b through 3.7.l.b.
Pre-Test Valve Leakage                        Pre-test valve leakage was measured before each test. The purpose of the valve leakage measure-ments were to insure that leakage during the multiple tests of a test series was within a range that the valve manufacturer assessed would provide representative valve performance.         The leakage procedure and leakage range were only related to the safety valve tests and were not based on PWR plant leakage procedures. The leakage test and leakage range were included as part of the test procedure in order to determine whether or not a test should be performed.         If leakage occurred which exceeded the manufacturer's recommended test range, the valve was disassembled and the seats were normally lapped and in some cases replaced.
The leakage data is included to supplement the valve performance information.
The leakage data is included to supplement the valve performance information.
Specific test parameter definitions are as lows: Media -the media is the fluid at the valve inlet used for the leakage test. Nominal Valve Inlet Pressure and these are the approximate conditions at the valve inlet when the leakage test was performed.
Specific test parameter definitions are as fol-lows:
Leakage Rate -Leakage is expressed as gallons per minute of condensed leakage. One gpm condensed leakage is equivalent to a leakage rate of about 500 lbs/hr of steam. The data includes safety valve opening pressure, opening ti111e, closing pressure, valve blowdown and an assessm(?nt of valve stability.
Media - the media is the fluid at the valve inlet used for the leakage test.
These parameters describe the valve performance from valve opening through valve closure and are defined as frillows:
Nominal Valve Inlet Pressure and Temperature-these are the approximate conditions at the valve inlet when the leakage test was performed.
A-6 * * * 
Leakage Rate - Leakage is expressed as gallons per minute of condensed leakage. One gpm condensed leakage is equivalent to a leakage rate of about 500 lbs/hr of steam.
''
Valve Opening                                The data includes safety valve opening pressure,
! * *
~nd Closing                                  opening ti111e, closing pressure, valve blowdown and an assessm(?nt of valve stability. These parameters describe the valve performance from valve opening through valve closure and are defined as frillows:
* Initial Valve Opening Pressure -this is the test valve inlet static pressure at which there is a 111t'il'.LJt't1blv lift ol t11e disc away fro111 the closed position.
A-6
The pressure is measured in the cumulator (tank 1). The initial valve opening pressure corresponds to the main disc lift for the Crosby and Dresser test valves and corresponds to the pilot disc lift for the Target Rock test valve. Opening Pop Pressure -the pop pressure is the value of increasing inlet static pressure at which the main disc for all three manufacturer's designs moves in the opening direction at a faster rate as compared with corresponding movement at higher or lower pressures.
* Initial Valve Opening Pressure - this is the test valve inlet static pressure at which there is a 111t'il'.LJt't1blv lift ol t11e disc away fro111 the closed position.         The pressure is measured in the ac-cumulator (tank 1). The initial valve opening pressure corresponds to the main disc lift for the Crosby and Dresser test valves and corresponds to the pilot disc lift for the Target Rock test valve.
Opening Simmer time -Simmer time is the time elapsed between initial valve opening pressure and the valve pop pressure (see Figure A-1).
Opening Pop Pressure - the pop pressure is the value of increasing inlet static pressure at which the main disc for all three manufacturer's designs moves in the opening direction at a faster rate as compared with corresponding movement at higher or lower pressures.
* Opening Pop Time -This was the effective time for the valve stem to move from the closed position to the rated lift positiori.
Opening Simmer time - Simmer time is the time elapsed between initial valve opening pressure and the valve pop pressure (see Figure A-1).
In cases where the pop starts from an intermediate lift and/or the valve does not reach rated lift, the slope of the stem position is extrapolated to give a pop time for the entire lift range. The pop time does not include the stem acceleration time which normally occurs at the beginning of the pop. This is included with the total simmer time (see Figure A-1). Pop time is not applicable to subcooled water tests. Tank 1 Pressure at Valve Closure -Closing pressure is the pressure at which the valve main disc establishes contact with the seat (reseats).
* Opening Pop Time - This was the effective time for the valve stem to move from the closed position to the rated lift positiori. In cases where the pop starts from an intermediate lift and/or the valve does not reach rated lift, the slope of the stem position is extrapolated to give a pop time for the entire lift range. The pop time does not include the stem acceleration time which normally occurs at the beginning of the pop. This is included with the total simmer time (see Figure A-1). Pop time is not applicable to subcooled water tests.
The pressure is measured in the accumulator (tank 1). % Slowdown -Slowdown as used herein is the ference between the design set pressure and the actual reseating pressure expressed as a centage of the design set pressure.
Tank 1 Pressure at Valve Closure - Closing pressure is the pressure at which the valve main disc re-establishes contact with the seat (reseats). The pressure is measured in the accumulator (tank 1).
  % Slowdown - Slowdown as used herein is the dif-ference between the design set pressure and the actual reseating pressure expressed as a per-centage of the design set pressure.
NOTE: ANSI S95.l defines blowdown relative to the actual popping pressure.
NOTE: ANSI S95.l defines blowdown relative to the actual popping pressure.
Valve Stability  
Valve Stability - the valve stem behavior while the valve is open is defined as follows:
-the valve stem behavior while the valve is open is defined as follows: Chatter -chatter is rapid reciprocating motion of the movable parts in which the disc contacts the seat . A-7 Post-Test Leakage Flutter -flutter is rapid reciprocating motion of the movable parts in which the disc does not contact the seat. Stable -the. va*lve opens, remains open and closes without flutter and/or chatter. In some tests, combinations of these behaviors occurred (e.g. loop seal discharge) and the binations are clarified by a footnote on a case basis. The definition for the pre-test valve leakage applies except that the post-test valve leakage measurement was conducted after the test was pleted. In tests with multiple cycles, the test leakage data are listed for the first cycles but were measured after the last cycle.
Chatter - chatter is rapid reciprocating motion of the movable parts in which the disc contacts the seat .
* A-8 * *
* A-7
* 1, i: I I 1 !
 
z 0 ....... I-,_ ):::> VJ I 0 \.0 a. ::E: w I-VJ Rated Li ft Zero Lift * >* Representation of Typical Safety Valve Stem Position as a Function of Time Simmer Time Time }Extrapolate to Zero Lift ---------------
Flutter - flutter is rapid reciprocating motion of the movable parts in which the disc does not contact the seat.
Extrapolate to Rated Lift, If Necessary
Stable - the. va*lve opens, remains open and closes without flutter and/or chatter.
----------
In some tests, combinations of these behaviors occurred (e.g. loop seal discharge) and the com-binations are clarified by a footnote on a case-by-case basis.
-
Post-Test Leakage The definition for the pre-test valve leakage applies except that the post-test valve leakage measurement was conducted after the test was com-pleted. In tests with multiple cycles, the post-test leakage data are listed for the first cycles but were measured after the last cycle.
*--
* 1, i:
---------
I I 1 A-8
The following definitions apply to Tables 3.1,l.d, 3.2.l.d, 3.3.l.d, 3.4.l.d, 3.5. l.d, 3.6. l .d and 3.7.l .d: KEY TERMS AND PARAMETERS Test No. Jest Type Conditions at 3% l\ccumu lat ion CC1nditions at 6% Accumulation DEFINITION Refer to the definitions applicable to Tables 3. l. l. b through 3. 7. l. b. Refer to definitions applicable to Tables 3. 1.1.b through 3.7. l .b. The test valve lift position flow rate were evaluated at a pressure which was 3% above the valve design set pressure (3% accumulation) during the ;depressurization portion of the steam test transients.
 
The accumulation conditions are vided based on the pressure measured in tank 1 and on the pressure measured in the inlet pipe just upstream of .the safety valve. In each case, the valve lift position and steam flow rate are listed based on the following terms: % Rated Lift -this value is the lift position of the valve at 3% accumulation and is expressed as a percentage of the valve rated lift; Rated lift is the design lift at which a safety valve attains its rated steam relieving capacity.  
Representation of Typical Safety Valve Stem Position as a Function of Time Rated Li ft z
% Rated Steam Flow -this value is the steam flow rate through the valve at 3% accumulation expressed as a percentage of the valve rated capacity.
0 I-
Accumulation data are applicable to high ization rate steam tests only. Other tests were not designed to produce accumulation above the setpressure.
):::> VJ I   0
The inlet pipe pressure is corrected for velocity head to approximate the stagnation pressure at the valve inlet and to eliminate the difference due to static head losses in the inlet piping. In some steam tests, the 3% accumulation p1*essure was not achieved and that has been noted in the table. The definitions for Conditions at 3% Accumulation apply except that the valve lift and flow rate data were measured when the inlet pressure was above the valve design set pressure.
\.0   a.
A-10 * :* 
::E:
*
Extrapolate to Rated Lift, w
* Liquid Flow Measurement The maximum steady liquid flow as well as the associated pressure and temperature and valve lift positions are listed for the transition and water tests. Definitions for these terms are as follows: Tank Conditions  
I-If Necessary VJ Zero                               }Extrapolate to Zero Lift Lift Simmer Time Time
-the pressure and temperature associated with the measured liquid flow rate are based on tank 1 conditions.
                                                                  -- ------------- - - - - - - - - - - - - - - - - - - - - * - - -~-- -------~-
Maximum Steady Liquid Flow -refer to the finitions applicable to" Tables 3.1. l .b through 3.7.l.b. % Rated Lift -the value listed is the lift tion expressed as a percentage of the valve rated lift when the flow rate was measured.Rated lift is the design lift at which a safety valve attains its rated steam relieving capacity . A-11 The following terms were not used in the tables of section 3.0 but were used in the text of the report and are defined for information purposes:
 
KEY TERM DEFINITION The pressure in the accumulator used to pressurize the air operators of the relief valves tested in. Wyle Phase III tests. GN 2 is gaseous nitrogen.
The following definitions apply to Tables 3.1,l.d, 3.2.l.d, 3.3.l.d, 3.4.l.d, 3.5. l.d, 3.6. l .d and 3.7.l .d:
A-12 *}}
KEY TERMS AND PARAMETERS                                           DEFINITION Test No.                             Refer to the definitions applicable to Tables
: 3. l. l. b through 3. 7. l. b.
Jest Type                            Refer to definitions applicable to Tables 3. 1.1.b through 3.7. l .b.
Conditions at 3%                    The test valve lift position ~nd flow rate were l\ccumu lat ion                      evaluated at a pressure which was 3% above the valve design set pressure (3% accumulation) during the ;depressurization portion of the steam test transients. The accumulation conditions are pro-vided based on the pressure measured in tank 1 and on the pressure measured in the inlet pipe just upstream of .the safety valve. In each case, the valve lift position and steam flow rate are listed based on the following terms:
                                      % Rated Lift - this value is the lift position of the valve at 3% accumulation and is expressed as a percentage of the valve rated lift; Rated lift is the design lift at which a safety valve attains its rated steam relieving capacity.
                                      % Rated Steam Flow - this value is the steam flow rate through the valve at 3% accumulation expressed as a percentage of the valve rated capacity.
Accumulation data are applicable to high pressur-ization rate steam tests only. Other tests were not designed to produce accumulation above the setpressure.
The inlet pipe pressure is corrected for velocity head to approximate the stagnation pressure at the valve inlet and to eliminate the difference due to static head losses in the inlet piping.
In some steam tests, the 3% accumulation p1*essure was not achieved and that has been noted in the table.
CC1nditions at 6%                  The definitions for Conditions at 3% Accumulation Accumulation                        apply except that the valve lift and flow rate data were measured when the inlet pressure was 6~ above the valve design set pressure.
A-10
 
Liquid Flow The maximum steady liquid flow as well as the Measurement  associated pressure and temperature and valve lift positions are listed for the transition and water tests. Definitions for these terms are as follows:
Tank Conditions - the pressure and temperature associated with the measured liquid flow rate are based on tank 1 conditions.
Maximum Steady Liquid Flow - refer to the de-finitions applicable to" Tables 3.1. l .b through 3.7.l.b.
              % Rated Lift - the value listed is the lift posi-tion expressed as a percentage of the valve rated lift when the flow rate was measured.Rated lift is the design lift at which a safety valve attains its rated steam relieving capacity .
* A-11
 
The following terms were not used in the tables of section 3.0 but were used in the text of the report and are defined for information purposes:
KEY TERM                                             DEFINITION The pressure in the accumulator used to pressurize the air operators of the relief valves tested in.
Wyle Phase III tests.
GN 2 is gaseous nitrogen.
A-12
                                                                                    *}}

Latest revision as of 21:36, 17 March 2020

EPRI PWR Safety & Relief Valve Test Program:Safety & Relief Valve Test Rept, Interim Rept
ML18047A461
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EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM SAFETY AND RELIEF VALVE TEST REPORT Research Project Vl02 Interim Report, April 1982 Prepared by EPRI Valve Test Program Staff Prepared for Participating PWR Utilities and Electric Power Research Institute 3412 Hillview Avenue Palo Alto, California 94304 EPRI Project Managers T. Auble J: Hosler Nuclear Power Division s2o716ossa 820401 PDR ADOCK 05000255 p PDR

Copy11ghl 1f* 1982 Elecl11c Power Research lns111u1e. Inc. All 11ghls reserved NOTICE This reporl was p1epared by lhe Elect11c Power Research lnst1tule. Inc 1EPRll Ne1lher EPRI. members ol EPRI.

nor any person acting on their behalf (a) makes any warranty. express or implied. w1!h resoec1 to !he use er any rnformat1on. appa1alus. melhod. or process disclosed 1n lh1s report or lhal suc~1 use may no1 1nlr1nge prrvareJy owned 11ghls. or (bl assumes any l1ab1l1t1es wilh respecl to the use ol. or tor damages resulting tram lhe use ol.

any 1ntormalion, apparalus. method. or process disclosed 1n this report.

ii

EPRJ PERSPECTIVE PROJECT DESCRIPTION A valve test program was conducted by EPRI for a group of participating PWR utilities to respond to the USNRC recommendations documented in NUREG 0578 Section 2.1.2, "Performance Testing on BWR _and PWR Safety and Relief Valves," and as clarified in NUREG 0737, Item II.D.l.A. Documentation of the Program is contained in four major program outputs.*

  • Valve Selection/Justification Report
  • Test Condition Justification Report (Including the three PWR NSSS Vendor 11 Plant Condition Justification Reports")
  • Safety and Relief Valve Test Report
  • Application of RELAP 5/MOD 1 for Calculatibn of
  • Safety and Relief Valve Discharge Piping Hydrojynamic Loads 11 This report. entitled Safety an*d Relief Valve Test Report" together with the other

.three major program outputs, documents the required information for the participating PWR utilities to use in responding to the above mentioned USNRC recommendations.

PROJECT OBJECTIVE The* objectives of this report are:

  • Campi le a list of relief and safety valves utilized in or planned for use iri domestic participating PWR's and identify the valves selected for t<:sting.
  • For all tests performed as part of the EPRI PWR Safety and Relief Valve Test Program, present the "As Tested" Test Matrices, Valve f' er f o1*man c e Dat a and Pr i nc i pa l 0bs er vat i on s .
  • iii

PROJECT RES.UL TS

  • A total of seven safety valves and ten relief valves were selected for testing. All valve performance tests were completed in December, 1981. The "as tested 11 test matrices, valve performance data and principal observations have been compiled in a form such that pcrticipating utilities may use the results in developing their response to the USNRC recommendations documented in NUREG 0578 Section 2.1.2, and as clarified in NUREG 0737 Item II.D.1.A.

Thomas Auble and John Hosler, Project Managers Nuclear Power Division iv

  • ABSTRACT A safety anrl relief valve test program was conducted by EPRI for a group of par-ticipating PWR utilities to ri?spond to the USNRC recommendations documented in NUREG 0578 Section 2.1.~, and as clarified in NUREG 0737 Item II.D.l.A. Seventeen safety and relief valve~ rep1~sentative of those utilized in or planned for use in participating domestic PWRs wer~ tested under the full range of selected test conditions. This report contains a listing of the selected test valves and the corresponding "as tested" test matrices, valve performance data and principal observations for the tested safety and ~*elief valves. The information contained in this report may be used by the participat ng utilities in developing their response to the above mentioned USNRC recommendations .

v

  • ACKNOWLEDGMENTS This work was performed by the Electric Power Research Institute on behalf of the electric power utilities participating in the EPRI PWR Safety and Relief Valve Test Program.

EPRI wishes to thank the following individuals and organizations who contributed to the completion of the Safety and Relief Valve Test Report, Interim Report, April.1982:

D. Abdollahian s. Levy, Inc.

s. Kucharski Intermountain Technologies, Inc.

B. Sans Electric Power Research Institute (on loan from Framatome)

G. Wi 11 i amson Continuum Dynamics, Inc .

    • vii-
  • SECTION 1.0. INTRODUCTION TABLE OF CO~TENTS PAGE 1-1 2.0 PWR PRESSURIZER SAFETY AND RELIEF VALVES 2-1 2.1 List of Valves in Plants 2-1 2.2 Selected Test Valves and Valves Represented 2-2 2.3 Des:ription of Test Valves 2-4 2.3.l Sa f:?ty Valves 2.3.2 Relief Valves 3.0 SUM'1ARY OF SAFETY VALVE OPERABILITY DATA 3-1 3.1 Dresser Safety Valve Model 31739A 3-3 3 .1.1 Valve Description and Inlet Piping Configuration,

'"As Tested" Test Matrix and Valve Performance Data 3 .1. 2 Principal Observations 3 .2. Dre .ser Safety Valve Model 31709NA 3-23 3.2.1 Val"e Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data 3.2.2 Priticipal Observations 3.3 Cro~ by HB-BP-86 3K6 (Steam Internals) 3-35 3.3.l Val1e Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data

~.3.2 Principal Observations 3.4 Cro~.by HB-BP-86 3K6 (Loop Seal Internals) 3-53 3.4.1 Valve Description and Inlet Piping Configuration.

"As Tested" Test Matrix and Valve Performance Data 3.4.2 Pri11cipal Observations 3 ..5 Cro~by HB-BP-86 6M6 (Loop Seal Internals) 3-65

3. 5 .1 Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data 3:5.2 Principal Observations
  • ix

SE CTI ON 3.6

3. 6 .1 Crosby HB-BP-86 6NB (Steam Internals)

Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data PAGE 3-83

  • 3.6.2 Principal Observations 3.7 Targd Rock 69C 3-95
3. 7 .1 Valvr* Description and Inlet Piping Configuration, "As **e*sted" Test Matrix and Valve Performance Data 3.7.2 Prin*:i pa 1 Observations 4.0 SUMK\RY OF RELIEF VALVE OPERABILITY DATA 4-1
4. l Dres:.er Relief Valve 4-3 4 .1.1 "As **ested" Test Matrices and Valve Performance Data 4.1.2 Prin( ipal Observations 4.2 Crosl*y Relief Valve. .4-13 4.2.1 "As **ested" Test Matrices and Valve Performance Data 4.2.2 Prine ipal Observations 4.3 4.3.1 4.4 4.3.2 Target Rock Relief Valve "As **ested" Test Matrices and Valve Performance Data Principal Observations Control Components Relief Valve 4-23' 4-31 4.4.1 11 As lested" Test Matrices and Valve Performance Data 4.4.2 Prine ipal Observations 4.5 Masoreilan Relief Valve 4-49 4.5.1 "As lested" Test Matrices and Valve Performance Data 4.5.2 Principal Observations 4.6 Cope~-Vulcan Relief Valve (316 w/Stellite Plug and 4-61 17-4PH Cage) 4.6.1 "As lested" Test Matrices and Valve Performance Data 4.6.2 Principal Observations x
  • SE CTI ON PAGE 4.7 Copes-Vulcan Relief Valve (17-4PH Plug and Cage) 4-67 4.7.1 "As Tested" Test Matrices and Valve Performance Data 4.7.2 Principal Observations 4.8 MUESCO Controls Relief Valve 4-75 4.8.1 "A~ Tested" Test Matrices and Valve Performance Data 4.8.2 Principal Observations 4.9 Fi~her Controls Relief Valve 4-83 4.9.1 "A~ Tested" Test Matrices and Valve Performance Data 4.9.2 Principal Observations 4.10 Garrett Relief Valve 4-91 4.10 .1 "A~ Testtid" Test Matrices and Valve Performance Data 4 .10. 2 Principal Observations 5... 0 RE I ERENCES 5-1 APFcNDIX A - Definition of Key Terms and Parameters A-1 for Safety Valves xi

SUMMARY

The U. S. Nuclear Regulatory Commission (NRC) in their report NUREG 0578, 11 TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations 11 , dated July, 1979, recommended in Section 2.1.2 that Utilities operating and constructing nuclear power pl ants develop a program for performance te~;ts of power operated relief valves and self-ac.tivated safety valves which are used in the reactor primary coolant system.

The requirement of NUREG 0578 was later incorporaL;d into the "NRC Task Action Plan",

NUREG 0660 and it was further clarified in NUREG 0737, Item II.D.l.A. At the request of Utilities with PWRs, EPRI developed and implemented a Test Program for pov1er operated relief valves and safety valves.

The *primary objective of the EPRI PWR Safety and Relief Valve Test Program was to rrovide full scale test data confirming the functionability of primary system power cperated relief valves and safety valves for expected operating and accident con-ditions. The second objective of the program was to obtain sufficient piping thermal hydraulic load data to permit confirmation of models which may be utilized in plant unique analysis of safety and relief valve discharge piping systems.

TJ obtain valve operability data for the wide variety of safety and relief valves used.

or intended for use in PWR. plants, it was necessary to select a limited but fully representative set of valves for test purposes. The criteria used for valve selections are presented below:

  • test each basic valve type (spring-loaded safety valves, pilot operated safety valves, air operated relief valves, pilot operated relief valves)
  • test each different manufacturer's version of a type
  • test design variations in internal guiding parts which might affect valve performance .
  • S-1

The fina*1 valve evaluations resulted in the selection of ten power operated relief

  • valves and seven safety v.1lves to be tested. Justification that the test valve results were applicable to all PWR plant safety and relief valves was developed by the manufacturers of the valves being tested.

The tests performed covered a wide range of prototypical fluid conditions which may occur in PWR plants. ThE* tests included steam, water, steam-to-water transition and water seal fluid conditiJns at pressures of up to 2750 psia and flow rates of up to 670,000 lb/hr steam. Th2 fluid inlet conditions were based on conside~ation of PWR plant FSAR, cold overpressurization, and extended high pressure liquid injection events.*

All relief valve tests ~ere performed at the Marshall Steam Station test facility, Terrell, North Carolina (owned and operated by Duke Power Company) and the test facility located at Wyle Laboratories, Norco, California. All safety valve tests were performed at the test facility located at Combustion Engineering, Windsor, Connecticut. Valve performance testing was completed in December, 1981.

Documentation of the program is contained in four major program outputs.

  • Valve Selection/Justification Report
  • Test Conditions Justification Report

'.Including the three PWR NSSS Vendor "Plant .Condit-ion Justification Reports")

  • Safety end Re 1 ief Valve Test Report
  • Application of RELAP 5/MOD 1 for Calculation of Safety end Relief Valve Discharge Piping Hydrodyr amic loads.

S-2

This report entitled 11 Safety and Relief Valve Test Report 11 together with the other three major program outputs, documents the required information for the participating PWR utilities to use in responding to the above mentioned USNRC recommendations. These.

program outputs will provide the PWR Utilities with sufficient documentation and test' data to permit each PWR Licensee to develop plant specific submittals that demonstrate

  • the functionability of all PWR plant safety and relief valves and to comply with NUREG 0737, Item II.0.1.A .
  • S-3
  • Section 1 INTRODUCTION At the request of Utilities with pressurized water reactors (PWR's), the Electric Power Research Institute (EPRI) implemented a PWR Valve Test program responsive to the safety and relief valve test recommendations contained in NUREG 0578, Section 2.1.2 and as clarified in NUREli 0737, Item Il.D.l.A. The objective of the EPRI PWR Safety and Relief Valve Test Program was to perform full scale operability tests on a set of primary system relief and safety valves representative of those utilized in or planned for use in PWRs and gather discharge piping data to permit the bench marking of dis-charge piping analysis mE:thods. The test conditions were selected to be representa-tive of those expected in participating PWRs based on consideration of limiting FSAR, cold overpressurization, and extended high pressure liquid injection events.

This report presents the safety and relief valve test results generated as part of the Generic EPRI PWR Valve Test Program. The intent of the report is to provide the required valve performance information and data to permit PWR.licensees and applicants to demonstrate the functionability of power operated relief valves and safety valves utilized in the primary system of PWRs. The information presented includes key*

information typically used to assess valve functionability such as valve opening and closing data, transient depressurization data and valve inspection results. In addition, other supplemental information related to valve performance for these tests has been included. All valve performance tests were completed in December 1981.

This report is organized into five sections. Section 1 is the report introduction.

Section 2 lists the relief and safety valves utilized in or planned for use in domestic participating PWRs and identifies the valves that were selected for testing. The basis for test valve selection and justification is documented in Reference 1 of this report. Sections 3 and 4 present the "as tested" test matrices, valve performance data and principal observations for the relief and safety valves tested as part of the program, respectively. The basis and justification of the valve test conditions are documented in Reference 1, 2, 3,4 and 5 of this report. Section 5 contains the list of references of this reJort. In addition to these five sections, an Appendix A entitled "Definition of K*?y Terms and Parameters" has been included .

  • 1-1
  • 2.0 Section 2 PWR PRESSURlZER SAFETY AND RELIEF VALVES As part of the EPRI PWR Safety and Relief Valve Test Program, full-scale testing of pressurizer safety and relief valves representative of those in use or planned for use in PWR plants was performed. In order to select a set of valves for testing, a com-plete list of valve types, models, and sizes used or intended for use in domestic participating PWR plants was compiled based on information provided by the PWR Utilities, l~SSS vendors, and valve manufacturers. From these lists, valves were selected for testing which represent the participating PWR plant valve population.

Justifiction of the selection was developed based on evaluations performed by the valve manufacturers. These evaluations considered the effects of differences in valve operational characteristics, materials, design details, and sizes.

The purpose of this section is to:

  • present lists of safety and relief valves used or intended for use in domestic participating PWR plants and the PWR Utilities and plants which utilize these valves,
  • present lists of the safety and relief valves selected for testing, the valves represented by the test valves and a summary of the valve distribution in PWR plants,
  • present a description of the valves selected for testing .

2.1 LIST OF VALVES IN PLANTS The valve manufacturer and valve model numbers of safety and relief valves used in PWR plants are ~;umrnarized in Tables 2-1 and 2-2. These tables provide the following information:

  • Table 2-1 provides a list of safety valves (identified by manufac-tiJrer and model number) and the PWR Utilities and plants which utilize these valves;
  • 2-1
  • Table 2-2 provides a list of relief valves (identified by man1ifrir.-

f.1Jt"1*r anti 11111111* I nu111lir!t*) arid 1111* l'Wli UI. i Ii I. it*s c111d p I ant.~) wh icl1 uL i I i11!

these valves.

Table 2-2 has been updated since the Valve Selection/Justification Report (Reference 1), and it's list of relief valves was issued. The lists are identical except that the Commonwealth Edison Company, Zion 1 & 2 Plant Copes-Vulcan relief valve plug material has been changed from 17-4PH to 316 w/Stellite material. The technical justification of Reference 1 is not effected by this change.

2.2 SELECTED TEST VALVES AND VALVES REPRESENTED As can be seen from Tables 2-1 and 2-2, a large number of safety and relief valve models are used in PWR plants. As a result, it was necessary to perform engineering evaluations in order to select a number of valve types, models and sizes for test purposes that provide generic results that are applicable to all of the plants involved. These evaluations were performed by the valve manufacturers and they considered the effects of the differences in valve operation characteristics, ma-terials, design details, and sizes on valve operabil~ty. The criteria for valve selection that were used in conjunction with the above evaluations are presented below:

  • Include each basic valve type (e.g., spring-loaded safety valve, air-operated relief valve, etc.);
  • Include each different manufacturer's version of a given valve type (e.g., Dresser and Crosby spring-loaded safety valves);
  • Include each design variation in internal guiding parts which could impact valve performance (e.g., Copes-Vulcan 17-4PH cage/plug versus 316 w/stellite plug with a 17-4PH cage).

Utilizing the results of the above evaluations and valve selection criteria, a set of safety and relief valves were originally selected for testing. The types, models and PWR plant distribution of the valves selected for testing are presented in Tables 2-3 and 2-4.

2-2

  • Table 2-3 provides a list of the selected test safety valves, the
  • valves represented and the valve distribution in PWR plants;
  • Table 2-4 provides a list of the selected test relief valves, the valves represented and the valve distribution in PWR plants.

Table 2-4 has been updated since the Valve Selection/Justification Report and it's list of selected test relief valves was issued. The lists are identical except that the "Valves Represented, No. of Plants" column has been revised to include the previously noted change of Table 2-2.

n summary, nine safety valves and ten relief valves were originally selected for tests .. Based on valve vendor evaluations, the test results of the valves selected for testing (Tables 2-3 and 2-4) can be extended to the entire population of PWR valves represented by the selected test valves .
  • 2-3

?.3 DESl.RIPTION OF TESl VALVES The following is a brief description of the specific safety and relief valves which were tested.

2.3.l Safety Valves 2.3.1.a Crosby Valve and Gage Company. All PWR plants which have Crosby safety valves utilize the same basic valve design. Model No. HB-BP-86. The Crosby model is a direct acting spring lo~ded safety valve design. However, a variety of inlet, outlet and orifice sizes are utilized as listed in Table 2-3. Valves with the smallest and largest orifice sizes were selected for test, as well as a valve with an intermediate orifice size which is utilized in a large number of PWR plants. Also, the original selection included each of the three Crosby valves using two different sets of internals: one set which represents valves which are installed in systems which use loop seals, and the second set which represents valves which are installed in non-loop seal plants.

The original selection process resulted in a total of six Crosby safety valve designs selected for test. Once testing was initiated, the valve selection was re-evaluated and it was determined that the Crosby valve selection could be reduced from six safety valve variations to four safety valve variations and still obtain test results representative of all Crosby PWR plant safety valve designs.

The tested valves included each of the three orifice sizes originally selected for testing and each of the internal valve seating and guiding material combinations originally selected for testing.

The Crosby_ 3K6 safety valve was tested with both the steam and loop seal seating materials designed for their respective applications. These tests demonstrated the performance of the two different seat material combinations within a valve orifice size. With this test data and the assessment that the major effect of the variation in seat materials is on valve seat leakage and not overall valve performance, it was determined that the Crosby 6M6 and 6N8 safety valve designs could be tested utilizing 2-4

  • one representative seating material combination in each valve, instead of both loop seal and non-loop seal seating maLerial combinations. Loop seal internals were selected for test in the 6M6 valve (long inlet configuration with a loop seal) and steam internals were selected for test in the 6N8 valve (long inlet configuration with no loop seal).

As a result, the total selection of Crosby safety valves which needed to be tested to provide te~t. data representative of all Crosby PWR plant safety valyes was reduced from three Crosby orifice sizes and two internal seat material combinations per orifice size to three Crosby orifice sizes with two seat material combinations in one orifice size (3K6) and one seat material combination in each of two orifice sizes (6M6, 6N8). The total number of safety valves finally selected for test became seven valves instead of the originally selected quantity of nine valves defined in Reference 1.

A description of the three Crosby designs selected for testing is presented below.

  • HB-BP-86, 3K6 This valve model has the smallest orifice size and therfore the smallest flow capacity of the Crosby safety valves. This valve size is utilized in three of the 67 pl ants which have Crosby safety valves.
  • HB-BP-86, 6M6 This valve model was selected for testing because it is utilized in 38 of the 67 plants which have Crosby safety valves. Also, it provides test results with an intermediate orifice size which facilitates the extension of the Crosby valve test results to the other smaller Crosby safety valves.
  • HB-BP-86, 6N8 This valve model has the largest orifice size and flow capacity of the Crosby valves and is utilized in 6 of the 67 PWR plants which have Crosby safety valves.

Note that the three Crosby valves selected for test directly represent valves in 47 of the 67 PWR plants which utilize Crosby safety valves.

2.3.1.b. Dresser Industries. The same basic valve design, Model No. 31700, is used in all PWR plants which have Dresser safety valves. The Dresser valve is a direct acting spring loaded safety valve design. Again, a variety of combinations of inlet, 2-5

outlet and orifice sizes are used in the various PWR plants, as shown in Table 2-3. For the tests, two Dresser safety valves were selected, a valve with a small orifice size, and a valve with a large orifice size. Also, the two valves selected for test are the same models and sizes as valves installed in 28 of the 37 PWR plants which have Dresser valves. These valves are briefly described below:

  • 31739A This valve model has a small orifice size and flow capacity and is utilized in 11 of the 37 PWR plants which have Dresser safety valves.
  • 31709NA This valve model has the largest orifice size and flow capacity and is utilized in 17 of the 37 PWR plants which have Dresser safety valves.

2.3.1.c. Target Rock Corporation. There is only one PWR plant which uses Target Rock safety valves. The test valve, Model No. 69C, is representative of the valves installed in this plant. The Target Rock model is a pilot operated valve design actuated by the system inlet pressure 2.3.2 Relief Valves 2.3.2.a Control Components, Inc. The test valve is identical to the Control Com-ponents relief valves which are installed in 4 PWR plants. The Control Components drag valve model is an air operated globe valve design.

2.3.2.b. Copes-Vulcan, Inc. The Copes-Vulcan model is an air operated globe valve design. As indicated in Table 2-4,two different sets of valve internals with different material combinations are utilized in the Copes-Vulcan relief valves. Also, the initial design valves utilized a two-inch valve body with three inch butt weld ends while the more recent valves utilized a three-inch valve body. For the test, the three-inch valve body was selected because it directly represents 25 of the 38 plants which utilize Copes-Vulcan relief valves. Also, the test valve was tested with the two different types of internals in order to obtain results which are representative of all of the Copes-Vulcan valves in PWR plant service.

2-6

I f . 111 2.3.2.c. Crosby Valve and Gage Company. The Crosby model is an electrically actuated pilot operated valve.design. As shown in Table 2-4, there is only one model Crosby relief valve used in PWR plants, Model No. HPV-SN. However, there are differences in the specific versions of this model utilized in the three PWR plants, e.g.,

differences in bore size and body configuration. However, from a functional standpoint, the test valve is representative of both valve designs.

2.3.2.d. Dresser Industries. The Dresser models are electrically actuated pilot operated valve designs. As indicated in Table 2-4, there are two different Dresser valve models utilized in PWR plants: Model 31533VX-30 which utilizes a bellows in the pilot valve section of the valve, and Model 31533VX which does not have a bellows. For the test, Model 31533VX-30 was selected since it directly represents 20 of the 21 PWR valves. Also, the results obtained from the model 31533VX-30 valve represent Model 31533VX valve performance.

2.3.2.e. Fisher Controls. The Fisher Controls SS-103-SS-95 model is an air operated globe valve design. The test valve is identical to the Fisher Controls relief valves which are installed in three PWR plants .

  • 2.3.2.f. Garrett Pneumatic Systems Division. The Garrett valve model is an elec-trically actuated pilot operated valve design. There are two different versions of the same basic Garrett relief valve model, one with an angle body and one with a straight-through body. However, from a functional standpoint, the two valves are virtually identical. Accordingly, the results obtained with the straight-through test valve are representative of both Garrett valve models.

2.3.2.g. Masoneilan. The Masoneilan 20,000 Series model is an air operated globe valve design. The test valve is identical except for a variation in plug geometry to the Masoneilan relief valves-installed in the 8 PWR plants. The test valve results represent the performance of both plug designs and all Masoneilan PWR relief valves.

2.3.2.h. MUESCO .Controls, Inc. The MUESCO Controls 70-18-9 DRTX model is an air operated globe valve design. The test valve is identical to the MUESCO Controls relief valves installed in l PWR plant .

  • 2-7

2.3.2.i. Ta.!:..9_~ Rock_ Corporation. The Target Rock BOX-006 model valve is a pilot operated solenoid valve design. The test valve represents the Target Rock relief valves which are installed in 2 PWR plants.

  • 2-8 *
  • TABLE 2-1 LIST OF PWR UTILITIES, PLANTS AND PRESSURIZER SAFETY VALVES (Participating Utilities)

UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*

Model No. Size Assembly No.

Alabama Power Co. Farley l & 2 Crosby Valve & Gage HB-BP-86 6Ml 6 N56963- l Arizona Public Palo Verde l. 2, & 3 Dresser 31709NA Service Co.

Arkansas Power & Arkansas Nuclear Dresser 31759A (forged body, forged bonnet)

Ught Co. One-1 N

I

\.0 Arkansas Nuclear Crosby Valve & Gage HB-BP-86 6M6 55605 One-2 Baltimore Gas & Calvert Cliffs 1 & 2 Dresser 31739A (cast body, forged bonnet)

Electric Co. 31739A (forged body, forged bonnet)

Carolina Power & H.B. Robinson 2 Crosby Valve & Gage HB-BP-86 4K26 51249 Light Co.

Shearon Harris Crosby Va 1ve & Gage HB'-BP-86 6M6 N56964 1,2,3,&4 Commonwealth Zion l & 2 Crosby Valve & Gage HB-BP-86 6M6 Edi son Co. 51688 & N56499 Byron l & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 Braidwood l & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 Connecticut Yankee Connecticut Yankee Crosby Valve & Gage HB-BP-86 3K26 51185 Atomic Power Co.

TABLE 2-1 (Continued)

UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*

Model No. Size Assembl.z No.

Consolidated Indian Point 2 Crosby Valve & Gage HB-BP-86 4M6 51250-1 Edison Company of New York, Inc.

Consumers Power Co. Palisades Dresser 31739A (cast body, cast bonnet)

~lidland 1 &2 Dresser 31739A (forged body, forged bonnet)

Duke Power Co. Oconee &2 Dresser 31739A (cast body, cast bonnet)

Oconee 3 Dresser 31739A (forged body, forged bonnet)

McGuire &2 Crosby Valve & Gage HB-BP-86 6M6 N56925 Catawba &2 Dresser 31749A (forged body, forged bonnet)

N I Perkins 1

  • 2, & 3 Dresser 31709NA I--'

0 Cherokee 1, 2, & 3 Dresser 31709NA Duquesne Light Co. Beaver Valley 1 Target Rock 69C Beaver Valley 2 Crosby Valve & Gage HB-BP-86 6Ml6 N56963 Florida Power Corp. Crystal River 3 Dresser 31739A (forged body, forged bonnet)

Florida Power Turkey Point 3 & 4 Crosby Valve & Gage HB-BP-86 4K26 51249

& Light Co.

St. Lucie l Crosby Valve & Gage HB-BP-86 3K6 N54495 St. Lucie 2 Crosby Valve & Gage HB-BP-86 3K6 N59336 Georgia Power Co. Vogtle 1 & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 Houston Lighting South Texas l & 2 Crosby Valve & Gage HB-BP-86 6N8 N60491

& Power Co.

Indiana &Michigan Donald C. Cook l & 2 Crosby Valve & Gage HB-BP-86 6M6 51688 Electric

UTILITY PLANT TABL. (Continued)

VALVE MANUFACTURER Model No. Size VALVE MODEL NO. AND DESCRIPTION*

Assembly No.

Kansas City Power and Light Wolf Creek Crosby *valve & Gage HB-BP-86 6M6 N60446 Kansas Gas &

Electric Co.

Louisiana Power Waterford 3 Oresser 31749A (forged body, forged bonnet)

& Light Co.

Ma i.ne Yankee Maine Yankee Dresser 31709KA (cast body, forged bonnet)

Atomic Power Co.

Metropolitan Three Mile Isl and 1 Dresser 31739A (cast body. cast bonnet and Edi son Co. forged body, forged bonnet)

Three Mile Island 2 Dresser 31759A (forged body, forged bonnet)

N Northeast Utilities Millstone 2 Dresser 3l739A *(forged body, forged bonnet)

,_.I

,_. Mi 11 stone 3 Crosby Valve & Gage HB-BP-86 6M6 N56964-4 Northern States Prairie Isl and 1 Crosby Valve & Gage HB-BP-86 6Ml 6 52137 & N57872 Power Company Prairie Island 2 Crosby Valve & Gage HB-BP-86 6Ml 6 52137 Omaha Public Fort Calhoun 1 Crosby Valve & Gage HB-BP-86 3K6 50646-1 Power District Paci fie Gas & Di abl o Canyon l &2 Crosby Valve & Gage HB-BP-86 6M6 51688 Electric Co.

Portland General Trojan Crosby Valve & Gage HB-BP-86 6M6 N55366 Electric Co.

  • Pebble Springs l &2 Dresser 31709NA Power Authority Indian Point 3 Crosby Valve & Gage HB-BP-86 6M6 51688- l of the State of New York Public Service Marble Hi 11 l &2 Crosby Valve & Gage HB-BP-86 6M6 N56964 of Indiana

TABLE 2- T (Continued)

UTILITY PLANT YALVE MANUFACTURER VALVE MODEL NO. AND D~SCRIPTION*

Model No. Size Assembly No.

Public Service Co. Seabrook 1 & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 of New Hampshire Public. Service Salem l & 2 Crosby Valve & Gage HB-BP-86 6M6 51688 Electric & Gas Rochester Gas and Ginna Crosby Valve & Gage HB-BP-86 4K26 51249 Electric Corp.

Sacramento Municipal RANCHO-SECO l Dresser 3l 759A (forged body, forged bonnet)

Utility District South Carolina Virgil C. Summer* Crosby Valve & Gage HB-BP-86 6M6 N56964- l Electric & Gas Southern California San Onofre Crosby Valve & Gage Edi son Company HB-BP-86 3K26 47469-1 &N51185-2 San Onofre 2 & 3 Dresser 31709NA N

,__.I Tennessee Valley Sequoyah 1 &2 Crosby Valve & Gage HB-BP-86 6M6 51688 N Authority Watts Bar l & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 Bellefonte 1 & 2 Dresser 31709NA Yellow Creek 1 & 2 Crosby Valve & Gage HB-BP-86 6N8 N61894 Texas Utilities Commanche Peak 1 & 2 Crosby Valve & Gage HB-BP-86 6M6 N56964 Generating Co.

Toledo Edison Co. Davis. Besse 1 Crosby Valve & Gage HB-BP-86 4Ml6 N54891 & N59303 Union Electric Co. Ca 11 away l & 2 Crosby Va 1 ve & Gage HB-BP-86 6M6 N60446 Virginia Electric Surry l & 2 Crosby Valve & Gage HB-BP-86 6K26 51689

& Power Co.

North Anna & 2 Dresser 31759A (cast bod'" forged bonnet)

-.)

North Anna 3 & 4 Crosby Valve & Gage HB-BP-86 4Ml6 N56264

  • _J

UTILITY PLANT

~E 2-1 (Continued)

VALVE MANUFACTURER VALVE MODEL NO. & DESCRIPTION*

Model No. Size Assembly No.

Washington Public WPPSS 1 & 4 Dresser 31709NA Power Supply System WPPSS 3 & 5 Crosby Valve & Gage HB-BP-86 6N8 N60582 Wisconsin Point Beach 1 & 2 Crosby Valve & Gage HB-BP-86 4K26 51249 Electric Power Wisconsin Public Kewaunee Crosby Valve & Gage HB-BP-86 6Ml6 52137 Service Corp.

  • The assembly no. is a unique identifier for each hardware variation in the Crosby Valve & Gage N

I Safety Valve model HB-BP-86.

f--'

w The size of the Crosby Safety Valve covers the valve inlet size, (3" - 6") orifice size (K, K2, Ml, M, N) and outlet size (6 8").

11 The only information required to uniquely identify the Target Rock Safety Valves is the model no.

The model no. and any parenthetical information on the _body and bonnet uniquely identify the Dresser Safety Valves.

/

/

  • LIST OF PWR UTILITIES, PLANTS AND POWER OPERATED RELIEF VALVES r,"

{Participating Utilities)

UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*-

MODEL NO. SIZE AND DESCRIPTION Al a bama Power Co. Farley l & 2* Copes-Vulcan Globe 3" NPS, 316 W/Stellite Arizona Public Palo Verdel, 2, & 3 D-100-160 Plug and 17-4PH Cage Service Co. No PORVs No PO RVs Arkansas Power & Arkansas Nuclear Dresser Light Co. One-1 31533VX-30 l 3/ 32" Bore N

I Arkansas Nuclear No PORVs

........ One-2 No PO RVs Ul Bal ti more Gas & Calvert Cliffs l & 2 Dresser 31533VX-30 Electric Co. l 5/16" Bore Carolina Power & H.B. Robinson 2 Copes-Vulcan Globe 2" NPS, 17-4 PH Plug Light Company D-100-160 and Cage Shearon Harris Copes-Vulcan l, 2, 3, & 4 Globe 3" NPS, 316 W/Stellite Plug .

D-100-160 and 17-4PH Cage Commonwea 1th Zion 1 & 2 Copes-Vulcan Globe 2" NPS, 316 w/Stellite Plug Edi son Company D-100-160 l 7-4PH Cage Byron l & 2 Copes-Vulcan Globe 3" NPS, 316 W/Stellite D-100-160 Plug and 17-4 PH Cage Braidwood l & 2 Copes-Vulcan Globe 3" NPS, 316 W/Stellite D-100-160 Plug and 17-4 PH Cage Connecticut Yankee Connecticut Yankee Copes-Vulcan Ato mi c Power Co. Globe 3" NPS, 316 W/Stell ite D-100-160 Plug and 17-4 PH Cage

TABLE 2-2 (Continued)

UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*

MODEL NO. SIZE AND DESCRIPTION Consolidated Edison Indian Point 2 Copes-Vulcan Globe 3" NPS, 316 W/Stellite Company of D-100-160 Plug and Haynes #25 Cage New York, Inc.

Consumers Power Co. Palisades Dresser 31533VX l 3/8" Bore Midland l & 2 Target Rock 80X006 2~" Inlet, 4 Outlet 11 Duke Power Co. Oconee & 2 Dresser 3l 533VX-30 3/32 Bore 11 Oconee 3 Dresser 31533VX-30 3/32 Bore 11 Mc Gui re &2 Control Components, Inc. Drag Valve 3 NPS 11 N

I Catawba & 2 Control Components, Inc. Drag Valve 3 NPS 11 CJ)

Perkins l , 2, & 3 No PORVs No PORVs Cherokee l, 2, & 3 No PORVs No PORVs Duquesne Light Co. Beaver Valley l Masoneilan 20,000 Series 2 NPS 11 Beaver Valley 2 Fisher Controls SS-103-SS-95 3 NPS 11 Florida Power Corp. Crystal River 3 Dresser 31533VX-30 5/32 11 Bore Florida Power & Turkey Point 3 &4 Copes-Vulcan Globe 2" NPS, 17-4PH Plug Light Company D-100-160 and Cage St. Lucie Dresser 3l 533VX-30 5/32" Bore St. Lucie 2 Garrett Angle Valve 3 inch inlet, 8 inch outlet

UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*

MODEL NO. SIZE AND DESCRIPTION Georgia Po1~er Co. Vogtl e l & 2 Garrett Straight Through 3" inlet, 6 11 outlet Houston Lighting South Texas 1 & 2 Copes-Vulcan

& Power Company Globe 3" NPS, 316 W/Stellite D-100-160 Plug and 17-4 PH Cage Indiana &Michigan Donald C. Cook l & 2 Masoneilan Electric 20,000 Series 211 NPS Kansas City Power and Light Ho l f Creek Garrett Straight Through 3" inlet, 6" outlet Kansas Gas & Electric Company Louisiana Power Waterford 3 No PORVs r;v & Li ght Co . No PORVs Maine Yankee Atomic Maine Yankee Dresser 31533VX-30 5/16" Bore Power Co.

Metropolitan Three Mile Island Dresser 31533VX-30 3/32" Bore Edi son Co.

Three Mile Island 2 Dresser 31533VX-30 5/16" Bore Northeast Utilities Millstone 2 Dresser 31533VX-30 5/16" Bore Millstone 3 Garrett Straight Through 3" inlet, 6" outlet Northern States Prairie Island 1 Copes-Vulcan Globe 2" NPS, l 7-4PH Plug D-100-160 and Cage.

Prairie Island 2 Copes-Vulcan Globe 2" NPS, 17-4PH Plug D-100-160 and Cage Omaha Public Fort Calhoun l Dresser 31533VX-30 l 3/32" Bore Power District

TABLE 2-2 (Continued)

UTILITY PLANT VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*

MODEL NO. SIZE AND DESCRIPTION Paci fie Gas & *Diablo Canyon l & 2 Masoneilan Electric Co. 20,000 Series 2" NPS*

Portland General Trojan Copes-Vulcan Electric Co. Globe 311 NPS, 316 W/Stellite D-100-160 Plug and l7-4PH Cage Pebble Springs l & 2 Dresser 31533VX-30 l 5/16" Bore Power Authority Indian Point 3 Copes-Vulcan of the State of Globe 3" NPS, 316 W/Stellite flew York D-100-160 Plug and Haynes #25 Cage Public Service of Marble Hill 1 & 2 Co pes-Vul qi.n Indiana Globe 3" NPS, 316 W/Stellite D-100-160 Plug and 17-4PH Cage N

,_.I Public Service Co. Seabrook 1 & 2 Copes-Vulcan CXl of New Hampshire Globe 3" NPS, 316 W/Stellite 0-100-160 Plug and 17-4PH Cage Public Service Sal em l & 2 Copes-Vulcan El ec tr i c & Gas Globe 2" NPS, 17-4PH Plug 0-100-160 and Cage Rochester Gas & Ginna Copes-Vulcan E: i e ctr i c Corp .

Globe 3" NPS, 316 W/Stell ite D-100-160 Plug and 17-4PH Cage Sacramento Municipal RANCHO-SECO l Dresser Utility District 31533VX-30 l 5/32" Bore South Carolina Virgil C. Summer Copes-Vulcan Gas & Electric Globe 3" NPS, 316 W/Stellite D-100-160 Plug and 17-4PH Cage Southern California San Onofre l MUESCO Controls Edi son Company 70-18-9 DRTX 2 11 NPS San Onofre 2 & 3 No PORVs No PORVs Tennessee Va 11 ey Sequoyah Masonei la n Authority 20,000 series 2" NPS Sequoyah 2 Copes-Vulcan Globe 0100-160 3" NPS, 316 W/Stellite Plug and l7-4PH Cage Watts Bar l & 2 Fisher Controls SS-103-SS-95 Bellefonte l & 2 3" NPS Dresser 31533VX-30 l 5/16" Yellow Creek l & 2 No No PORVs

UTILITY PLANT TABLE (Continued)

VALVE MANUFACTURER VALVE MODEL NO. AND DESCRIPTION*

MODEL NO. SIZE AND DESCRIPTION Texas Utilities Commanche Peak l & 2 Copes-Vulcan Globe Generating Co. 3tt NPS, 316 W/Stellite D-1 00-1 60 Plug and 17-4PH Cage Toledo Edison Co. Davis Besse l Crosby Valve & Gage Co. HPV-SN l l/2tt Bore Union Electric Co. Ca 11 away l & 2 Garrett Straight 3" inlet, 6tt outlet Through Virgini~ Elertrir ~ <;11rrv l* & 2 Copes-Vulcan Globe Power Co.

. - .* J 2 11 NPS, i 7-4PH Plug and D-100-160 Cage North Anna &2 Masoneil an 20,000 Series 2" NPS North Anna 3 & 4 Crosby Valve & Gage HPV-SN 3/Btt Bore N

Washington Public WPPSS 1 & 4 Dresser 31533VX-30 5/l 6tt Bore I

Power Supply System

\.Q l~PPSS 3 &5 No PORVs No PO RVs Wisconsin Electric Point Beach l & 2 Copes-Vulcan Globe Power 2" NPS, l 7-4PH Plug and D-100-160 Cage Wisconsin Public Kewaunee Masoneil an 20,000 Series Service Corp. 2" NPS

  • NPS is the nominal pipe size of the valve

TABLE..

EPRI S/RV TEST PROGRAM SELECTED VALVES, VALVES REPRESENTED. VALVE DISTRIBUTION IN PARTICIPATING PWR'S Pressurizer Safety Valves Valve Manufacturer Selected Test Valves Valves Re~resented No. of Model No. Size Model No. 1 ze Plants Inlet Orifice Outlet Inlet Orifice Outlet Crosby Valve & Gage HB-BP-86 3 K 6 HB-BP-86 3 K 6(small est) 3 Company 6 M 6 3 V')

1'.L c

u

')

II 6 N 8 4 K2 6 6 i 6 K2 6 2 I 4 Ml 6 3 6 Ml 6 6 I

N I

N I-' 4 M 6 l I 6 M 6 38 I

I 6 B(largest)

N 6 Dresser Industries 3l 739A 2.5 No.3 6 31709KA 2.5 K 6 ( s ma 11 est ) l I 31709NA 6 N 8 31739A 2.5 No.3 6 11 31749A 3 No.4 6 3 31759A 3 No.5 6 5..

31709NA 6 N B(largest) 17 2 2 Target Rock Corp. 69C 6 3.513in 6 69C 6 3.513in 6 l Total 105 Note: Inlet and outlet sizes are nominal pipe sizes in inches

(1) I Inlet and outlet Sizes are nominal p_ipe sizes in inches.

(2)

  • Crosby valves selected for test include both loop seal internals (3K6, 6M6) and non-loop seal internals (3K6, 6N8)
  • The tested valves with loop seal internals represent plants with Crosby valves installed on a loop seal. The tested valves with non-loop seal internals represent plants with Crosby valves installed without a loop seal.

2-22 *

  • -4 EPRI S/RV TEST PROGRAM SELECTED VALVES, VALVES REPRESENTED, VALVE DISTRIBUTION IN PARTICIPATING PWR'S Power Operated Relief Valves Valve Manufacturer Selected Test Valves Valves Represented Model No. Size Model No. Size No. of Plants Control Components, Inc. Drag Valve -

3" NPS Drag Valve 3" NPS 4 Copes-Vulcan Globe 0-100-160 3" NPS Globe D-100-160 2" NPS 11 II with 17-4PH cage

  • with 17-4PH cage I N

I and plug and plug II N

w I Globe D-100-1 60 3" NPS Globe D-100-160 3" NPS 25 with 316 w/stellite with 316 plug and 17-4PH cage w/stell ite plug and 17-4PH cage Globe 0-100-160 3" NPS 2 with 316 I w/stell ite plug j

&Haynes #25 cage I I

Crosby Valve & Gage Co. HPV-SN l 3/8" bore HPV-SN 1 3/8" bore 2 1 1I2" bore 1 Note: NPS is the valve nominal pipe size

TABLE 2-4 (Continued)

EPRI S/RV TEST PROGRAM SELECTED TEST VALVES, VALVES REPRESENTED, VALVE DISTRIBUTION IN PARTICIPATING PWR 1 S Po~~r Operated Relief Valves Valve Manufacturer Selected Test Valves Valves Represented Model No. Size Model No. Size tlo. of Pl ants Dresser Industries 3l 533VX-30 l 5/16" bore 31533VX-30 l 3/32" bore 6 l 5/32 11 bore 3 l 5/16 11 bore 11 31533VX l 3/8 11 bore l N

I Fisher Controls Co. SS-103-SS-95 3" NPS SS-103-SS-95 311 NPS N 3

~

Garrett Pneumatic Straight Through 3" inlet Angle 3" inlet Systems Division l 6" outlet 811 outlet Straight Through 311 inlet 6 511 outlet Masonei l an 20,000 Series 211 NPS 20,000 Series 2" NPS 9 MUES CO Cont ro 1s, . Inc. 70-18-9 DRTX 211 NPS 70-18-9 DRTX 2" NPS l Target Rock Corp.

11 inlet 80X-006 2~

11 inlet 2 4" outlet 4 11 outlet Total 88 Note: llPS is the valve nominal pjpe size

Section 3 3.0

SUMMARY

OF SAFETY VALVE OPERABILITY DATA A total of seven PWR pressurizer safety valve designs were tested under steam, water, steam-to-water transition and loop seal conditions.

The seven safety valves selected for testing in the EPRI program and the safety valves represente'd by the valves tested are identified in Section 2.0 of this report.

All safety valve testing as part of the EPRI PWR Safety and Relief Valve Test Program is complete. The purpose of this section is to present the valve description and inlet piping configurations, "as tested" test matrices, valve performance data and principal obst~rvations for all safety valves tested.

To assist in understanding the overall performance of each of the three manufacturer's safety valve clesigns, refer to the Valve Description Section of the "Valve Selection/

Justification Report" (Reference l)as well as Appendix A, "Definition of Key Terms and Parameter::".

3-1

  • . 3.1 DRESSE.R S/\FUY VALVE MO!JEL 31739A 3 .1.1 Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Dresser 317.39A safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The valve was tested on both a short (test series 300 and 1100, configuration C) and a long (test series 1000, configuration D) inlet piping configuration. The following is the list of tables that contain the safety valve information/data for these tests:

Table Description Table Number Safety Valve Description and Inlet Piping Configuration 3.1.l.a "As Tested" Test Matrix 3.1.l.b Valve Transient and Leakage Performance Data 3.1.l.c Valve Flow Rate Performance Data 3.1.l.d

  • 3.1.2 Principal Observations 3.1.2.a. Short Inlet Configuration (Configuration C). A total of nineteen tests were performed with the valve mounted on a short inlet pipe configuration. Of these tests, fifteen were steam tests performed with ring positions representative of those utilized in typical PWR plant installations and with ring position adjustments meant to improve the valve test performance. The final steam test ring position used (test no. 1104) was then maintained during the remaining non-steam test conditions. The principal observations for these tests are as fQllows:

Steam Tests Tests nos. 302 through 308 were steam tests performed at high and low ramp rates, high and low back pressures and with a ring position established by Dresser as a po~ition representative of typical PWR plant ring positions.

For these test~., the valve opened with.in +3% of the valve design set 3-3

prt'ssure, but the valve did not. achiev(~ rated lift at an accumulation pressure of 6% above the valve design set point. In one low back pressure test (no. 306), rated flow was achieved at an accumulation pressure of 6%

above the valve design set pressure. Rated flow was not achieved at 6%

-0ccumulation pressure for the other tests.

For the remaining steam tests, nos. 310 through 328 and no. 1104, the tests were performed at a high ramp rate with high and low back pressures and various ring positions. The purpose of these tests was to achieve and maintain the valve rated lift position or the valve rated flow rate. In all of the 300 series tests and the first actuation in test no. 1104, the valve opened within ~3% of the valve design set pressure and had stable behavior.

Valve rated lift was achieved and maintained at both high and low back pressures for the latter 300 series tests (nos. 324 and 326). For the final steam test ring position used in test no. 1104 (selection based on 1000 series long inlet pipe configuration tests), rated lift was not maintained at a pressure 6% above the valve design set pressure but rated fl ow was maintained. The valve closed with 11.0% blowdown. Immediately after closing, the valve re-opened at 2240 psia to a partial lift position and closed at 2227 psia.

Transition Test During the high back pressure, steam-to-water transition test, the valve opened within !3% of the valve design set pressure, had stable performance and closed with 19.1% blowdown.

Water Tests Three high back pressure water tests were performed at nominal water tem-peratures of 650, 550 and 400°F. The valve had stable behavior for all of the tests. During the 65QOF water test, the valve opened within +3~

of design set pressure and closed with 16.8~ blowdown.

For the 5500 water tE'st, the valve opened at 2387 psi a and closed with 12. 3?:0 blowdown. During the 4QQOF water test, the valve opened to a partial lift 3-4

position within +/-_3% of design set pressure. The system pressure continued to accumulate while the valve remained in a partial lift position. The test was terminated when the tank 1 pressure reached 2749 psia.

Valve Inspection Results The valve was disassembled and inspected during the test series. On inspection, the typical wear pattern observed as scratches or marks on the seat surfaces. To minimize seat leakage, the seats were lapped prior to reassembly and continued testing.

3.1.2.b. Long Inlet Pipe Configuration (Configuration D). A total of twelve tests were performed on the Dresser 31739A safety valve mounted on a long inlet pipe configuration. The principal observations for these tests are as follows:

Steam Tests Six drained loop seal steam tests were performed at test initiation ramp rates of 2.3 - 309 psi/sec and with a back pressure range of 220 to 617 psia. The first ring position selected (-48, -60, O) resulted in chatter in test No. 100!:*. The te!;t was terminated after the valve was manually opened to stop the chattering. Following this test, four ring adjustments were made in order to improve the valve test performance. For all of the subsequent tests, the valve opened within +/-_3% of the design set pressure, had stable performance and closed with a bl6wdown range of 10.7 to 14.2%.

For those tests when the system pressure accumulated to 6% above the valve design set pressure, rated lift was achieved.

Loop Se~l - Steam Tests Three loop seal - steam tests were performed with the two fina*1 ring po-sitions of the steam testing. For two of the tests, the valve lift ini-tiation pressure was within +3% of the valve design set pressure. For the other test, the lift initiation pressure was 2595 psia. During two of the loop seal discharges, the valve fluttered and/or chattered at partial lift positions, then the valve popped open on steam at system 3-5

pressures of 2594 to 2678 psia, stabilized, and closed with 10.0 to 13.9% blowdown. The second ring position used in the loop seal steam tests (-48, -40, +11) was also used for all of the subsequent trans-ition and water tests.

While the loop seal was being discharged during two of the loop seal tests and one transition test, the valve fluttered and/or chattered through partial lift positions at frequences of approximately 170-260 Hz. The valve oscillations during the water discharge caused water-hammer type pressure oscillations in the valve inlet piping. Pressure oscillations measured in the pressure transducers immediately upstream of the valve inlet indicated pressures ranging from 0 psia to a pressure which over-ranged the transducer at 3400-3600 psia. These pressure oscillations were not observed in Tank 1.

Transition Test One high back pressure, loop seal, steam-to-water transition test was performed. The valve lift initiation occurred at a pressure within ~3% of the valve design set pressure. The valve then fluttered and/or chattered at partial lift positions during the loop seal discharge and subsequently popped open on steam at 2535 p~ia. Valve performance was stable on steam and the valve closed on water with 14.0% blowdown.

The pressure oscillation description in the Loop Seal-Steam Tests section also applies to the transition test.

Water Tests Two high back pressure water tests were performed at nominal water temp-eratures of 650 and 550°F. The first test was a fi!10°F water test. ThP valve opened, had stable performance and closed with a 19.3% blowdown.

During the 550GF water test, the valve opened and chattered. The. test was terminated after the valve was manually opened to stop chattering .

3-6

  • y_aJ..~_e_ }!1 spe_c ti on .~-es ul ~-s After the water test which was terminated by manually opening and closing the valve to stop chattering, the valve was disassembled and inspected.

Galled guiding surfaces and several damaged internal parts were found.

For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage .

  • 3-7
  • EPRI/CE VE TEST PROGRAM TABLE 3.1.1 .a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION DRESSER 31739A SAFETY VALVE Valve Descrietion Inlet Piein9 Configuration 11011 Length, in. I.D., in.

Manufacturer Dresser Industries Type Nozzle 17 6.813 Spring Loaded Safety Valve Model No. 31739 A Serial No. BN-04372 Venturi 38 6.813 Drawing No. 4CP-2432 Rev. 9 Pipe 11 6.813 Body Size (inlet/outlet) 2~ in./ 6 in. Reducer Bore Area 2.545 in.2 6 6.813/3.152 Orifice Designation* 3 Loop Seal Design Set Point Pressure

  • 2500 Stra *j ght 60 3.152 w psig Bends 4-90° 6 in. radius I

\.0 Design Blowdown 5 percent Reducer 4 3 . 152/ 2. 125 Rated Flow 297845 lb/hr. Rated Lift 0. 45. in. Inlet Flange 6 2.125 Internals Type: Not applicable Ring Setting Reference Position: Inlet Pieing Configuration 11c" The ring setting positions refer to the number of Length, in. I. D., in.

notches relative to the followinq surfaces; Nozzle 17 6.813 Upper Ring - top holes in the guide Middle Ring- seat plane 38 6.813 Lower Ring - seat plane Venturi Pipe 11 6.813 Reducer 10 6.813/2.125 Inlet Flange 6 2.125

  • EPRI/CE VE TEST DATA "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE DRESSER 3l739A SAFETY VALVE TEST TEST CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS VAL VE RING INLET NO. TYPE SETTINGS PIPING IN TANK 1 AT VALVE INLET PEAK PEAK INDUCED ( 2) MAX. STEADY UPPER MIDDLE LOWER CONFIG. TANK 1 BACK- BENDING MOMENT LIQUID FLOW FLUID PRESS. TEMP. PRESS. RATE FLUID TEMP. PRESS. PRESS. OPENING/CLOSING (PSIA) (OF) {PSI/SEC) (GPM)

(OF) (PSIA) (PSIA) (IN. LBS.)

  • 302 STEAM -48 0 -13 c STEAM 2483 (l) 3.7 STEAM (1) 2483 304 STEAM -48 87 94,250 N/A 0 -13 c STEAM 2526 (1 ) 300 STEAM (l) 2638 306 STEAM -48 132 94,250 N/A 0 -13 c STEAM 2557 (1) 320 STEAM (l ) 2680 308 STEAM -48 160 84,825 N/A 0 -13 c STEAM 2547 (1) 329 STEAM (1) 2677 310 STEAM -48 477 98,963 N/A

-9 c STEAM 2557 (1) 343 STEAM (l) 2680

  • 312 STEAM -48 170 103,675 N/A 0 -13 c STEAM 2524 (l ) 360 STEAM (l) 2684 314 STEAM -48 485 98,963 N/A

-20 (3) c STEAM 2537 (l ) 333 STEAM (l) 2680 316 STEAM -48 177 94,250 N/A

-40 11 c STEAM 2590 (l ) 320 STEAM (1) 2703 w 318 STEAM 195 89,538 ~II A

-48 -40 11 c STEAM 2483

,_..I (l) 285 STEAM (l) 2685 195 94,250 N/A

,_.. 320 STEAM -48 -40 11 c STEAM 2580 (1) 316 STEAM (1) 2667 866 103,675 322 STEAM -48 N/A

-40 11 c STEAM 2530 (1) 311 STEAM (1) 2670 324 STEAM -48 609 103,675 N/A *

-60 11 c STEAM 2570 (1) 325 STEAM (l) 2693 664 326 STEAM -48 89,538 N/fl

-60 11 c STEAM 2500 (1 ) 333 STEAM (1) 2697

  • 328 STEAM +48 196 98,963 N/A

-60 11 c STEAM 2527 (l) 311 STEAM (1 ) 269D 676 89,538 N/A N/A Not applicable NOTES:

(1)

All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests, the initiation temperature was the saturation temperature.

(2)

(3)

The reµorted values are the maximum induced bending monents on the valve discharge flange during opening or closing.

The lower ring setting was intended to be -6. The actual setting was between -13 and +11.

  • The valve was disassembled, inspected, and refurbished as required for representative test performance.

EPRl/CE SAF~VE TEST DATA TABLE 3.1.l.b (Con't)

"AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE DRESSER.31739A SAFETY VALVE CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST VJ.L VE RJNG  :~LET NO. TYPE SETTINGS PI PING IN TANK 1 AT VP1LVE INLET PEAK PEAK INDUCED (2) MAX. STEADY TANK 1 BACK- BENDING MOMENT LIQUID FLOW UPPER MIOOLE LOWER CONFIG. FLUID PRESS. TEMP. PRESS. RATE FLUID TEMP. PRESS. PRESS. OPENING/CLOSING (GPM)

( PSIA) (OF) (PSI/SEC) (OF) (PSIA) (PSIA) (IN. LBS.)

1003 . STEAM -48 -60 0 D STEAM 2460 (l) 2.3 STEAM (l ) 2460 220 145,625 N/A

  • 1005 STEAM -48 -60 0 D STEAM 2425 (l) 248 STEAM (l ) 2665 550 163, 100 N/A
  • 1008 STEAM -48 -80 11 D STEAM 2446 (l ) 275 STEAM (l) 2680 617 64,075 N/A 1011 STEAM -48 -60 5 D STEAM 2478 (l ) 286 STEAM (l ) 2676 596 241,738 N/A 1012 STEAM -48 -40 3 D STEAM 2490 ( l) 309 STEAM (l ) 2665 564 69,900 N/A
  • 1016 LS -48 -40 3 D STEAM 2595 (l ) 3.4 WATER 300 2595 392 186,400 N/A l 017 LS -48 -40 3 D STEAM 2531 (l) 315 WATER 84 2685 191 186 ,400 N/A
  • 1018 STEAM -48 -40 11 D STEAM 2455 (l) 308 STEAM (1) 2657 570 87,375 N/A w *1021 LS -48 -40 11 I D STEAM 2582 (l ) 329 WATER 104 2698 586 157,275 N/A

...... 1025 LS w -48 -40 11 D STEAM/ 2525 (1) 2.0 WATER 104 2536 781 157,275 TRAJlS ~!ATER 2008 1027 WATER -48 -40 11 D WATER 2350 621 2.4 WATER 618 2363 580 131'063 2492

  • 1030 WATER -48 -40 11 D WATER 2408 522 l.8 l4ATER 515 2458 640 87,375 (3)
  • ll04a STEAM -48 -40 11 c STEAM 2550. (1) 316. STEAM (l) 2720 600 230,913 N/A b STEAM 2240 0.1 STEAM (l ) 2240 94 1107 TRANS -48 -40 11 c STEAi!/ 2489 (l) 2.8 STEAM (l ) 2489 725 226,200 2040 WATER 1110 WATER -48 -40 11 c WATER 2521 608 2.3 WATER 570 2521 500 169,650. 1506 1112 WATER -48 -40 11 c WATER 2387 513 3.1  !~ATER 493 2393 290 158,340 1130
  • 1114 WATER -48 -40 11 c WATER 2470 414 3.2 WATER 407 2749 211 84,825 1243 N/A Not applicable NOTES:

(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steanVw~tPr tr~nsitio~ test~ t~e initiation te~~er~ture w~s the saturation temrerature.

(2) The reported values are the ~aximum induced bending moments on the valve discharqe flange during ooen1ng or closin~.

(3) Unstable conditions precluded reliable measurement.

  • The valve was disassembled, inspected, and refurbished as required f
  • or representative test performance.

EPR!/CE SAF VE TEST DAT.:.

T/lllLE 3.1.1.c VALVE TRANSIENT ANO LEAKAGE PERFORMANCE OATA FOP Tµ~

DRESSER 31739A SAFETY VALVE PRE-TEST VALVE LEAKAGE VALVE OPENING ANO CLOSING NOMINAL NOMINAL POST-TEST VALVE LEAKAGE VALVE VALVE LEAKAGE TANK 1 NOMINAL NOMINAL TEST TEST INITIAL OPENING OPENING OPENING PRESS.

MEDIA INLET INLET RATE OPEN ING "POP" VALVE V.OLVE LEAKAGE NO. TYPE PRESS. TEMP. SIMMER "POP" AT VALVE % BLOWOOWN VALVE MEDIA INLET HILET RATE (GPM) PRESS. PRESS. TIME TIME CLOSURE (PS IA) (OF) (PSIA) STABILITY PRESS. TEMP. (GPM)

(PSIA) (SEC) (SEC) (PSIA) (PSIA) (OF) 302 STEAM STEAM 2325 SAT 0.0 2483 2482 .0088 .029 304 STEAM STEAM 2340 7.0 Stable STEAM 2298 2300 SAT 2526 2526 SAT 0.0 306 .0034 .040 2370 5.8 Stable STEAM STEAM 2292 SAT o.o STEAM 2310 SAT 0.0 2557 2557 .004 .026 2352 308 STEAM STEAM 2300 6.5 Stable STEAM 2296 SAT SAT 0.0 2547 2549 .004 0.0 310 .034 2393 4.9 Stable STEAM STEAM 2300 SAT 0.0 STEAM 2296 SAT 0.75 2557 2557 .005 .025 2337 312 STEAM STEAM 2311 7. l Stable STEAM 2300 SAT SAT 0.0 2529 2533 .003 0.0 314 STEAM .034 2393 4.9 Stable STEAM STEAM 2308 SAT 0.0 2537 2319 SAT o.o w 2542 .007 .024 2320 7.8 316 STEAM STEAM 2300 SAT Stable STEAM 2321 SAT o.o I 0.0 2590 2590 .005 .012 I--'

318 STEAM STEAM 2187 13. l Stable STEAM 2300

  • SAT U1 2300 SAT 0.0 2483 2485 0.0 320 .006 .021 2164 14.0 Stable STEAM STEAM 2301 SAT 0.0 STEAM 2310 SAT o.o 2580 2582 .005 .015 322 STEAM STEAM 2340 7.0 Stable STEAM 2303 SAT 2300 SAT o.o 2530 2535 .005 . 015 2237 11 . 1 0.05 324 STEAM STEAM 2300 SAT Stable STEAM 2345 SAT (). 17 0.0 2570 2572 .006 .013 326 STEAM 2200 12.6 Stable STEAM 2304 STEAM 2300 SAT 0.0 2500 S."T 0.0 2502 .006 .012 2092 16.9 328 STEAM STEAM 2300 SAT Stable STEAM 2300 SAT 0.0 0.0 2527 2530 .007 .016 2260 10.2 Stable STEAM 2300 SAT 0.0

EPRl/CE '.> LVE TEST DATA

.1.1.c (Can't)

VALVE TRANSIENT ANO LEAKAGE PERFORMANCE DATA FOR THE DRESSER 31739A SAFETY VALVE PRE-TEST VALVE LEAKAGE VALVE OPENING ANO CLOSING NOMINAL NOMINAL POST-TEST VALVE LEAKAGE VALVE VALVE TANK 1 : - ' - - - - ' - - - - - - - -

TEST TEST LEAKAGE INITIAL OPENING OPENING OPENING NOMINAL NOMINAL MEDIA INLET INLET RATE OPENING PRESS. VALVE VALVE LEAKAGE NO. TYPE PRESS. "POP" SIMMER "POP" AT VALVE % BLOWDOWN VALVE TEMP. (GPM) PRESS. PRESS. MEDIA INLET INLET RATE

{ P) rAI fOF\ ,,,,.,."' TIME TIME CLOSURE STAB rt. ITV r.)11-\ 'PSiA' s1:c* SEC PP~SS. TEMP. (GPM)

(PSIA) (PSIA) (OF) 1003 STEAM STEAM 2300 SAT 0.5 2460 2460 . 011 . 015 1005 STEAM STEAM 2323 7.7 Stahle STEAM 2285 2285 SAT 0.5 2425 2431 SAT 0.5

.014 . 016 (4) 1008 STEAM STEAM 2287 SAT (4) Chatter (6) STEAM 2285 SAT 0.0 0.23 2446 2450 .0076 . 014 1011 STEAM STEAM 2160 14;2 Stable STEAM 2290 2300 SAT 0.0 2478 2482 SAT 2.5 1012 .008 .016 2191 13.0 STEAM STEAM 2285 SAT Stable STEAM 2302 SAT 0.18 0.0 2490 2495 .008 1016 .021 2248 10.7 Stable STEAM LS WATER 2284 101 o.o 2595 2280 SAT 0.36 2594 0.368 .007 2266 10.0 1017 LS WATER 2300 96 Stable STEAM 2300 SAT 0.32 0.0 2531 2678 .632 .024 1018 STEAM STEAM 2168 13. 9 Stable (3) STEAM 2278 SAT 2300 SAT 0. 15 2455 2458 0.17 1021 .008 .024 2211 12.2 Stable STEAM w LS WATER 2303 290 0.0 2582 2300 SAT 0.28 I 2656 .279 .007 2177 13. 5 I-' 1025 LS TRANS WATER 2285 172 Stable (3) STEAM 2300 SAT 0.0

'-J 0.0 2525 2535 5.37 .011 1027 WATER WATER 2166 14.0 Stable (3) WATER 2295 317 2295 317 0.0 2350 2.150 0.0

.010 .026 2032 19.3 1030 WATER WATER 2280 515 Stable WATER 2000 (2) 0.0 0.0 2408 2382 .128 N/A (4) (4) Chatter (2) 1104a (2) (2) (2)

STEAM STEAM 2300 SAT 0.0 2550 2550 .004 .013 2238 11 .0 Stable {l) STEAM <2230 b SAT 1. 3 2240 2227 11. 5 Stable (l) STEAM l. 3 1107 TRAl1S srn 2280 SAT 0.0 2489 2489 .009 .)ll 8 2038 19. 1 Stable 2280 lllO HATE'l WATER 2298 SAT .15 610 0.0 2521 2521 . 01 .043 2096 16.8 Stable l4ATER 2285 615 1112 l*IATER ~IATER 2287 544 'L '1 0.0 2387 2391 2.00 N/11 1114 2208 12.3 Stable WATER 2290 535 0.0 WATER WATER 2275 411 0.0 2470 2551 37 N/A ( 5) (5) Stable WATER 2285 410 0.0 N/A Not Applicable NOTES:

(1) The value experienced low amplitude chatter for approximately 5 sec following each closure.

( 2) No measurement was taken. *

(3) The valve fluttered and/or chattered during loop seal discharge. The valve stabilized on steam.

(4) The test was terminated ~ihen the valve Has manually opened to stop chatter, interfering with this measurement.

(5) This test was terminated when the valve did not relieve the inlet pressure.

(6) The valve chattered on closure.

  • EPR l /CE VE TEST DATA TABLE 3.1.1.d

'ML Vt ~L0W Rf,il rEKtUKMfl~Lt Uf\ If\ t UK IHt.

DRESSER 31739A SAFETY VALVE CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% .~CCUMULATION ( 1) LIQUID FLOW MEASUREMENT BASED ON BASED ON BASED Of:

TANK PRESSURE tl/\SED ON VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE TEST TEST %RATED %RATED %RATED %RATED TANK CONDITIONS STEADY NO. TYPE  % RATED rRATrD -ntATED %RATED PRESS. TEMP.

LIFT STEAM LI FT STEAM LIFT STEAM LIQUID  % RATED FLOW LIFT STEAM (PSIA) (OF) FLOW LIFT FLOW FLOW FLOW (GPM) 302 STEAM N/A N/A N/A N/A N/A N/A N/A N/A 304 STEAM 56 N/A N/A N/A N/A 78 44 60 ( 2) (2) 306 59 83 N/A N/A N/A N/A STE1~M 60 84 61 86 73 l 07 73 308 STEAM 107 N/A N/A N/A N/A 30 114 30 44 45 67 (2) (2) N/A N/A N/A 310 STEAM 69 98 72 N/A 103 77 114 (2) (2) 312 STEAM 18 N/A N/A N/A N/A 27 18 27 40 60 314 41 61 N/A N/A N/A N/A STEAM 79 110 80 113 82 118 (2) (2) N/A 316 STEAM 110 122 N/A N/A N/A 110 124 110 128 111 318 STEAM 130 N/A N/A N/A N/A w lll 122 110 124 111 128 (2) (2) N/A

,_.I 320 STEAM 44 64 N/A N/A N/A 44 64 104 127 l.O 322 (2) (2) N/A N/A N/A N/A STEAM 78 113 104 122 110 129 (2) (2) N/A 324 STEAM 110 122 N/A N/A N/A 111 125 112 129 326 112 130 N/A N/A N/A N/A STEAM lll 122 112 124 112 129 112 130 N/A 328 STEAM 93 N/A N/A N/A 118 l 04 122 112 129 117 131 N/A N/A N/A N/A NOTES:

(1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.

(2) The appropriate measurement conditions were not achieved.

  • EPR!/CE se,ALVE TEST DATA TABLE 3.1.1.d (Can't)

VALVE FLOW RATE PERFORMANr.F OATA FOR THE DRESSER 31739A SA.FETY VALVE CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ACCUMULATION ( 1) LIQUID FLOW MEASUREMENT BASED ON BASED N: BASED or: BASED ON TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE TANK CONDITIONS STEADY TEST TEST %RATED  % RATED  % RATED  % RATED  % RATED  % RATED %RA1ED  % RATED PRESS. TEMP. LIQUID  % RATED NO. TYPE LIFT STEAM LIFT STEAM LIFT ~TEAM LIFT )TEAM (PSIA) (OF) FLOW LIFT FLOW FLOW FLOW FLOW (GPM) 1003 STEAM N/A N/A N/A N/A rl/A N/A N/A N/A N/A N/A N/A N/A 1005 STEAM 63 87 74 104 106 121 (3) (3) N/A N/A N/A N/A 1008 STEAM 88 111 112 1a 120 124 (3) ( 3) N/A N/A N/A N/A 1011 STEAM 87 111 98 123 118 124 (3) (3) N/A N/A N/A N/A 1012 STEAM 72 99 109 122 119 125 (3) (3) N/A N/A N/A N/A 1016 LS N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1017 LS 120 120 115 116 120 126 (3) (3) N/A N/A N/A N/A 1018 STEAM 80 107 114 116 (3) (3) (3) (3) N/A N/A N/A N/A w 1021 LS 89 110 111 115 121 124 (3) (3) N/A N/A N/A N/A I

N

...... 1025 LS TRANS N/A N/A N/A N/A N/A N/A N/A N/A 2382 649 2492 97 1027 WATER N/A N/A N/A N/A N/A N/A N/A N/A 2307 622 2350 99 1030 WATER N/A N/A N/A N/A N/A N/A N/A N/A (2) (2) (2) (2) l 104a STEAM 77 107 80 112 90 121 112 129 N/A rl/A N/A N/A 1107 N/A N/A N/A N/A N/A N/A N/A N/A 2346 647 2040 84 lllO WATER N/A N/A N/A N/A N/A N/A N/A N/A 2302 603 1506 39 lll 2 WATER N/A N/A N/A N/A N/A N/A N/A N/A 2254 539 1130 28 1114 WATER N/A N/A N/A N/A N/A N/A N/A N/A 2619 401 1243 26 N/A Not Applicable NOTES:

g\

(3)

During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.

Unstable conditions precluded reliable measurement.

The appropriate measurement conditions were not achieved.

3.2 DRESSER SAFETY VALVE MODEL 31709NA 3.2.l Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Dresser 31709NA safety valve model at the EPRI/CE PWR Safety* and Relief Valve Test Facility. The valve was tested on both a short (test series 600 and 1300, configuration B) and a long (test series 200, configuration A) inlet piping configuration. The following is the list of tables that contain the safety valve information/data for these tests:

Jable Description Table Number Safety Valve Description and Inlet Piping Configuration 3. 2. 1. a "As Tested" Text Matrix 3. 2. l. b Valve Transient and Leakage Performance Data 3.2. l.c Valve Flow Rate Performance Data 3.2. l.d 3.2.2 Principal Observations 3.2.2.a. Short Inlet Pipe Configuration (Configuration B). A total of fourteen tests was performed on the Dresser 31709NA safety valve with a short inlet pipe configuration. Each of the tests were performed with the valve middle and lower ring positions established by Dresser based on previous EPRI/CE test experience obtained on the Dresser 31739A safety valve. The valve ring positions were not necessarily typical of PWR plant ring p0sitions. The principal observations for these tests are as fo 11 ows:

Steam Tests A total of eight steam tests was performed with high and low ramp rates, varying back pressures from 174 to 530 psia and three different middle ring positions. Neither the valve upper or lower ring positirn was changed during these tests. For all of these tests, the valve opened 3-23

within +3% of the V<ilvl~ i-Jesi~111 *s1~t presstffe und exhibited ~lable performance. In tests wilere the inlet pressure accumulated to 6% above the valve design set pressure, the valve achieved rated lift. Valve bJowdown varied depending on the position of the middle ring and the back pressure.

Generally, the valve blowdown decreased as the back pressure increased and as the middle ring was adjusted to higher test positions. Slowdown ranged from a maximum of 14.2% to a minimum of 7.5%.

Transition Tests Two steam-to-:water transition tests with an intermediate back pressure (approximately 400 psia) were performed using the highest and lowest middle ring positions of the steam tests. For both tests, the valve opened within +3% of the valve design set pressure and exhibited stable performance. The valve blowdown ranged from 17.0% to 18.5%.

Water Tests Four water tests were performed with an intermediate back pressure at nom-inal water temperatures of 650, 550 and 400°F.

  • During the two 650° water tests performed which used the highest and lowest middle ring positions of the steam tests, the valve opened at system pressures of 2393-2412 psia and exhibited stable performance. Valve blowdowns ranged from 16.3 to 22.6%.

The two -subsequent water tests (550, 4000F) were performed using the highest middle ring position. For both tests, the valve opened at a system pressure within ~3% of the valve design s~t pressure. During the 550°F water test, the valve opened, had stable behavi6r and closed with 4.0%

blowdown.

Dllring the 400°F water test, the valve opened at 2558 psia and exhibited five partial lift cycles over a period of three seconds. The valve then 3-24

opened and chattered. Three seconds later in the transient, the valve stopped chattering without manual actuation and then closed. After the transient, a ste~m leakage test was attempted. The valve partially

  • opened at which p9int the leak test was terminated.

Valve Inspection Results After the 4000F test, the valve was disassembled and inspected. Galled guiding surfaces and several damaged internal parts were found.

For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage.

.:.2.2.b. Long Inlet Pipe Configuration (Configuration A). A high ramp rate, low back 1*ressure steam test was performed with the valve mounted on a loop seal configuration
  • .. nd the loop seal drained. The safety valve opened within .:'.:.3% of the valve design set rjressure and the transient continued for a total time of 122 seconds. The valve chattered during most of the test duration and then closed at a pressure of 2010 psi a.

~*everal minutes after closure, the valve re-opened at a pressure noted by the loop ciperator of approximately 2150 psi a. The valve chattered during the 10 second duration of the transient and then closed at a pressure just below 2150 psia.

Mter the test, a leak test was performed at an inlet pressure of about 2100 psia. The valve leakage measured was J.54 gpm. The valve was then dissassemb.led and inspec-ted. Galled guiding surfaces and several damaged internal parts were found .

  • 3-25
    • ,.* ,' ,j, ,,*,. * *, }'lt*_'.,* __:_,*~-~\;,*1l_ *. _L'..:_ '.~*'II *~ ,**

EPRI/CE SAFET1 _VE TEST PROGRAM TABLE 3. 2 . 1. a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION DRESSER 31709NA Valve Descripiion Inlet Piping Configuration "Au Length, in. I. D., in.

Manufacturer Dresser Industries Type Nozzle 17 6.813 Spring Loaded Safety Valve Model No. 31709A Serial No. Venturi 38 6.813 BQ07681 Drawing No. 4CP-2332 Rev 11 Pipe 6 6.813 Body Size (inlet/outlet) 6 in./- -in.

Bore Area 4.34 in.2 Reducer 6 6.813/4.897 Orifice Designation N Loop Sea*!

w I

Design Set Point Pressure 2500 Straight 48 4.897 N psig Bends 2 Bends 180°

'-J 9" radius Design Bl owdown __5_ _-'percent Inlet Flange 11 4.897 Rated Flow 507918 1b/hr. Rated Lift 0.588 in.

Internals Type: Not Applicable Inlet Piping Configuration "B" Length, in. I.D., in.

Ring Setting Reference Position The ring setting positions refer to the number of Nozzle 17 6 .813 notches relative to the following surfaces:

Venturi 38 6.813 Upper Ring - top holes in the guide Pipe Middle Ring- seat plane 6 6.813 Lower Ring - seat plane Reducer 6 6.813/4.897 Inlet Flange 11 4.897

EPRI/CE SAFETY TABLE 3.2. l.b TEST DATA "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE DRESSER 31709NA SAFETY VALVE CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST VALVE RING INLET NO. IN TANK l AT VALVE INLET PEAK PEAK INDUCED (2)

TYPE SETTINGS PIPING MAX. STEADY UPPER MIDDLE LOWER CONFIG. TANK 1 BACK- BENDING MOMENT LIQUID FLOW FLUID PRESS. TEMP. PRESS. RATE FLUID TEMP. PRESS.

(oF) PRESS. OPEN ING/ CLOS ING (GPM)

(PSIA) (PSI/SEC) ("F) (PSIA) {PSIA) (IN. LBS.)

  • ~01 STEAM -48 +34 -20 A STEAM 2486 (1) 400 STEAM (1) 2680 (3) 137,500 N/A
  • 603 STEAM -48 -60 0 B STEAM 2505 (1) 2.9 STEAM ( 1) 2505 174 CJl ,000
  • 606 STEAM N/A

-48 -60 0 B STEAM 2503 (1 ) 296 STEAM (1 ) 2695 195 91,000 N/A 611 STEAM -48 -60 0 B STEAM 2530 {1) 322 . STEAM (1) 2697 358 95,550 N/A 614 STEAM -48 -40 0 B STEAM 2546 w (1) 317 STEAM ( 1) 2686 354 100, 100 N/A I

615 STEAM -48 -20 0 B STEAM 2568 (l)

N

\.0 317 STEAM (1) 2639 326 100, 100 N/A 618 STEAM -48 -60 0 B STEAM 2536 (l) 288 STEAM (1 ) 2680 530 91,000 N/A

  • 620 STEAM -48 -20 0 B STEAM 2540 (l ) 317 STEAM (l) 2667 194 95,550 N/A 623 TRANS -48 -60 0 B STEAM/ 2545 (1) 3.0 STEAM (1 ) 2545 418 100, 100 3801 WATER 625 WATER -48 -60 . 0 B WATER 2412 603 3.0 WATER 573 2420 338 91 ,000 2715 628 TRANS -48 -20 0 B STEAM/ 2530 (l) 2.7 STEAM (1) 2530 386 81, 900 3305 WATER
  • 630 WATER -48 -20 0 B WATER 2393 625 2.5 WATER 589 2393 336 100, 100 3735
  • 1305 STEAM -48 -20 0 B STEAM 2530 (1) 308 STEAM (1) 2652 345 200,200 N/A 1308 WATER -48 -20 0 B WATER 2487 562 1.8 WATER 535 2513 145 473,200 1436
  • 1311 WATER -48 -20 0 B WATER 2558 415 2.6 WATER 429 2558 100 445,900 (3)

N/A Not applicable NOTES:

(1) All tests were initiatP.d at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests, the initiation temperature was the saturation temperature.

(2) The reporteti values are the maximum bending moments on the valve discharqe flange during opening or closinq.

(3) Unstable conditions precluded reliable measurement.

  • The valve was disassembled, inspected, and refurbished as required for representative test performance.
  • EPRl/CI:. S ALVI:. 11:.ST UAIJl1 TABLE 3.2.1.c VALVE TRANSIENT AND LEAKAGE PERFORMANCE DllTA FOR THE DRESSER 31709NA SAFETY VALVE
  • NOMiNAL VOLV~

- - -PRF-TF5T LEAKAG[

NOMI NA-L- - - - VALVE OPENING AND CLOSING VALVE VALVE LEAKAGE TANK I POST-TEST VALVE LEAKAGE TEST TEST MEDIA INLET INITIAL OPENING OPENING OPENING NOMINAL NOMINAL NO. INLET RATE OPENING "POP" PRESS.

TVD~

-'~[~~. IEi*i?. S!MMFR nofJp" .nT V/\L VE % BLOWDDHN VALVE VALVE LEAKAGE (GPMj PRESS. PRESS. VALVE MEDIA INLET INLET RATE (PSIA) OF) TIME TIME CLOSURE PSIA PSIA SEC STABILITY PRESS. TEMP. (GPM)

SEC (PSIA) 201 STEAM STEAf.1 (PSIA) (OF) 2300 660 < 0. l 2486 2489 0.0ll 0.013 2010 20.2 chatter 603 STEAM 2091 646 fl.54 STEAM STEAM 2298 Sat 0.9 2505 2505 0.004 606 STEAM STEAM 2283 0.012 2160 14.2 611 Sat o.o 2503 2509 0.005 s table STEAM 2286 Sat l.O STEAM STEAM 2285 Sat 0.015 2166 14.0 0.0 2530 2538 stable STEAM 2200 Sat 614 STEAM STEAM 0.007 0.017 2290 l. l 2293 Sat . 0.0 2546 9.0 stable STEAM 615 STEAM 2551 0.007 0.016 2290 Sat l.O STEAM 2294 Sat o.o 2294 8.8 stable 618 2568 2575 0.006 STEAM 2300 Sat l. 8 w STEAM STEAM 2300 0.018 2327 7.5 I Sat 0.0 2486 2486 stable STEAM 2285 Sat w 620 STEAM STEAM 0.007 0.015 2277 1.5 I-' 2300 Sat 0.0 2540 9.5 stable STEAM 623 TRANS 2540 0.005 2285 Sat 2.1 STEAM 2286 0.017 2227 11. 5 Sat 0.0 2545 2545 stable STEAM 2300 Sat 0.006 0.015 l. 7 2052 18.5 stable 625 WATER WATER STEAM 2285 Sat 0.67 2300 Sat 0.37 2412 628 TRANS 2412 0.010 0.035 STEAM 2281 Sat 2108 16. 3 stable.

0. l 2530 2530 0.006  !~ATER 2300 Sat o.o 0.017 2090 17. 0 630 WATER stable WATER 2290 Sat WATER 2296 Sat 0.47 0.36 2393 2393 0.011 0.037 1950 22.6 stable HATER 2300 Sat 1303 STEAM STEAM 0.09 2280 Sat 0.0 2530 l30G WATER 2535 0.008 0.023 2301 WATER 2300 544 0.0 8.6 stable 2487 2487 0.011 STEAM 1800 Sat 0.66 1311 WATER WATER. 2300 0.059 2398 4.7 429 o.o 2558 2558 <O.Ol (1).

stable l*IATER 2300 544 0.0 (2) (2) chatter (3) (2) (2) (2) (2)

N/A Not applicable HOTES:

(1) Unstable conditions precluded reliable measurement.

(2) These data were not available (3) The valve opened, chattered for approximately 3 seconds and then stopped chattering for the remainder of the test.

EPRI/CE SAFE VE TEST DATA TABLE 3.2.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE DRESSER 31709NA SAFETY VALVE CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ACCUMULATION (1) LIQUID FLOW MEASUREMENT BASED ON BASED ON BASED O~: BASi:.D uii TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE MAX.

TEST TEST %RATED %RATED %RATED VALVE INLET PRESSURE TANK CONDITIONS STEADY .

NO. %RATED  % RATED %RATED -nm TED %RATED PRESS. TEMP.

TYPE LIFT STEAM LIFT STEAM LIFT ,_ STEAM LIQUID 1: RATED FLOW LIFT STEAM (PSIA) (Of) FLOW LIFT FLOW FLOW FLOW (GPM) .

.201 STEAM (2) (2) (2) (2) (2) (2) (2) (2) N/A N/A N/A N/A

.603 STEAM N/A N/A N/A N/A N/A N/A N/A N/A 606 STEAM 109 125 N/A N/A N/A N/A 109 125 109 130 109 611 STEAM 104 131 N/A N/A N/A N/A 124 105 124 107 130 614 STEAM 107 130 N/A N/A N/A N/A 98 123 99 124 107 615 130 107 132 N/A N/A STEAM 83 117 84 N/A N/A 119 (3) (3) (3) 618 STEAM 101 (3) N/A N/A N/A N/A w 123 100 123 108 130 I 620 STEAM 108 130 N/A N/A N/A N/A w 107 124 107 126 w 107 130 (3) (3) N/A 623 TRANS N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 2372 653 3801 105 625 WATER N/A N/A N/A N/A N/A N/A N/A N/A 628 TRANS N/A 2320 603 2715 38 N/A N/A N/A N/A N/A N/A N/A 2343 647 3304 73 630 WATER N/A N/A. N/A N/A N/A N/A N/A N/A 2335 62S 3735 62 1305 STEAM 79 114 81 116 (3) (3) (3) (3) 1308 WATER N/A II/A N/A N/A N/A N/A N/A N/A N/A N/A 1311 WATER N/A N/A 2429 562 1436 26 N/A N/A N/A N/A N/A N/A N/A NIA (2) (2) . (2) (2)

N/A Not applicable NOTES:

(l) During the valve closing cycle. The valve inlet pressure corresponds to stagnation press.ure.

(2) Unstable conditions preclude reliable measurement.

(3) The appropriate measurement conditions were not achieved.

I I ~ I

  • !.J 3.3.l CROSL3Y Hl3-L3P-86, JKG (SHl\M INTERNl\LS)

Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Crosby HB-BP-86 3K6 (Steam Internals) safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The valve was tested on both a short (test series 400, configuration E) and a long (test series 500, configuration F) inlet piping configuration. The following is the list of tables that contain the safety valve information/data for these tests:

Table Description Table Number Safety Valve Description and Inlet Piping Configuration 3. 3. l. a "As Tested" Test Matrix 3. 3. l. b Valve Transient and Leakage Performance Data 3. 3. l .c Valve Flow Rate Performance Data 3. 3. l .d 3.3.2 Principal Observations 3.3.2.a. Short Inlet Pipe Configuration (Configuration E). Fourteen tests were performed on the Crosby 3K6 (Steam Internals) safety valve mounted on a short inlet pipe configuration. The principal observations for each type of test are as follows:

Steam Tests Tests 406 through 411 were high and low ramp rate and high back pressure steam tests. In all of these tests, one set of valve ring positions was maintained which was the manufacturer's recommended ring position. With this ring position the valve opened within !3% of the valve design set pressure, achieved a lift position which was 96% of rated lift when the pressure accumulated to 6% above the valve design set pressure and closed with 10.1-10.9% blowdown. Following these tests, rinq adjustment tests

  • 3-35

415 through 425 were performed to decrease blowdown. The final adjustment resulted in decreasing the blowdown to 8.4% with the va*lve performance re-maining stable. In addition, the valve achieved 99 to 100% of rated lift when the pressure accumulated to 6% above the valve design set pressure.

The final ring position was maintained for the non-steam tests.

Two other steam tests, nos. 441 and 442 were perfcrmed after the water tests were completed and the valve had been refurbished. The purpo~e of the tests was to re-establish va'lve performance simi"lar to the performance obtained on steam prior to valve refurbishment. lhe r'ing positions of test No. 442 were then used for the initial long ~ipe configuration tests of the Crosby 3K6 safety valve.

Transition Test During the high back pressure, steam-to-water transition test, the valve opened within ~3% of the valve design set pressure, had stable performance 1

and closed with 8% blowdown.

Water Tests Three high back pressure water tests were performed at nominal water temp-eratures of 650°F and 550°F. For the 650°F water test, the valve cycled twice. The valve opened at pressures of 2342 and 2278 psia; For the first cycle, the valve had stable performance and closed with 13.0% blowdown.

Two 550°F water tests were performed. In the first test, no. 435, the valve opened within ~3/i. of the valve design set pressure to a partial lift position. The system pressure continued to accumulate while the valve remained in a partial lift position. The test was terminated be-cause the valve did not relieve the pressure in tank 1. In the second 550°F water test performed at similar. conditions, the valve opened and chattered. The test was terminated after the valve was manually opened to stop chattering.

3-36

  • Valve Inspection Results After each test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected. Galled guid-ing surfac1~s and several *damaged internal parts were found.

For all other inspections, the typical wear pattern observed was scratches or marks .011 the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to miminize seat leakage.

3.:l.2.b. Long Inlet Pipe Configuration (Configuration F). Six tests were performed on the Crosby HB-BP-86 3K6 (Steam Internals) safety valve mounted on a long inlet pipe co11figuration. Four of the tests were self actuation steam tests performed with a dr<~ined loop seal. The other two tests were manual actuation tests. The principal observations for the self actuation tests are as follows:

Foi three of four steam tests, the valve opened at a syst~m pressure within .:::_3% of the valve design set pressure. In test No. 506, the valve set point was established on a portable air bench device and the valve subsequently opened at a pressure of 2708 psi a.

For the tests performed with ring positions resulting in 15.6 - 15.9% blowdown, valve operation was stable and 99% of rated lift was achieved when the pressure was 6% above the valve design set point. During one test (No. 508) performed with ring positions which had resulted in 10.5% blowdown on the last Crosby 3K6 (St~am Inter-nals) short inlet piping configuration test, the valve opened and chattered. The test was terminated after the valve was manually opened to stop chattering.

Valve Inspection Results After each test which was terminated by manually open_ing the valve to stop chattering, the valve was disass~mbled and inspected. Galled guid-ing surfaces and several damaqed internal parts were found.

For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage .

  • 3-37
  • EPRI/CE SAFE~VE TEST PROGRAM TABLE 3.3. l .a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 3K6 (STEAM INTERNALS)

Valve Descri~tion Inlet Pi~in9 Configuration F" Length, in. I.D., in.

Manufacturer Crosby Valve and Gage Type Spring Loaded Safety Nozzle 17 6.813 Model No. HB-BP-86 3K6 Serial No. None Ventur-i 38 6.813 Drawing No. SK-3658-V Pipe 6 6.813 Body Size (inlet/outlet) 3 in./ 6 in.

Bore Area l. 841 in.2 Reducer 6 6.813 Orifice Designation K Loop Seal w Design Set Point Pressure Straight 54 3. 152 w

I 2485 psig Bends 4-900 6 inches radius

"° Design Blowdown percent 5 Reducer ti 3. 152/2.624 Rated Flow 212,182 lb/hr. Rated Lift 0.382 in. Inlet Flange 7 2.624 Internals Type: Steam Ring Setting Reference Position: Inlet Pi~ing Configuration 11E11 The ring setting position refers to the number of Length, in. I.D., in.

notches relative to the bottom of the ring disc. Nozzle 17 6.813 Venturi 38 6.813 Pipe 6 6.813 Reducer 10 6. 813/ 2. 624 Pipe 4 2.624 Inlet Flange 7 2.624

  • 11r1r

.""'\~

TLC'Trnn

, :_...)IL l.J Ef'RI/CC SAFE.E T.EST DATA COM3U~Tror:

TABLE 3.3.l.b

[NGIN((RING TEST MATRIX ror:: ... c.

CROSBY HB-BP-B6 3K6 (STEAM INTERNALS)

CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST VALVE RING INLET IN TANK 1 PEAK PEAK INDUCED ( 2) MAX. STEADY NO. TYPE SETTINGS PIPING AT VALVE INLET TANK 1 BACK- BENDING MOMENT LIQUID FLOW UPPER MIDDLE LOWER CONFIG. FLUID PRESS. TEMP. PRESS. RATE FLU ID TEMP. PRESS. PRESS. - OPENING/CLOSING (GPM)

( PSIA) (OF) (PSI/SEC) (OF) (P<;TA) f P<: ! n \

' * *'I ( l~L LBS.)

406 Steam -55 N/A -14 E Steam 2456 {l) 2.7 Steam (1) 2456 662 123,500 N/A 408 Steam -55 N/A -14 E Steam 2462 (l) 2.5 Ste;im (1) 2462  !;7J'. 123,500 N/A 411 Steam -55 N/A -14 E Steam 2502 (l) 286 Steam (l) 2683 60(: 114 ,000 N/A 415 Steam -35 N/A -14 E Steam 2545 (1) 300 Steam ( l) 2660 860 28,500 N/A 416 Steam -45 N/A -14 E Steam 2487 (l ) 311 Steam (l) 2700 705 19,000 N/A 419 Steam -38 N/A -14 E Steam 2510 (1) 271 Steam (l) 2717 700 19,000 N/A 422a Steam -38 N/A -14 E Steam . 2507 {l) 335 Steam (1) 2710 690 19,000 N/A w b -38 N/A -14 E Steam 2417 1.6 Steam (l) 2417 .586 N/A I

~ c -38 N/A -14 E Steam (3) (3) Steam (l ) (3) (3) N/A

......

  • 425 140 Steam -45 N/A -14 E Steam 2505 (l) 325 Steam (l) 2730 14,250 N/A
  • 428 Trans -45 N/A -14 E Steam/ 2548 (l ) 2.7 Steam ( l) 2548 854 (~) 1616 Water 431 a Water -45 N/A -14 E Water 2342 631 l.8 Water 622 2349 . 5f4 32,300 1370 b -45  :~/A -14 E Water 2273 l. 6 ~later 616 (4) (4) 'I/A 435 Water -45 N/A -14 E Water 2454 520. l. 7 Water 510 (3) (3) 24,700 493
  • 438 Water -45 tl/A -14 E Water 2447 554 2.3 Water 532 2490 700 19,000 (4)

H/A Not applicable NOTES:

(1) All tests were initiated at a nomir.al pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation temperature.

(2) Th~ reported values are the maximum induced bending moments on the valve discharge flange during opening or closing.

(3) These data were not available.

(4) Unstable conditions precluded reliable measurement.

  • The valve was disassembled, inspected, and refurbished as required for representative test performance.
  • EPRI/CE SAF.VE TESTDATA TABLE 3.3.l.b (Can't)

"AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE CROSBY HB-BP-86 3K6 (STEAM INTERNALS)

CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST VALVE RING INLET IN TANK 1 AT VALVE INLET PEAK PEAK INDUCED (2) MAX. STEADY NO. TYPE SETTINGS PIPING TANK 1 BACK- BENDING MOMENT LIQUID FLOW UPPER MIDDLE LOWER CONFIG. FLUID PRESS. TEMP. PRESS. RATE FLUID TEMP .. PRESS. PRESS. OPEN ING/CLOSING (GPM)

(PSIA) (OF). (PSI/SEC) (Of) (PSIA) (PSIA) (IN. LBS.)

~~-------

441 Steam -45 N/A -14 E Steam 2473 (l ) 289 Steam (l) . 2700 632 161,500 N/A 442 Steam -55 N/A -14 E Steam 2487 (l) 314 Steam (l) 2670 626 133,000 N/A

  • 506 Steam -55 N/A -14 F Steam 2708 (1) 4.1 Steam (l) 2709 455 59,000 N/A
  • 508 Steam -55 N/A -14 F Steam 2507 (l ) 2.6 Steam (l) 2508 515 5,900 N/A 516 Steam -115 N/A -14 F Steam 2435 (1) 2.9 Steam ( l) 2436 507 56,050 N/A
  • 517 Steam -115 N/A -14 F Steam 2465 (l) 222 . Steam (l) 2725 582 59,000 N/A w 503 Manual Actuation. Valve perfonnance data are not applicable.

I 512 Manual Actuation. Valve performance data are not applicable.

""'w" NOTES:

(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests l'lnd steam/water transition tests the initiation temnE>rature was the saturation temperature.

(2) The reµorted values are the maximum induced bending moments on the valve discharge flange during opening or closing.

  • The valve was disassembled, inspected, and refurbished as required for representative test perfonnance.
    • l:.i'Hl/LI:_ SML I Ui\ 111 VAL'*E TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE CROSBY HB-BP 3K6 (STEAM INTERNALS)

PRE-TEST VALVE LEAKAGE Vd I_ V[. 0 PEN ING AND CL C'.:.: :: :; POST-TEST VALVE cEAKAGE

NOMINAL NOMINAL TANK 1 NOM!tlAL NOP.: '*.~L VALVE VALVE LEAKAGE INITIAL OPENING OPENING OPENING PRESS. VALVE VA~,~ LEAKAGE TEST TEST MEDIA INLET INLET RATE OPEi! ING "POP" SIMMER "POP" AT VALVE  % BLOWDOWN VALVE MEDIA INLET. INL~T RATE NO. TYPE PRESS. TEMP. (GPM) PRESS. PRESS. TT~ff T!'-1E Cl n<;11[1E STABILITY PRESS. T;'.HI""'

.. r. (GPM)

I n r r,., \

, , .JJ.t'l/ I 1r...-\

r J \r:>li'\} \l'SlA) (SEC) (SEC} (PSII\) (PSIA) (0:)

406 Steam Steam 2315 Sat 0.0 2456 2456 .008 .009 2250 10. l Flutter (l) Steam 2302 Sat 0.0 408 Steam Steam 2306 Sat 0.81 2462 2462 .009 .006 2243 l 0.3 Stable Steam 2305 Sat 0. 74 411 Steam Steam 2319 Sat 0.58 2502 2505 .009 .006 2228 10.9 Stable Steam (2) (2; (2) 415 Steam Steam 2310 Sat 0.03 2545 2547 .006 .007 (4) (4) Chatter (6) Steam 2310 Sa't 0.05 416 Steam Steam 2322 Sat 0.0 2487 2490 .01 .006 2298 8. 1 Stable Steam 2322 Sat fl.O 419 Steam Steam 2295 Sat 0.0 2510 (2) (2) (2) 2370 5.2 <;t;ible (1) Steam 2301 Sat 1.2 422a Steam Steam 2288 Sat 0.0 2507 2511 . 011 .006 2408 3.7 Flutter Steam 2320 Sat 0.0 w b 2417 2417 2364 5.5 Flutter I

CJ1 c (5) ( 5) (5) (5) (5) 425 Steam Steam 2285 Sat 0.0 2505 2508 .008 .006 2292 8.4 Stable Steam 2300 Sat 0.0 428 Trans Steam 2297 Sat 0.0 2548 2548 . 005 .007 2300 8.0 Stable Steam 2296 Sat 0.08 431 a Water Steam 2284 Sat . 0.03 2, * ..,

~"'-

2342 .005 .010 2177 13.0 Stable Steam 2278 Sat 0.05 b 2278 ( 5) (5) (5) 435 Water Steam 2210 550 8.4 2454 2454 .010 N/A ( 5) (5) ( 5) Steam 2300 52Z >15 438 Water Steam 2321 Sat 0.0 2447 (3) (3) NJA (3) (3) Chatter (2) (2) (2) (2)

(l) Valve stability was inferred from the inlet pressure stability.

(2) No measurement was taken.

(3) Unstable conditions precluded reliable measurement.

(4) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.

(5) These data were not available.

(6) The valve chattered on closure.

ll'I< I/ Lt ~/\I L VI:. I b I UI\ 11\

.3.1.c (Con't)

VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE CROSBY HB-BP 3K6 (STEAM INTERNALS)

DD!::-TEST VALVE LEAVAGE VAL VE OPENING AND CLOSING POST-TEST VALVE LEAKAGE NOMINAL NOMI NA[ TANK 1 NOMINAL NOMINAL VALVE VALVE LEAKAGE INITIAL OPENING OPENING OPENING PRESS. VALVE VALVE LEAKAGE TEST TEST MEDIA INLET INLET RATE OPENING "POP" SIMMER "POP" AT VALVE % SLOWDOWN VALVE MEDIA INLET INLET RATE NO. TYPE PRESS. TEMP. (GPM) PRF<;<;. ppr:-<:<; T!~E TIME CL0'.:!.!RE STABILITY PRESS. TEMP. (GPM)

(PSIA) (UF) (PSIA) (PSIA} (SEC} (SEC} (PSIA) (PSIA) (OF) 441 Steam Steam 2320 Sat 0.0 2473 2476 .011 .008 2407 3.7 flutter Steam 2325 Sat 0.0

~~2 Steam Steam ]2238 Sat 0.0 2487 2489 .007 .008 2240 10.5 stable Steam 2314 Sat 0.24 506 Steam Steam 2302 Sat 0.0 2708 2708 .007 .006 2330 6.8 flutter Steam 2300 Sat 0.0 508 Steam Steam 2276 Sat .74 2507 2506 .009 .008 (1) (1) chatter (2) Steam 1897 Sat .6 516 Steam Steam 2270 Sat .05 2435 2435 .0070 .007 2106 15.9 stable Steam 2255 Sat .02 517 Steam Steam 2285 Sat 0.0 2465 2465 .008 .008 2113 15.6 stable Steam 2309 Sat 0.0 503 Manual Actuation. Valve performance data are not applicable.

w I 512 Manua 1 Actuation. Valve performance data are not applicable .

-....J (1) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.

(2) The valve chattered on closure.

EPRI/CE LVE TEST DATA TABLE 3.3. l.d VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86-3K6 (STEAM INTERNALS)

CONDITIONS AT 3% ACCUMULATION ( 1) CONDITIONS AT 6% ACCUMULATION ( 1)

BASED LJN ___ -- LIQLJ.IO FLOW MEASUREME~H s;;sEJ ot: ... BASED-ON _____ -*

TANK PRESSURE BASED ON MAX.

TEST VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE TEST  % RATED  % RATED  % RATED  % RATED  %- RATED TANK CONDITIONS STEADY NO. TYPE LIFT STEAM  % RATED  % RATED  % RATED PRESS. TEMP. LI QU ![l  % RATED LIFT STEAM LIFT STEAM LIFT STEAM FLOW FLOW (PSIA) (Of) FLOW LIFT FLOW FLOW (GPM) 406 Steam N/A N/A N/A N/A N/A M/A N/A N/A N:. NA 408 Steam N/A NA NA N/A N/A N/A N/A N/A N/A N/A NA NA NA '"....

411 Steam 96 122 g5 122

  • (

96 128 96 129 NA NA NA Nil.

415 Steam 101 118 102 121 1')4 125 104 127 NA NA 416 Steam 109 NA NA 120 109 122 110 126 110 127 NA NA NA NA 419 Steam (2) 117 (2) 119 (2) 123 (2) 124 NA NA NA ~iA 422<! Steam 99 120 99 120 99 126 99 126 NA NA NA 'til w b NA NA NA NA I

NA NA NA NA NA NA NA 'IA 4':> c NA NA NA NA l.O NA NA NA NA NA NA NA ~A 425 Steam 99 120 99 121 99 126 99 126 NA NA NA NA 428 Trans NA NA NA NA NA NA NA NA 2430 648 1616 78 43la Water NA NA NA NA NA NA NA NA 2284 630 1370 57 b NA NA NA NA NA NA NA NA NA NA NA 'lA 435 Water NA NA NA NA NA NA NA NA 2575 526 493 6 438 Water NA NA NA NA NA -NA NA NA ( 3) ( 3) ( 3) ( 3)

N/A Not Applicable NOTES:

(1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.

(2) No measurtment 11as taken.

(3) Unstable conditions precluded reliable measurement.

EPR!/CE

  • VE TEST DATA TABLE 3.3.1.d (Can't)

VALVE FLOW RATE PERFORMANCE DATA FOR THE CORSBY HB-BP-86 3K6 (STEAM INTERNALS)

CONDITIONS AT 3% ACCUMULATION ( 1)

CONDITIONS AT 6% ACCUMULATION ( 1)

BASED ON BASED ON LIQUID FLOW MEASUREMENT TA"NK PRESSURE BASED ON BASED ON TEST TEST VALVE INLET PRESSURE TANK PRESSURE MAX.

% RATED  % RATED  % RATED  % RATED VALVE INLET PRESSURE TANK CONDITIONS NO. TYPE LIFT  % RATED  % RATED TRATrn xm- STEADY STEAM LIFT STEAM LIFT PRESS. -TEMP. LIQUID ~  : ! ~rn FLOW STEAM LIFT STEAM (PSIA) (Of)

FLOW FLOW FLOW ~~T FLOW (GPM) 441 Steam 98 123 98 120 99 442 Steam 127 98 126 98 121 g9 125 N/A N/A N/A t~_* .!

506 99 127 (2)

Steam N/A N/A (2) N/A N/A N/A N/A N/A N/A h .!

508 Steam N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A t~ ..:,

516 N/A N/A N/A N/A Steam N/A N/A N/A N/A N/A N/A ,.~-. ~

N/A N/A N/A 517 Steam 99 N/A N/A N/A N/A 103 99 104 99 N/A I

\ -*

109 99 103 N/A 503 Manual Actuation. N/A N/A \ ~

Valve performance data are not applicable.

w 512 Manual Actuation.

I Valve perfonnance data are not applicable.

tJ1 N/A Not Applicable NOTES:

(1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.

(2) The appropriate measurement conditions were not achieved.

  • 3.4 CROSBY HB-BP-86, 3K6 (LOOP SEAL INTERNALS)
3. 4 .. l Valve Description and Inlet Piping Configuration Data, "As Tested"Test Matrix and Valve Performance Data.

Tests were performed on the Crosby HB-BP-86 3K6. (Loop Seal Internals) safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The v~lve model was tested on both a short (test series 400, configuration E) and a long (test series 500, configuration F) inlet piping configuration. The following is the list of tables that contain the safety valve informdtion/data for these tests:

Table Description Table Number Safety Valve Description and Inle.t Piping Configuration 3. 4. l. a "As Tested" Test Matrix 3 .4. l. b Valve Transient and leakage Performance Data 3. 4. l. c Valve Flow Rate Performance Data 3. 4. l. d 3.4.2 Principal Observations 3.4.2.a. Short .Inlet Pipe Configuration (Configuration E). One steam test was performed on the Crosby HB-BP-86 3K6 (Loop Seal Internals) safety valve mounted on a short inlet pipe configuration (test No. 403). The test was a low ramp rate, high back pressure steam test with a drained loop seal. Prior to this test, higher than typically measured seat leakage was observed. The valve then opened at a reduced pressure pi-ior to activation of the data acquisition system. The valve behavior was stable and the valve closed with a blowdown of 10.lS. After the test, the valve was disassembl1~d and inspected. Scratches and marks were observed on the valve seats. The seats were replaced with steam internal seats.

3.4.2.b. !ong lnl~t P_ipe Conf~_~tion (Configuration F). A total of seven tests 1-1as performed with the valve mounted on a long inlet configuration. Six of the tests were performed using the final ring positions established during the long inlet pipe configuration Crosby 3K6 (Steam Internals) 500 series tests. The last test was performed with the rings adjusted to reduce blowdown. The principal obser-

  • vat.ions for these tests are as follows~

3-53

Steam Tests Two high back pressure, drained loop seal steam tests were performed. For both tests, the valve opened within ~3% of the valve design set pressure and had stable behavior. When the pressure accumulated to 6% above the valve design set pressure, the valve achieved rated lift. Valve blowdown varied from 15. 7 to 20.1% depending on the ring positions.

Loop Seal-Steam Tests Four loop seal-steam tests were performed at test initiation ramp rates of 3.4-220 psi/sec. For these tests, valve lift initiation occurred at pres-sures ranging from 2536 *psia to 2637 psia. The valve fluttered and/or chattered at partial lift positions during three of the loop seal discharges and was stable during the fourth, then popped open on steam at pressures from 2531 psia to 2708 psia. Valve behavior was stable on steam and the valve achieved rated lift when the pressure was 6%. above the valve design set pressure. The valve closed with 17.7 to 19.9% blowdown.

While the loop seal was being discharged during loop seal tests, the valve fluttered and/or chattered through partial lift positions at frequences of approximately 170-260 Hz. The valve oscillations during the water dis-charge caused water-hammer type pressure oscillations in the valve inlet piping. Pressure oscill:itions measured in the pressure transducers immediately upstream of the valve inlet indicated pn~ssures ranging from O psia to a pressure which over-ranged the transducer at 3400-3600 psia.

These pressure oscillations were not observed in Tank 1.

Transition Test One loop seal-st2am-to-water transition test was performed. For this test, the valve initially opened and fully opened within ~3% of the valve design set pressure and exhibited partial lift flutter and/or chatter during the 3-54

10011 seal discharge. The val.ve popped open on steam and was stable. When the transition from steam-to-water occurred, the valve began to fl11tter and subsequently chatter. The test was terminated after the valve was manually opened to stop chattering.

The pressure oscillations description in the Loop Seal-Steam Tests section also applies to the transition test.

Valve Inspection Results After each test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected. In each case, galled guiding surfaces and damaged internal parts were found.

Damaged parts were either refurbished or replaced prior to continued testing.

For all other inspections, the typical wear pattern observed was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimi~e seat leakage.

3-55

EPRI/CE SAF LVE TEST PROGRAM TABLE 3.4.1.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 3K6 (LOOP SEAL INTERrJALS)

Valve Description Inlet Piping Configuration "F" Length, in. I.D., in.

Manufacturer Crosby Valve and Gage Type Spring Loaded Safety Nozzle 17 6.813 Model No. HB-BP-86 3K6 Serial No. None Venturi 38 6.813 Drawing No. SK-3658-V Pipe 6 6.813 Body Si?e (inlet/outlet) 3 in./ 6 in. Reducer Bore Area 1. 841 in. 2 6 6.813/3.152 Orifice Designation K Loop Seal w Straight 54 3. 152 I

Design Set Point Pressure 2485 psig Bends 6 inches CJ1

'-.I 4-90° radi~;,

Design Bl owdown

- -percent Reducer 4 3. 152/2.624 Rated Flow 212 ,1 82 lb/hr. Rated Lift 0* 382 in.

Inlet Flange 7 2.624 Internals Type: Loop Seal Ring Setting Reference Position: Inlet Piping Configuration "E" The reported measurements are relative to Length, in. I.D., in.

the bottom of the disc ring.

Nozzle 17 6.813 Venturi 38 6.813 Pipe 6 6.813 Reducer 10 6.813/2.624 Pipe 4 2.624 Inlet Flange 7 2.624

EPRI/CE SA~VE TEST DATA TABLE 3.4.1.b

""M..J .,..l *...............

("

L J I LU

'""'" COM6USii0~ fNblN~tRING TEST MATRIX FOR THE CROSBY HB-BP-3K6 (LOOP SEAL INTERNALS)

CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS Tt:"~T Tt'<:'T \'.~.L '.'r:_ ".: ~::

IN TANK 1 AT VALVE INLET PEAK PEAK INDUCED (2) MAX. STEADY NO. TYPE SETTINGS PIP'.NG TANK 1 BACK- BENDING MOMENT LIQUID FLOW UPPER MIDDLE LOWER CONFIG. FLUID PRESS. TEMP. PRESS. RATE FLU ID TEMP. PRESS. PRESS. OPENING/CLOSING (GPM)

(PSIA) (OF) (PSI/SEC) (OF) (PS!/\) (PSIA) (IN. LBS.)

  • 403 STEAM -55 N/A -14 E STEAM ( 3) (1) (3) STEAM (1) (3) 696 142,500 N/A
  • 525 LS -115 N/A -14 F STEAM 2536 (l) 3.4 WATER 110 2558 471 70,800 N/A 526 LS -115 N/A -14 F STEAM 2608 (1) 220 WATER 94 2708 513 147,500 N/A 529 LS -115 N/A -14 F STEAM 2602 (1) 13.3 WATER 86 2638 480 64,900 N/A
  • 532 LS ,-115 N/A -14 F STEAM/ 2572 (1) 3.3 WATER 360 2573 615 59,000 (4)

TRANS WATER 535 STEAM -115 N/A -14 F STEAM 2530 (l) 85.7 STEAM (l ) 2650 541 59,000 N/A 536 LS -115 N/A -14 F STEAM 2637 (1) 43.6 WATER 98 2677 507 59,000 N/A w 537 STEAM -95 N/A -14 F STEAM 2500 (l ) 267 STEAM (1) 2713 557 64,900 N/A

, I

(.TT

\.0 N/A Not applicable NOTES:

(l ) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation temperature.

(2) The reported values are the maximum induced bending moments on the valve discharge flange during opening or closing.

(3) The valve opened at a reduced pressure prior to data acquisition activation.

(4) Unstable conditions precluded reliable measurement.

  • The valve was disassembled, inspected, and refurbished as requ_ired. for representative test performance.

TABLE VE TCSI DATA 3.4.1.c VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA rnP CROSBY HB-BP-86 3K6 (LOOP SEAL INTERNALS)

TH~

PRE-TEST VALVE LEAKAGE VALVE OPENING AND CLOSING NOMINAL NOMINAL POST-TEST VALVE LEAKAGE VALVE VALVE LEAKAGE TllNK I NIJM!rlAL NOM lNAL INITIAL OPENING OPENING TEST NO.

TEST MEDIA INLET INLET RATE OPENING "POP" SIMMER OPENING "POP" PRESS.

AT VALVE % BLOWDOWN VALVE VALVE LEAY-AGE i TYPE PRESS. TEMP. (GPM) VALVE MEDIA INLET INLET RATE .

I I

PRESS. PRESS. TIME TIME CLOSURE I (PSIA (OF PSIA STABILITY PRESS. TEMP. (GPM)

PSIA SEC SEC (PSIA) (PSIA) (OF) 403 STEAM STEAM 2315 Sat 0.7 (l) (l) (l) (l) 2250 10. l stable (4) STEAM 2320 Sat 3.8 525 LS WATER 2296 84 o.o 2536 2531 12 .0139 2032 stable (3) STEAM 526 LS WATER 18.8 2298 Sat 0.0 2278 94 u.u 2608 2708 .894 .090 529 LS 2031 18.9 stable (3) . STEAM 2307 Sat 0.0 WATER 2301 88 0.0 2604 2635 l .990 .007 2048 17. 7 stable (3) STEAM 532 LS

  • WATER 2309 BO o.o 2572 2568 2300 Sat o.o TRANS .402 .013 (2) (2) chatter (3)(5)WATER 2296 305 0.0 535 STEAM STEAM 2287 Sat .26 w 2530 2530 .008 .006 2000 20. 1 I

536 LS WATER stable STEAM 2300 Sat o.o en

,__. 2303 98 0.0 2637 2676 1. 387 537 .008 2006 19. 9 stable STEAM 2302 STEAM STEAM 2300 Sat 0.0 Sat .34 2500 2500 .009 . 007 2109 15.7 stable STEAM 2300 Sat l. 0 N/A Not Applicable NOTES:

(1) The valve opened at a reduced pressure prior to data acquisition activation.

(2) Unstable conditions precluded reliable measurement.

(3) The valve fluttered and/or chattered during loop seal discharge. The valve stabilized on steam.

(4) Data available after valve opening indicated stable performance.

(5) Chatter occurred simultaneous with steam/water transition.

EPRI/CE SAF VE TEST DATA TABLE 3.4.1.d VALVE FLOW RATE PEP>ORMANCE DATA FOR THE CROSBY -HB-BP-86 3K6 (LOOP SEAL INTERNALS)

CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ACCUMULATION ( 1)

BASED ON BASED ON LIQUID FLOW MEASUREMENT TANK PRESSURE BASED ON BASED ON TEST VALVE INLET PRESSURE TANK ~P.E SSURE MAX.

TEST  % RATED %RATED % R/.\TED  % RATE[* VALVE INLET PRESSURE TANK CONDITIONS STEADY NO. TYPE  % RATE2  % RATED % RATED  % RATED LIFT STEAM LI FT STEAM LIFT PRESS. TEMP. LI QU Ji)  % RATED FLOW STEAM LIFT STEAM ( PSIA) (OF)

FLOW FLOW FLOW LIFT F.LOW (GPMl 403 STEAM N/A N/A N/A N/A N/A 525 LS 1-J/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/11 526 LS 109 96 N/A N/A N/A N/A 108 97 109 101 529 LS 109 104 N/A N/A N/A 111 99 110 100 N/A (3) (3) (3) 532 LS N/A N/A (3) N/A N/A N/A N/A N/A N/A N/A N/A TRANS N/A N/A (2) (2) (2) (2) 535 STEAM 101 94 101 95 (3) ( 3) (3) 536 LS 105 94 (JJ N/A N/A N/A N/A 105 96 107 104 537 STEAM 104 105 N/A N/A N/A w 102 99 103 101 N/A I 103 105 103 108 N/A CJ) N/A N/A N/A w

N/A Not Applicable NOTES:

(1) During the valve closing cycle. The valve inlet pressure corresponds to (2) Unstable conditions precluded reliable measurement.

-~tagnation pressure.

(3) The appropriate measurement conditions were not achieved.

For the low backpressure test, the valve opened at a system pressure of 2410 psia, had stable behavior and closed with 8.2% blowdown.

Loop Seal-Steam Tests Seven 100°F nominal temperature loop seal-steam tests were performed at test initiation ramp rates of 3.2-375 psi/sec and back pressures ranging from 227 to 710 psia. For four tests, the valve lift initiation occured at a system pressure within .:!::_3% of the valve design set pressure. For all of the tests, the valve initially opened, fluttered and/or chattered at partial lift po-sition during the loop seal discharge, then popped open on steam at press8res ranging from 2580 to 2734 psia and stabilized. The valve closed with a blow-down varying from 5.1 to 9.4%.

Four high ramp rate, low back pressure, 350°F nominal temperature loop seal-steam tests were performed. For all of the tests, the valve opened initially within .:!::_3% of the valve design set pressure, fluttered and/or chattered at partial lift position during the loop seal discharge (except test no. 1415),

popped open on steam at pressures of 2662-2755 psia and closed with 6.2-9.0%

blowdown. During two tests, the valve chattered on closu*re, and the tests were terminated after the valve was manually opened to stop the chattering.

While the loop seal was being discharged during loop seal tests, the valve fluttered and/or chattered through partial lift positions at frequencies of approximately 170-260 Hz. The valve oscillations during the water dis-charge caused water-hammer type pressure oscillations measured in the valve inlet piping. For the 900 series tests, pressure oscillations measured in the pressure transducers located 13 inches upstream of the valve inlet flange face indicated pressures ranging from 0 psia to a pressure which over-ranged the transducer at 3400-3600 psia. For the 1400 series tests, the 900 series pressure transducers were replaced by pressure transducers with increased pressure ranges and strain gauges were mounted on the inlet pipe 15 inches upstream of the valve inlet flange face. The 1400 series data indicated that the pipe was responding to internal pressure oscillations of +/-_2450 psia at a frequency of approximately 170-260 Hz about a steady state pressure of 2650 psia. These internal pressures are based on strain gauge data since the

  • pressure transducer sensing line lengths did not result in accurate pressure measurements for the frequency of these oscillations.

3-66

3.5 CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS) 3.5. l Valve Description and Inlet Piping Configuration, "As Tested"Test Matrix and Valve Performance Data.

Tests were performed on the Crosby HB-BP-86 6M6 (Loop Seal Internals) safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The valve model was tested. on a long inlet piping configuration (test series 900 and 1400, configuration G). The fol lowing is the 1ist of tables that contain the safety valve information/data for these tests:

Table Description Table Number Safety Valve Description and Inlet Piping Configuration 3.5.l.a "As Tested" Test Matrix 3. 5. 1. b Valve Transient and Leakage Performance Data 3.5. l.c Valve Flow Rate Performance Data 3.5.l.d 3.5.2 Principal Observations A total of seventeen tests were performed on the Crosby HB-BP-86 6M6 (Loop Seal Internals) safety valve mounted on a long inlet pipe configuration. Essentially, two groups of tests were performed. The first group of tests (nos. 903 to 926) were performed with *several "lowered" ring positions selected in order to increase the valv~ opening time and decrease the inlet transient pressure drop. The second group of tests (nos. 929 to 932 and the 1400 series tests) generated valve performance data for the Crosby valve with ring positions representative of typical PWR plant ring positions. The principal observations for these tests are as follows:

Steam Tests Two high ramp rate steam tests were performed at high and low back pres-sures. During the high back pressure test, the valve opened at a system pressure of 2490 psia, had stable behavior and closed with 9.5% blowdown .

3-65

Transition Tests Three low ramp rate, high back pressure, steam-to-water transition tests were performed. Two of the tests included loop seals (nos. 914 and 931) and one test was a drained loop seal test (no. 926). Test number 914 was performed with the valve rings inccirrect1y set and the valve chattered during the steam portion of the test. For the tests with the rings cor-rectly set, the valve had stable performance and closed with blowdowns of 9.1 to 13.1%. The pressure oscillation description in the Loop Seal-Steam

_l~t~ section also applies to the loop seal-transition tests.

Water Tests After the valve closed on test no. 931 (loop seal-steam-to-water transi-tion test), the system was permitted to repressurize and the valve cycled on 650°F nominal temperature water. Test observations indicated that the valve did not chatter.

During the 550°F subcooled water test, the valve opened at a system pressure within +/-_3% of the valve design set pressure and chattered.

The test was terminated after the valve was manually opened to stop the chattering.

Valve Lift For those.tests in which the valve was in full lift at a pressure 6% above the valve design set pressure, rated flow was achieved even though the valve was in a lift position of up to 8% below rated lift.

Valve Inspection Results After each test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected. In each case, galled guiding surfaces and damaged internal parts were found.

3-67

Damaged parts were eilher refurbished or replaced prior to continued testing.

For all other inspections, the typical wear pattern observed was scratches or marks on the seat surf aces. The seat surfaces were lapped prior to

~eassembly and continued testing in order to minimize 1seat leakage.

/

3-68

  • EPRI/CE SAFET~E TEST PROGRAM TABLE 3.5.1.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)

Valve Description Inlet Piping Configuration "G" Length, in. J.D., in.

Manufacturer Crosby Valve and Cage Company Nozzle . 17 TV!iP 5~rir.g ~8adcd ~~7cty Valve 6.813 Model No. HB-BP-86 6M6 Venturi Serial No. N56964-00-0086 3.8 6.813 Drawing No. Crosby DS-C-56964 Rev. C Pipe 13 6.813 Body Size (inlet/outlet) 6 in./ 6 in. Reducer 6 Bore Area 3.644 in.2 - - - - ---- 6.813/4.897 Orifice Designation M Loop Seal Straight 48 4.897 Design Set Point Pressure _2_4_8_5_ __,psig Bends 2-1800 w 9 in. radius

~ Design Slowdown ___ 5 _ _,percent Inlet Flange l.O 10 4.897 Rated Flow 420,006 lb/hr. Rated Lift 0.538 Internals Type: Loop Seal Ring Setting Reference Position Th~ ring setting position refers to the number of notches relative to the bottom of the disc ring.

  • EPRI/CE SA~LVE TABLE 3.5. l .b TEST DATA "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE CROSBY HB-BP-86-6M6 (LOOP SEAL INTERNALS)

CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST VALVE RING INLET IN TANK l AT VALVE INLET PEAK PEAK INDUCED (2) MAX. STEADY NO TYPE SETTINGS PIP ING TANK l BACK- BENDING MOMENT LIQUID FLOW UPPER MIDDLE LOWER CONFIG. FLUID PRESS. TEMP. PRESS. RATE FLUID TEMP. PRESS. PRESS. OPENING/CLOS ING (SPM)

(PSIA) (oF) \PSI/SEC) ("F) (PSIA) (PSIA) (IN. LBS.)

  • 903 STEAM -136 -68 G STEAM 2490 (l) 291 STEAM (1) 2667 665 215, 100 NJfJ.

906a LS -136 -68 G STEAM 2582 (1) 3.2 WATER ( 5) 2582 554 256,925 'i/A b STEAM 2455 31. 5 STEAM (1) 2455 532 'UA c STEAM 2456 14.2 STEAM ( 1i 2456 520 ':i/A 908 LS -136 -68 G STEAM 2567 ( l) 297 WATER ( 5) 2688 649 298,750 ,,,~

  • 910 LS -136 -68 G STEAM 2480 (l) 375 WATER ( 5) 2634 227 209, 125. ':i/A 913 LS - 44 -66 G STEAM 2550 (1) 375 WATER (5) 2735 242 239,000 ~I/A w

I

-....J *914a LS - 44 -66 G STEAM 2510 (l) 1. 1 WATER ( 5) 2516 520 203,150 (4)

I-" TRANS b STEAM 2400 21.8 STEAM (1) 2400 330 (4) c STEAM 2360 (3) STEAM (1) 2400 (3) (4) 917 LS -136 -68 G STEAM 2458 (1 ) 291 WATER (5) 2732 245 227,050 NI.A

  • 920 LS -136 -68 G STEAM 2497 (1 ) 297 WATER (5) 2725 246 215' 100 N/A 923 LS -186 -68 G STEAM 2649 (1) 283 WATER 91 2736 667 179,250 N/A.

N/A l~ot Applicable NOTES:

(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation temperature.

(2) The reported values are the maximum induced bending moments on the valve discnarge flange durino openinq or closing.

( 3) Unstable conditions precluded reliable measurement.

(4) The test was terminated, interferinq with this measurement.

  • The valve was disassembled, inspected, and refurbished as required, for representative test performance.

(5) The test in~trllfnent;ition malfunctioned. No reliable measurement was avaiiable.

J

  • trl\ 111.,t It ST UA TA TABLE 3.5. l .b (Con' t)

"AS TESTED" COMBUSTION ENGINEERING TE~T MATRIX FOR THE CROSBY HB-BP-86-6M6 (LOOP SEAL INTERNALS)

CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST VALVE RING INLET PEAK PEAK INDUCED (2) MA.X. STEADY NO. TYPE SETTINGS PIPING IN TANK l AT VALVE INLET TANK 1 BACK- BENDING MOMENT LIC'.! ! D FLOW UPPER MIDDLE LOWER CONFJG. FLUID PRE SS. TEMP. PRESS. RATE FLUID TEMP. PRESS. PRESS. OPENING/CLOSING (GPM)

( P<;TA) (OF) !PST /<;Fr\ ran

' , ......I'\',

(\ 'OC"l T n' r\ 'nr_,,,,.,...., ( ;;i. LBS.)

  • 926a TRANS -186 -68 G STEAM/ 2389 (l) 2.0 STEAM (1) 2389 445 95,600 N/A WATER b STEAM/ l. 6 STEAM (1} 2385 440 N/A WATER c STEAM/ l.9 STEAM (l) 2384 650 ~II A WATER d WATER l. 5 l*IATER 635 2271 585 2233 929 LS -71 -18 G STEAM 2600 (l) 319 WATER 90 2726 710 179,250 ~l/A w

I

-....J 93la LS -71 -18 G STEAM/ 2570 (l ) 2.5 WATER 117 2578 725 201, 150 2355 w TRANS WATER b (4) (4) (4) (4) (4)

  • 932 WATER -71 -18 G WATER 2501 515 3.0 WATER 463 2520 650 107 ,550 (3)
  • 1406 LS -77 -18 G STEAM. 2530 (1) 325 WATER 147 2703 250 286,800 II/A
  • 1411 STEAM -77 -18 G STEAM 2410 (1) 300 STEAM (l) 2664 245 239,000 N/A 1415 LS -77 -18 G STEAM 2555 (l) 360 WATER 290 2760 255 268,875 NIA
  • 1419 LS -77 -18 G STEAM 2464 (1) 360 WATER 350 2675 245 256,925 N/A N/A Not applicable NOTES:

(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was* the saturation temperature.

(2) The reported values are the maximum induced bending moments on the valve discharge flange durina openi:19 or closinq.

(3) Unstable conditions preclude reliable measurements.

(4) These data were not available

  • The valve was disassembled, inspected, and refurbished as required for re,resent~tive test performance.

l:.PRl/CE ':>A. LVE JEST DATA TABLE 3.5.1.c VALVE TRANSIENT h~D LEA~AGE PlR~ukMANLE UAIA FUR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)

PRE-TEST VAL VE LEAKAGE NOMINAL NOMINAL VAL VE OPENING AND CLOSING TEST VALVE VALVE LEAKAGE INITIAL TANI< I POST-TEST VALVE -~AKAGE TEST MEDIA INLET INLET OPENING OPENING OPENING NO~~HIAL NOt>':~.!L NO. TYPE RATE OPENING "POP" PRESS.

PRESS. TEMP. (GPM) SIMMER "POP" AT VALVE % BLOWDOWN VilLVE VAL'::: LEAKAGE (PSIA OF PRESS. PRESS. TIME VALVE MEDIA Ilic ET R.l\T E TIME CLOSURE Ir1~:~

PSIA PSIA SEC STABILITY PPtSS. (GPM) 903 SEC PSIA) E"i:-.

STEAM STEAM 2275 (FSIA) (C~

470 o.o 2490 2496 .0194 906a LS .008 2264 9.5 WATER 2300 104 o.o stable STEAM 2~08 b 2582 2580 .857 (5)

Sat n.o 2294 8.3 stable (4) c 2555 STEAM 2300 Sa: 0.0 2294 8.3 stable 908 LS 2557 2298 WATER 2275 8.1 stable 159 o.o 2567 2687 .93 910 LS .012 2294 8.3 stable (4)

WATER 2280 354 0.0 STEAM 2276 Sat 2480 2628 l. 17 0.0 w 913 LS WATER (5) 2306 7.8 stable (4)

I 2300 124 0.0 2550 STEAM 2300 Sat 0.0

-....J 2734 .82 .014 tJ1 914a LS WATER 2316 7.4 stable (4) 2308 126 o.o 2510 STEAM 2300 590 1.0 TRAHS 2500 2.94 .011 2309 7.7 stable (4) b (6) (6) (6) (5) 2400 2360 5.6 stable c

2360 (2) (2) chatter 917 LS WATER 2280 477 0.0 2458 ....

2662 .69 .016 920 LS WATER 2276 9.0 stable (4) 2292 333 0.0 STEAM 2300 Sat o.o 2497 2695 0.73 923 LS 0.017 (2) (21 WATER 2275 94 chatter (7) STEAM 2275 Sat 0.0 2649 2732 0.9 0.0 0.009 2308 7.7 stable (4) STEAM 2300 Sat 0.0 N/A Not Applicable NOTES:

(1 J No measurement .was taken.

(2)

(3) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.

(4)

Unstable condition precluded reliable measurements.

The valve fluttered and/or chattered during the loop seal discharge.

(~? Post-test The test instrument malfunctioned. No reliable data was available.

leakage was not measured because it exceeded the system The*valye stabilized on steam.

measurement (7) The valve chattered on closure. limit of lO gpm.

EPRl/CE SA.LVE TEST DATA rn ~ . 5. I. c (Con ' t)

VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)

PRE-TEST VALVE LEAKAGE VAL VE OPENING AND CLOSING POST-TEST VALVE LEAKAGE NOMINAL NOMI NAE TANK I NOMINAL NOMINAL VALVE VALVE LEAKAGE INITIAL OPENING OPENING OPENING PEESS. VALVE VALVE LEAKAGE TEST TEST MEDIA INLET INLET RATE OPENING "POP" SIMMER "POP" AT VALVE % BLOWDOWN VALVE MEDIA INLET INLET RATE NO. TYPE PRESS. TEMP. (GPM) PRESS. PRESS. TIME TIME CLOSURE STABILITY PRESS. TEMP. (GPM)

(PS!AJ (OF) (PSIA} {PSIA} {SEC} (SEC} (PSIA) (PSIA) (OF) 926 a TRANS STEAM 2283 Sat 0.36 2389 2389 0.010 0.013 2267 9.4 Stable STEAM . 2295 Sat 0.08 b 2385 2274 9.1 Stable c 2384 2174 13. 1 Stable d 2263 2203 12.0 Stable 929 LS WATER 2290 94 o.o 2600 2717 0.83 0.019 23"13 5 .1 Stable (4) WATER 2300 476 0.0 93la LS WATER 2300 122 0.0 2570 2575 4.25 0.021 (6) (6) Stable(4) WATER 2295 485 0.0 w TRANS I

-....J

-....J b (6) (6) (6) (7) 932 WATER WATER 2300 489 0.0 2501 (3) (3) N/A (2) (2) Chatter ( 1) ( 1) ( 1) ("1) 1406 LS WATER 2300 105 o.o 2595 (3) (5) (5) 2666 9.4 Stable (4) STEAM 2275 Sat 0.63 1411 STEAM STEAM 2275 Sat 0.76 2410 2420 .007 .019 2297 8.2 Sfable STEAM 2275 Sat 0.37 1415 LS WATER 2300 196 o.o 2555 2755 1. 115 .012 2346 6.2 Stable STEAM 2300 540 0.0 1419 LS WATER 2300 342 0.0 2464 2674 l .035 .019 (2) (2) Chatter (B) STEAM 2300 Sat l. 5 N/A Not applicable NOTES:

(1) No measurement was taken.

(2) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.

(3) Unstable condition precluded reliable measurement.

(4) The valve fluttered and/or chattered during the loop seal discharge. The valve stabilized on steam.

(5) The test instrument malfunctioned. No reliable data was available.

(6) These data were not available.

(7) Visual test observations indicated that the valve did not chatter.

(8) The valve chattered on closure.

  • EPR!/CE SAF .VE TEST DATA TABLE 3.5.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)

CONDITIONS AT 3% ACCUMULATION (I) CONDITIONS AT 6% ACCUMULATION ( 1) LIQUID FLOW MEASUREMENT BASED or: BASED ON BASED ON BASED ON MAX.

TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE TANK CONDITIONS STEADY TEST TEST  % RATED %RATED %RATED %RATE[.  % RATED  % RATED  % RATED %RATED PRESS. TEMP. LIQUID  % RATED NO. TYPE LIFT STEAM LIFT STEAM LI FT STEAM LI FT STEAM. (PSIA) (OF) FLOW LI FT FLOW FLOW FLOW FLOW (GPM) 903 STEAM 93 (4) 93 ( 4) 94 (4) 94 (4) N/A N/A N/A N/A 906 LS N/A N/A N/A N/A N/A ~I/ A N/A N/A N/A N/A N/A '</A 908 LS 97 104 97 105 99 110 99 110 N/A N/A N/A N/A 910 LS (4) 104 (4) 107 (3) (3) (3) (3) N/A N/A N/A N/A 913 LS 95 105 95 107 95 111 96 112 N/A N/A N/A N/A 914 LS N/A N/A N/A N/A N/A ~I/A N/A N/A (2) (2) (2) (2)

TRANS w

I

'-.I 917 LS 97 98 97 98 97 102 97 104 N/A N/A N/A N/A

\.0 920 LS 106 95 106 95 lll 95 111 "!/A N/A "/A N/A 923 LS 95 104 95 105 96 109 96 110 N/A N/A N/A N/A N/A Not Applicable NOTES:

(1) During the valve closing cycle.The valve inlet pressure corresponds to stagnation pressure.

(2) The test was terminated when tile va 1ve was manually opened to stop chatter 1 interfering with this measurement.

(3) The appropriate measurement conditions were not achieved.

(4) The instrumentation malfunctioned. No reliable measurement was available.

  • EillCE SAf-VE llSI DA1A TABLE .5.1.d (Can't)

VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6M6 (LOOP SEAL INTERNALS)

CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ACCUMULATION ( 1) LIQUID FLOW MEASUREMENT BASED OK BASED ON BASED ON BASED arr---

TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE TEST TEST  % RATED  % RATED  % RATED VALVE INLET PRESSURE TANK CONDITIONS STEADY

% RATED  %-R~--Y-RATED %RATED  % RATED NO. TYPE LIFT STEAM LIFT STEAM PRESS. TEMP. LIQUID  % RATED LIFT STEAM LI FT SlEAM (PSIA) (OF) FLOW FLOW FLOW FLOW LIFT FLOW (GPM) 926a TRANS N/A N/A N/A N/A N/A N/A N/A N/A b

c d 2300 640 2233 64 929 LS 93 1ll 93 112 93 117 93 118 N/A N/A N/A N/A 93la LS N/A N/A N/A N/A TRANS N/A N/A N/A N/A 2415 641 2355 56 b

w 932 WATER N/A N/A N/A N/A I N/A N/A N/A N/A (2) (2)

CXl (2) (2) 1406 LS (2) l 07 (2) 109 (2) 112 (2) 116 N/A N/A N/A N/A 1411 STEAM 92 107 92 108 93 111 (3) (3) N/A N/A N/A N/A 1415 LS 92 109 92 111 92 114 92 116 N/A N/A N/A N/A 1419 LS 94 109 94 110 95 114 (3) (3) N/A N/A N/A N/A N/A Not Applicable NOTES:

(1) During the valve closing cycle.The valve inlet pressure corresponds (2) Unstable conditions precluded reliable measurement. to stagnation pressure.

(3) The appropriate measurement conditions were not achieved.

3.6 CROSBY HB-BP-86 6N8 (STEAM INTERNALS) 3.6. l Valve Description and Inlet Piping Configuration, "As Tested" Test Matrix and Valve Performance Data Tests were performed on the Crosby HB-BP-86 6N8 safety valve model at the EPRI/CE PWR Safety-and Relief Valve Test Facility. The valve was tested on a long (test series 1200, configuration H) inlet piping configuration. The following is the list of tables that contain the safety valve information/data for these tests:

Table Description Table Number Safety Valve Descriptidn and Inlet Piping Configuration 3. 6. l. a "As Tested" Test Matrix 3. 6. l. b Valve Transient and Leakage Performance Data 3.6.1.c Valve Flow Rate Performance Data 3. 6. l. d 3.6.2 Principal Observations

  • A total of eight tests was performed with the Crosby HB-BP-86 6N8 (Steam Internals) safety valve mounted on a long straight inlet pipe configuration. A flow venturi was not in -place during these tests. The principal observations for these tests are as follows:

Steam Tests Five steam tests were performed at test initiation ramp rates of 2-325 psi/sec with three different ring positions. For all of the tests, the valve opened within ~3% of the design set pressure and had stable behavior.

For those tests in which the system pressure was 6% above the valve design set pressure, the valve achieved a lift position which was 97% of its rated lift.

The first two tests were performed with ring positions (-110, -18) repre-3-83

sentative of typical PWR plant ring positions. The valve opened, had stable behavior and closed with a blowdown range of 15.1 to 16.6%. Both tests were high back pressure tests.

In order to reduce the valve bJowdown, the ring positi*ons were changed two

~imes during the subsequent steam tests. The last ring position (-40, -18) resulted in a blowdown of 9.6% and 9.8% for high and low back pressures, respectively. The last ring position was used during the subsequent transition and water tests.

Transition Test One low ramp rate, high back pressure, steam-to-water transition test was performed. The valve had stable behavior during the four actuations of this transition test. During the initial actuation, the valve opened at a system pressure within ~3% of valve design set pressure and closed with 8.6% blowdown. During the subsequent actuations,! the opening pressure range was 2420 - 2480 psia and the closing pressur~ range was 2120 - 2305 psi a.

Water Tests Two high back pressure water tests were performed at nominal temperat~res of 650°F and 550°F.

During the 650°F water test, the valve opened at a system pressure within

+3% of the valve design set pressure, had stable behavior and closed with 20 .9~~ bl owdown.

During the 5500F water test, the valve opened at 2526 psia and chattered.

The test was terminated after the valve was manually opened to stop the chat te'ri ng.

3-84

  • After the 55QOF water test which was terminated by manually opening the valve to stop chattering, the valve was disassembled and inspected.

Galled guiding surfaces and several damaged internal parts were found.

For all other inspections, the typical wear pattern observ~d was scratches or marks on the seat surfaces. The seat surfaces were lapped prior to reassembly and continued testing in order to minimize seat leakage~

  • 3-85
  • EPRI/CE SAFET E TEST PROGRAM TABLE 3.6. l.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)

Valve Descr{ption Inlet P*iping Configuration "H" Manufacturer Length, in. I.D., in.

Type Crosby Valve and Gage Company Spring Loaded Safety Valve Nozzle Model No. HB-BP-86 6N8 17 6.813 Serial No. N61894-00-0006 Drawing No. Venturi Not Applicable Crosby DSC- 61894 Rev. D Body Size (inlet/outlet) 6 in./ Pipe 9 8 in. 6.813 Bore Area 4.381 in.2 --"'---

Orifice Designation N Reducer 6 6 .813/5 .189 Pipe 76 5.189 Design Set Point Pressure 2485 psig Inlet Flange 7 5.189 Design Bl owdown _ __,5=--_.percent Rated Flow 504,952 lb/hr. Rated Lift a 591 in.

Internals Type: Steam Ring Setting Reference Position:

The ring setting position refers to the number of notches relative to the bottom of the disc ring.

EPRl/CE SA LVE TEST DATA TABLE 3.6.1.b "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)

TEST TEST CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS VALVE RING INLET NO. TYPE SETTINGS PIPING IN TANK 1 AT VALVE INLET PEAK PEAK INDUCED (2) MAX. STEADY UPPER MIDDLE LOWER CONFIG. FLUID TANK l BACK- BENDING MOMENT LIQUID FLOW PRESS. TEMP. PRESS. RATE* FLUID TEMP. PRESS. PRESS. OPEN ING/CLOS I NG (PSIA) (OF) (PSI/SEC) (')r l (GPM)

( PSIA) (rSIA) (IN. LBS.)

  • 1202 Steam -110 -18 H Steam 2487 (1) 2.0 STEAM ( 1) 2487 388 527,800 N/A 1203 Steam -110 -18 H Steam 2450 (1) 286 STEAM (1) 2680 500 682,500 N/A 1205 Steam - 75 -18 H Steam 2472 (1) 317 STEAM (1) 2635 546 254,800 N/A 1207 Steam - 40 -18 H Steam 2484 (1 ) 317 STEAM (l) 2674 560 655,200 N/A 1208 Steam - 40 -18 H Steam 2445 ( l) *325 STEAll. (1) 2640 200 473,200 N/A
  • l 209a TRANS - 40 -18 H Steam/ 2466 (1) w 2.6 STEAM (1) 2466 398 518, 700 I Water (3) 00

\.0 b Steam/ 5. 1 STEAM (1)

Water 2455 402 c Steam/ 5.0 STEAM (l) 2480 420 Water d

Steam/ 5.3 STEAM (1) 2420 Water 572 1211 Water - 40 -18 H Water 2450 635 4.6 l*/ater 621 2450 525 591,500 (3)

  • 1213 Water - 40 -18 H Hater 2526 549 3. 1 Hater 536 2605 318 518,700 (3)

N/A Not aprlicable NOTES:

(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests, the initiation temperature was the saturation temoerature.

(2) The reported values are the maximum indur.ed be:1dino mnrnent.s on the valve discharge flanqe <111rino openinn nr closinri.

(3) Because of the inlet configuration used for this test series valve flow rate was not me~sured. -

  • The valve was disassembled, inspected, and refurbished as required for representative test performance.
  • EPRl/CE SA~*LVE TA TEST DATA

.6.1.c VALVE TRANSIENT PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)

PRE-HST VAL VE LEAKAGE VALVE OPENING AND CLOSING NOMINAL flOMINAL POST~TEST VALVE LEAKAGE VALVE -TA/fl( 1 -*----NOM f NAL -Nor~ lNAL___ --- -

VALVE LEAKAGE INITIAL OPENING OPENING OPENING TEST TEST MEDIA INLET INLET PRESS. VALVE VALVE LEAKAGE RATE OPENING "POP" SIMMER "POP" AT VALVE % SLOWDOWN NO. TYPE PRESS. TEMP. (GPM) VALVE MEDIA INLET INLET RATE PRESS. PRFSS. rIME TIME CLOSURE STAB!LiTY PRESS. (GPM)

(PSIA) (OF) TEMP.

_i!>SIAJ__(_P_s_!jl.J_ _J_S_E_Cj ___~E_C_l__ (PSIA) (PSIA) (OF) 1202 Steam Steam 2280 SAT 0. 1 2487 2487 0.012 0.008 2124 15. 1 Stable Steam 2290 SAT i203 0.06 Steam Steam 2290 SAT 0.06 2450 2452 0.010 0.008 2088 16.6 Stable Steam 2290 SAT 0 1205 Steam Steam 2275 SAT 0.09 2470 2474 0.010 0. 010 21*~4 14.3 Stable Steam 2280 SAT 0. 01 1207 Steam Steam 2300 SAT 0.6 2484 2486 0.009 0.016 22151 9.6 Stable Steam 2290 SAT 0.48 1208 Steam Steam 2290 SAT 0.48 2445 2447 0.012 0.009 22!j6 9.8 Stable Steam 2278 SAT 0.1 1209a TRAl~S Steam 2278 SAT 0.1 2466 2466 0.009 0.010 22B6 8.6 Stable Steam 2280 SAT 0.0 w b I

\.Q 2455 2282 8.8 Stable c

2480 2305 7.8 Stable d

2420 2120 15.3 Stable 1211 Water Water (2) (2) (2) 2450 2450 0. 011 0.016 1980 20.9 Stable Water 2275 SAT 0.0 1213 Water Water 2300 558 0.0 ..

2526 2526 0.009 N/A (1) (1 ) Chatter (2) (2) (2) (2)

N/A Not applicable NOTES:

(1) The test was terminated when the valve was manually opened to stop chatter, interfering with this measurement.

(2) No measurement was taken.

  • EPRl/CE SA LVE TEST DATA TABLE 3.6.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE CROSBY HB-BP-86 6N8 (STEAM INTERNALS)

CONDITIONS AT 3% ACCUMULATION ( 1) CONDITIONS AT 6% ACCUMULATION ( 1) LIQUID FLOW MEASUREMENT BASED ON BASED ON BASED ON TANK PRESSURE VALVE INLET PRESSURE BASED ON TEST TEST %RATED TANK PRESSURE VALVE INLET PRESSURE . TANK CONDITIONS

% RATED %RA1 ED  % RATElJ  % RATED %RATED  % RATED STEADY NO. TYPE LIFT STEAM LIFT. STEAM

% RATED --pJlEss. TEMP. LIQUID  % RATED L !FT STEAM LIFT STEAM (PSIA) (OF) FLOW FLOW FLOW FLOW LIFT FLOW (GPM) 1202 Stearn N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1203 Stearn 96 (2) (2) (2) 97 (2) (2) (2) N/A N/A N/A N/A 1205 Stearn 97 (2) (2) (2) (3) (2) (2) (2) N/A N/A N/A N/A 1207 Stearn 96 (2) (2) (2) 97 (2) (2) (2) N/A N/A N/A N/A 1208 Stearn 97 (2) (2) (2) (3) (2) (2) (2) N/A N/A N/A N/A 1209 TRANS N/A N/A N/A N/A N/A N/A N/A N/A w (2) (2) (2) (2)

I ID w 1211 Water N/A N/A N/A N/A N/A N/A N/A N/A (2) (2) (2) (2) 1213 Water N/A N/A N/A N/A N/A N/A N/A N/A (2) (2) (2) (2)

N/A Not applicable NOTES:

(1) During valve closing cycle.

(2) Because of the inlet configuration flow was not measured. This precfoded determination of valve inlet sta~nation conditions.

(3) The appropriate measurement conditions were not achieved.

3.7 TARGET ROCK CORPORATION SAFETY VALVE MODEL 69C 3.7.l Valve Description and Inlet Piping Configuration, 11 As Tested Test Matrix 11 and Valve Performance Data Tests were performed on the Target Rock 69C safety valve model at the EPRI/CE PWR Safety and Relief Valve Test Facility. The valve was tested on a long (test series 700, configuration I) inlet piping configuration. The following is the list of tables that contain t~e safety valve information/data for these tests:

Table Description Table Number Safety Valve Description arid Inlet Piping Configuration 3.7.1.a "As Tested Test Matrix 11 3.7.1.b Valve Transient and Leakage Performance Data 3.7.1.c Valve Flow Rate Performance Data 3.7.1.d

  • 3.7.2 Principal Observations A total of nine tests were performed with the Target Rock 69C pilot operated safety valve mounted on a long inlet pipe configuration. The principal observations for these tests are as follows:

Steam Tests Two high ramp rate steam tests were performed with high and low back pressures. For these high ramp rate tests, the pilot disc opened within

+3% of the valve design set pressure and the main disc opened at pressures of 2612 and 2630 psia. The valve exhibited stable performance and closed with less than 4% blowdown. When the system pressure accumulated to 6%

above the valve design set pressure, rated flow was achieved.

3-95

Loop Seal ~ Steam Tests Two high back pressure loop seal-steam tests were performed at high and low ramp rates. For the low ramp rate test, the valve cycled opened and closed a total of eight times in response to system repressurizations. For the initial actuation cycle, the pilot disc and the main disc opened within ~3%

of the valve design set pressure, exhibited stable performance and closed with 4.9% blowdown. In the subsequent actuations, the pilot disc and main disc opened and closed at generally decreasing pressures down to minimum opening and closing pressures of 2390 and 2325 psia, respectively.

Valve performance was stable for all cycles.

For the high ramp rate test, the pilot disc opened within +3% of the valve design set ~ressure and the main disc opened at a pressure of 2610 psia.

The valve ex1ioited stable performance and closed with 8.5% blowdown. When the system pressure accumulated to 6% above the valve design set pressure, rated flow was achieved.

Transition Test In the loop seal-steam-to-water transition test, the valve cycled opened and closed twice. For the first cycle, the valve opened on the loop seal and closed on steam with performance similar to the low ramp rate loop seal-steam test performance. The system repressurized and the valve pilot disc and main disc opened on steam with performance similar to the low ramp rate steam test performance, had stable performance and closed on water with 12.5% blowdown.

Water Tests Four cold loop seal-water tests were performed at nominal water tempe~

atures of 6S0°F, 550bF and 4000F (2 tests). For the initial actuation cycle of each test, the pilot disc and main disc opened within +/-_35~ of the valve design set pressure and closed with 3.1 to 23.7 blowdowns.

In the 550°F water test, the valve ~ycled open and closed seven additional times in response to system repressurization with opening pressures of 2390-2466 psia and closing pressures of 2245-2390 psia.

3-96

Based on upstream pressure data, the valve fluttered during all of the water tests.

Valve Inspection Results The valve was disassembled and inspected twice. The first inspection occurred after the water tests were completed. For this inspection, it was observed that the main disk shaft had bowed and that there was scoring of the piston and piston ring. A new valve was used for the final two steam tests rather than refurbishing the existing test valve. The inspection of the second test valve occurred after the two steam tests were completed.

No wear was observed .

  • 3-97

EPRI/CE SAFETY TABLE

- TEST PROGRAM 3.. 7.1.a SAFETY VALVE DESCRIPTION AND INLET PIPING CONFIGURATION FOR THE TARGET ROCK 69C Valye Description Inlet Piping Configuration Length, in. I.D., in.

Manufacturer Target Rock Nozzle 17 Type 6.813 Pilot Operated Safety Valve Model No. (1) 69C Venturi 38 6.813 Serial No. 4,5 Drawing No. 69C-OOO Rev. 07 Pipe 33 6.813 Body Size (inlet/outlet) 6 in./ 6 in. Reducer 6 6.813/4.897 Bore Area 3.513 in.2 ----

Orifice Designation Not Applicable Loop Seal Straight 60 4.897 Design Set Point Pressure _24_8_5_ __,psig Bends 2-1800 9 in. radius

~ Design Slowdown 5 percent Inlet Flange 7 4 .897

<.O ---~

<.O Rated Flow 345,000 lb/hr. Rated Lift Not Applicable Internals Type: Not Applicable (1) Valve serial no. 4 was used for all tests except 722 and 723. Valve serial no. 5 was used for tests 722 and 723.

  • EPRI/CE SAFE.E TEST DATA TABLE 3.7.l.b "AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE
  • TARGET ROCK 69C TEST TEST CONDITIONS AT VAL VE OPEN ING VALVE RING INLET TRANSIENT CONDITIONS NO. TYPE SETTINGS PIPING IN TANK 1 AT VALVE INLET PEAK PEAK INDUCED (2) MAX. STEADY UPPER MIDDLE LOWER CONFIG. FLU ID TANK 1 BACK- BENDING MOMENT LIQUID FLOW PRESS. TEMP. PRESS. RATE FLUID TEMP. PRESS.

(PSIA)(3) (OF) PRESS. OPENING/CLOSING (GPM)

(PSI/SEC) (OF) (PSIA) ( PSIA) (IN. LBS.)

  • 703 a LS N/A N/A N/A steam 2543 (l) 2.7 water 90 2543 380 143,750 N/A b steam 2562 4. l steam (l) 2562 330 c steam 2503 20.6 steam (l) 2503 320 d steam 2472 2.2 steam (l) 2472 270 e steam 2445 5.0 steam (l) 2445 280 w f steam 2430 I 3.9 steam (l) 2430 270

...... g 0

...... steam 2415 3.1 steam (l ) 2415 270 h steam 2390 0.0 steam (l ) 2390 135 706 LS N/A N/A N/A steam 2610 ( l) 300 water 93 2713 482 230,000 N/A 709 a LS N/A N/A N/A steam/ 2508 (l) 2.0 water 97 2508 TRANS water 270 258,750 N/A b steam/ 2474 3.4 steam (l) 2474 617 water 2540 712 water N/A N/A N/A water 2486 613 2.8 water 118 2486 500 80,500 1873 N/A Not applicable NOTES:

(1) All tests were initiated at a nominal pressure of 2300 PSIA. For steam tests and steam/water transition tests the initiation temperature was the saturation te~perature.

(2) The reported values are the maximum induced bending moments on the valve discharge flange durina opening or closing.

(3) The main disc opening pressures ar reported under Tank l conditions at valve openina.

  • The valve was disassembled, inspected, and refurbished as required for representative test performance.
  • EPR!/CE SAFET~ TEST DATA TABLE 3.7.1.b (Con't)

"AS TESTED" COMBUSTION ENGINEERING TEST MATRIX FOR THE TARGET ROCK 69C CONDITLONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST VALVE RING INLET IN TANK 1 PEAK PEAK INDUCED (2) MAX. STEADY NO. TYPE AT VALVE INLET SETTINGS PIPING TANK l BACK- BENDING MOMENT LIQUID FLOW UPPER MIDDLE LOWER CONFIG. FLUID PR[SS.(3) TEMP. PRE SS. RATE FLU ID TEMP. PRESS. PRESS. OPENING/CLOSING (GPM)

(PSIA) (OF) (PSI/SEC) (OF) (PSJA) (PSIA) (IN. LBS.)

714 a water N/A N/A N/A water 2464 568 2.2 water 97 2464 87 201 ,250 b water 2433 4.2 water 540 2433 90 c water 2466 5.0 water 510 2466 265 d water 2450 7.0 water 530 2450 380 e water 2424 8.0 water 540 2424 405 2575 f water 2411 7.5 water !i42 2411 420 w

I g water 2396 6.7 water 550 2396 410 I-'

0 h water 2390 2.7 water ~;47 2390 380 w

717 water N/A N/A N/A water 2490 410 2.6 water 82 2490 215 58,650 2041

  • 719 water N/A N/A N/A water 2487 397 0.7 water 83 2487 146 74 '750 1501
  • 722 steam N/A N/A N/A steam 2612 (l) 311 steam (1) 2678 430 54,625 N/A
  • 723 steam N/A N/A N/A steam 2630 (1) 307 steam (1) 2674 63 54,625 N/A N/A Not applicable NOTES:

(1) All tests were initiated at a nomin;il pre>sure of 2300 PSJA. For steam tests and stean11water transition tests, the initiation temperature was the saturation temperature.

(2) The reported values are the induced bending moments on the valve dischar~e flange during opening or closinq.

(3) The main disc opening pressures are reported under Tank l conditions at valve opening.

  • The valve was disassembled, inspected, and refurbished as required for representative test performance. For tests 722 and 723 valve serial number 4 was replaced with serial number 5.

EPR!/CE SAF E TEST DATA

.c VALVE TRANSIENT ANn I FAkAGF PFPFnRMBHrF nnrn rnD THE TARGET ROCK 69C PRE-TEST VALVE LEAKAGE

-t*iuMtNAC- NDl~llil\l____ - - - - - - - - - - - VALVE ---- OPENING

- - - AND CLOSING POsT:.TEST VALVE LEAKAGE TANK 1 NOMINAC!;'G'l!NAL- -----

VALVE VALVE LEAKAGE INITIAL(2) OPENING (3bPENING OPENING PRESS. VALVE VALVE LEAKAGE TEST TEST MEDIA INLET INLET RATE OPENING "POP" SIMMER "POP" AT VALVE % SLOWDOWN VALVE (4) RATE NO. TYPE PRESS. MEDIA INLET INLET TEMP. (GPM) PRESS. PRESS. f IME TIME CLOSURE Sl Al:llll TY PRESS. ii:_Nf'. (G<'l*I)

(PS!A) (Of) ~&___l_P~_I__A_l__J_S_E_Cj _____ j_S_E_Cj___(~S_IA) (PSIA) (OF) 703a LS water 2300 98 a.a 2541 2543 D.21 (1) 2378 4.9 stable steam 2300 SAT 0.0 b 2562 2444 2.3 stable c 2503 2400 4.0 stable d 2472 2374 5.1 stable w e 2445 I

...... 2350 6.0 stable 0 f 2430 U1 2338 6.5 stable g

2415 2325 7.0 stable h 2390 2332 6.8 stable 706 LS water 2283 116 0.0 2510 2610 0.33 (1) 2290 8.5 stable steam 2300 SAT 0.0 709a LS TRANS water 2303 lll 2507 0.0 2508 0.39 (1) 2390 4.4 stable water 2294 386 0.fl b 2474 2190 12.5 stable 712 water water 2286 119 0.0 2485 2486 0.25 (1) 2191 12.5 flutter water (1) 519 0.0 N/A Not applicable NOTES:

(1) No measurement was taken.

(2) The Initial Opening Pressure is reported for the pilot valve opening.

(3) The Opening Pop Pressure is reported for the main disc opening.

(4) Valve stability was inferred from the inlet pressure stability.

EPRl/CE S.l\FET~ TEST DATA TABLE l.c (Can't)

VALVE TRANSIENT AND LEAKAGE PERFORMANCE DATA FOR THE TARGET ROCK 69C PRE-TE ~_T_'{.81J_~-1=J~KA~_E_., _____________y~_L_V_f___Q_f'_E_N~r:!__G~_i_L 0~1-~G POST-TEST VALVE LEAKAGE NOMINAL NOMINAL TANK 1 ----oofftiAL -NOM [ NAC*------,

VALVE VALVE LEAKAGE INITIAL(2) OPENING (3~PENING OPENING PRESS. VALVE VALVE LEAKAGE TEST TEST MEDIA INLET INLET RATE OPENING "POP" SIMMER "POP" AT VALVE % BLOl~DO\.IN VALVE (4) MEDIA INLET INLET RATE NO. TYPE PRESS. TEMP. (GPM) PRESS. PRESS. f !ME TIME CLOSURE STABILITY PRF.SS. TEMP. (GPM)

(PSJA~ (OF) (PSIAJ_{J.>_sm__ _J_S_E_0__ ___j_S_E_CJ_ _(!'_?IA) (PSIA) (OF) 714a water water 2300 103 0.0 2462 2464 0.31 (1) 2424 3.1 fl utter water 2300 442 0.0 b 2433 2391 4.4 fl utter c 2466 2341 6.4 fl utter d 2450 2275 9.1 fl utter e 2424 2247 l 0.2 flutter w

I f 2411 2245 l 0. 3 flutter 0

'.J g 2396 2246 10. 2 fl utter h 2390 2247 10.2 fl utter 717 water water 2300 128 0.0 2488 2490 0.70 (l ) 1910 23.7 fl utter water 2300 270 0.0 719 water water 2300 90 0.0 2487 2487 0.63 (1) 2235 10.7 fl utter water 2300 330 0.0 722 steam steam 2300 SAT 0.4 2500 2612 0.37 (1) 2490 0.4 stable steam 2300 SAT 0.0 723 steam steam 2300 SAT *O.O 2505 2630 0.45 (1) 2410 3.6 stable steam 2300 SAT 0.03 N/A Not applicable NOTES:

(1) No measurement was taken.

(2) The Initial Opening Pressure is reported for the pilot valve opening (3) The Opening Pop Pressure is reported for the main disc opening.

(4) Valve Stability was inferred from the inlet pressure stability

EPRI/CE SAFET TEST DATA TABLE 3.7.1.d VALVE FLOW RATE PERFORMANCE DATA FOR THE TARGET ROCK 69C CONDITIONS AT 3% ACCUMULATION (1) . CONDITIONS AT 6% ACCUMULATION (1) LIQUID FLOW MEASUREMENT BASED ON BASED ON BASED ON BASED ON TANK PRESSURE VALVE INLET PRESSURE TANK PRESSURE VALVE INLET PRESSURE TANK CONDITIONS MAX.STEADY TEST TEST %RATED %RATED %RATED  % RATED %RATED %RATED %RATED  % RATED PRESS. TEMP: LIQUID % RATED NO. TYPE LIFT ~lEAM LIFT STEAM LI FT STEAM LIFT ~lEAM (PSIA) (OF) FLOW LIFT FLOW FLOW FLOW FLOW (GPM) 703a LS N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A b

c d

e f

w I

....... g 0

l.O h

706 LS (2) 126 (2) 128 (2) 132 (2) 133 N/A N/A N/A N/A 709a LS TRANS N/A N/A N/A N/A N/A N/A. N/A N/A 2320 641 2540 (2) b 712 water N/A N/A N/A N/A N/A N/A N/A N/A 2335 611 1873 (2)

N/A Not applicable NOTES:

(1) During.val~e closing cyc~e. The valve inlet pressu~e corresponds to stagnation pressure.

(2) The fl'arn disc stem pos*1t1on was not measured for this valve.

EPR !/CE SAFETY EST DATA TABLE 3.7.l.d (Con't)

VALVE FLOW RATE PERFORMANCE DATA FOR THE TARGET ROCK 69C CONDITIONS AT 3% ACCUMULATION (1) CONDITIONS AT 6% ACCUMULATION (1) LIQUID FLOW MEASUREMENT BASED ON BASED ON BASED ON Bl\SED ON TANK PRESSURE VALVE INLET PRESSURE AX TEST TEST %RA1ED TANK PRESSURE VALVE INLET PRESSURE TANK CONDITIONS STEADY

%RATED %RAt ED  % RATED  % RAlED  % RATED  % RATED.  % RATED NO. TYPE LIFT STEAM* PRESS. TEMP. LIQUID % RATED LIFT STEAM l !FT STEAM LIFT STEAM (PSIA) (OF) FLOW FLOW FLOW LIFT FLOW FLOW (GPM) 714a water N/A N/A N/A N/A N/A N/A N/A N/A b

c d

e f

w 2340 567 2676 (2)

I g I-"

I-"

I-" h 717 water a11r.

1*/M N/A N/A N/A N/A N/A N/A N/A 2340 411 2041 (2) 719 water N/A N/A N/A N/A N/A N/A N/A N/A 2390 396 1601 (2) 722 steam (2) 116 (2) 117 (2) 110 (2) 75 N/A N/A N/A N/A 723 steam (2) 127 (2) 129 (2) 123 (2) 99 N/A N/A N/A N/A N/A Not applicable NOTES:

(1) During valve closing cycle. The valve inlet pressure corresponds to stagnation pressure.

(2) The main disc stem position was not measured for this valve.

Section 4 4.0

SUMMARY

OF RELIEF VALVE OPERABILITY DATA A total of ten relief valves were tested under steam, water, steam to water (tran-sition) and water seal conditions.

The ten relief valves selected for testing in the EPRI Program, and the relief valves represented by the valves tested are identified in Section 2.0 of this report.

All relief valves testing as part of the EPRI/PWR Safety and Relief Valve Test Program is complete. The purpose of this section is to present the "as tested" test matrices, valve performance data and principal observations for all relief valves tested.

To assist in understanding the overall performance of each of the manufacturer's relief valve designs, refer to the Valve Description section of the "Valve Selection/

Justification Report" (Hcference 1).

4-1

4.1 DRESSER RELIEF VALVE 4.1.1 "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Dresser relief valve model at the Marshall Steam Station and _during Phase II and Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Dresser relief valve tested at each of the test facilities.

Test "As Tested" Test Valve Performance Facility Matrix Table Data Table Marshall 4.1.l-la 4.1.l-lb Wyl e (Phase II) 4.l.l-2a 4.l.l-2b Wyl e (Phase II I) 4.1.1-3a 4.l.l-3b 4.1.2 Principal Observations Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles. During the evaluation tests, steam leaked past the valve pilot stem. Upon valve disassembly, the bellows was found to have several partially failed welds. The valve was reassembled with a new bellows and cycled 16 more times with varying steady state pilot backpressures up to 900 psig.

The valve fully opened and closed on demand for each cycle and the bellows did not leak. Upon disassembly, the bellows did not have any visible cracks. In all test cases, the valve fully opened on demand and closed on demand even though the bellows was damaged during some tests. Based on this input and the manufacturer's assessment of valve performance with the observed damage, the damage was determined to have no potential impact on valve npPration.

4-3

The valve fully opened on demand and fully closed on demand for each of the five (5) test cycles.

Wyle Phase III The valve fully opened on demand and fully closed on demand during nine (9) of the twelve (12) tests performed. The valve fully opened on demand and did not close on demand during the three (3) water seal simulation tests; number 16-DR-6W, 2?-DR-9W/W and 24-DR-6W. Each test was a 2500 psia pressure test with low temperature water just upstream of the valve followed by 650°F water.

In test number 16-DR-6W, the low temperature water was at l03°F. During the test, the Dresser valve opened on demand. Upon de-energizing the valve for closure, the valve remained open until the valve was isolated from the test loop. At an indeterminate time following 'test valve isolation, the valve closed. The valve was isolated approximately 40 seconds after it was signaJled _to close. The valve was removed from the test facility and disassembled by the Dresser representative. No damage was observed which might affect the ability of the valve to open/close on demand.

In test number 22-DR-9W/W, the low temperature water at the valve inlet was 321°F. During the test, the valve opened on demand. Upon de-energizing the valve for closure, the valve remained open for 2 seconds and then closed fully.

Test number 24-DR-6W was a repeat of the test l 6-DR-6W except that the test was run to maximize the time before the valve was i so 1ated. The water temperature immediately upstream of the valve was 105°F. During the test, the valve opened on demand but failed to close immediately upon de-energjzing the solenoid. The valve closed on its own approximately 70 seconds after the closure signal at an inlet pressure of approximately 2110 psi a.

4-4

After all tests were completed, the Dresser valve was removed, disassem-bled, and inspected. No damage was observed which might affect the ability of the valve to open/close on demand.

Valve Opening/Closing Times

.No direct measurement of stem position was possible for the Dresser relief valve design. Therefore, no valve opening or .closing stroke times have been reported. Estimates of total opening/closing times (time from energize/ de-energize signal to full open/closed) have been made and are reported in the Valve Performance Data Table. These estimates were based on accelerometer or acoustic emission detector and inlet pressure measure-1nents and the methods used were confirmed by evaluation of data from other valves tested with stem position indication available.

4-5

EPRI/ MARSHALL PORV TEST DATA (3)

TABLE 4. l. l 4'1a "AS TESTED" MARSHALL TEST MATRIX FOR THE DRESSER RELIEF VALVE CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS VALVE INLET IN ACCUMULATOR TEST OUAAT!ON VALVE INLET PRESS. WHEN MAXIMUM DISCHARG pl TEST TEST FLUID PRESS. . TEMP. FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS.

NO. TYPE (PSIA) (OF) (PSIA) (OF) TO CLOSE VALVE (PSIA)

PSIA)

STEAM STEAM 2435 (SAT.) SAME AS VALYE INLET 61 2295 415 2 STEAM STEAM 2455 (SAT.) 26 2335 415 STEAM STEAM 2440 (SAT.) I 22 2330 415 4 STEAM ST.EAM 2435 (SAT.) 21 2335 415 5 STEAM STEAM 2445 (SAT.) 24 2335 415 6 STEAM STEAM 2450 (SAT.} 66 2305 175

~

STEAM STEAM 2455 (SAT.) 23 2335 175 I

Q') 8 STEAM STEAM 2420 (SAT.) 27 2300 170 9 STEAM STEAM 2415 (SAT.) 24 2310 170 10 STEAM STEAM 2435 (SAT.)

11 STEAM STEAM 2435 (SAT.) l 27

( 2) 2330 2295 175 415 NOTES:

(1) Maximum Quasi steady discharge pipe pressure.

(2) Not recorded.

(3) Test results are for evaluation tests only. Total of 21 supplementary valve actuation cycles were performed under similar conditions

TABLE 4.1.l.-lb

SUMMARY

OF DRESSER RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS °COMMENTS TOTAL VALVE (1) VALVE VALVE INLET OUTLET FLOW TEST TEST OPEN ING TIME FLUID PRESS. TOTAL VALVE (2) VALVE INLET LEAKAGE NO. TYPE TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS.

(SEC) (PSIA) (OF) (PSIA) TEMP. RATE (LBM/HR) (SEC) (PSIA) (OF) (GPM)

STEAM 0.190 STEAM 2295 (SAT.) 415 155,000 0. 300 STEAM A pre-operational lea<a9e 2405 (SAT.) 0.005 test showed 0.0 GPM lea<a;e 2 STEAM 0.170 * * * *

  • 0.320 STEAM 0.190 * * * *
  • 0.310 4 STEAM 0.190 * * .
  • 0.320 .

5 STEAM 0.190

  • * * *
  • 0.310 STEAM 2455 (SAT.) 0.013 6 STEAM 0. 180 STEAM 2305 (SAT.) 175 155,000 0.300 * *
  • STEAM 0.230 * * *
  • 0.300
  • 8 STEAM 0.170

.+::>

I

-....J 9 STEAM

  • *
  • 0.300 * ..

0.180 10 STEAM

  • * *
  • 0.300 * * .

0.170 * * * *

  • 0.300 * * *
  • 11 STEAM 0.190 * * * *
  • 0.300 STEAM 2435 (SAT.) 0.0
  • not applicable to this test NOTES:

(1) Opening time measured from time of energizing solenoid until valve reaches full open position.

(2) Closing time measured from time of de-energizing solenoid until *valve reaches full ~losed f,osition, (3) Test results are for evaluation tests only. Total of 21 supplementary valve actuation eye es were performed under similar conditions.

EPR!/ WYLE roRV TEST DATA TABLE 4. 1. 1-2a "AS TESTED" WYLE.PHASE II TEST MATRIX FOR THE DRESSER RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS VALVE INLET ( 1) IN ACCUMULATOR TF~T VAL VE TNI ET ~. 0.Y!"'.1 (2) qu,;s; .STEADY TEST TEST DURATION PRESS. WHEN DISCHARGE MAX !MUM FLUID PRESS. TEMP. FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS.

NO. TYPE (PSIA) (OF) PILOT LINE (PSIA) (OF) TO CLOSE VALVE (PSJA) B.P.

(PSIA) (PSIA)

DR-1-S STEAM STEAM 2490 674 SAME AS VALVE INLET 6 2215 60 1040 DR-3-W WATER WATER 680 373 SAME AS VALVE INLET 15 510 110 213 DR-5-W WATER WATER 2500 646 SAME AS VALVE INLET 26 2300 290 680 DR-6-W WATER WATER 2500 506 SAME AS VALVE INLET 17 2120 340 380 DR-7-W HATER WATER 2510 447 SAME AS VALVE INLET 16 2120 230 333

+:>

I co NOTES:

(!) Fluid conditions at the valve *inlet inmediately prior to actuation of test valve.

(2) Maximum Quasi steady discharge pipe pressure. *

(3) Not recorded.

EPRI I 1-IYLE PHASE II PORV TEST DATA TABLE 4.1.1-2b

SUMMARY

OF ORESSER RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VA.LYE (I) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST C?f),~:jG TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TlMP. RATE

~lO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM)

DR-1-S STEAM 0. 15 STEAM 2355 668 56 137,000 0.60 STEAM 2saa 660 0.0 DR-3-W WATER 0. 17 WATER 630 373 102 331,000 0.6a WATER 685 J8a o.o DR-5-W lo/ATER 0. 15 WATER 2430 646 278 328,000 0.6a WATER 2475 651 0.0 OR-6-W lo/ATER 0. 15 WATER 2330 sag 310 590,aaa 0.6a WATER 2380 514 a.a 40:>

I DR-7-W WATER 0.10 WATER 2360 447 22a 641,00a a.so WATER 2495 454 a.a

<..O llOTES:

(I) Opening time measured fro.m time of energizing solenoid until valve reaches full open position.

(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.

EPR!/WYLE PHASE III PORV TEST DATA TABLE 4.1.l-3a "AS TESTED" WYLE PllASE II I TEST MATRIX FOR DRESSER RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS Valve Inlet Back- At Valve Inlet In Accumulator Pressure Maximum Maximum Maximum pressure at Discharge Bending Valve Orifice Test Closure Pipe Area Temp Press. Moment Acceleration Test No. Temp Press. Duration Signal Press. lnduced(l)lnduced Test Type ( in2) Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (in- lb) (g's) 10-DR-lS Steam 4.155 Steam 668 2,503 Steam 669 2,503 15 2,035 760 N/A 6.8 ll-DR-4W Water 6.166 Water 647 2,514 Water 658 2,514 15 2,338 625 N/A 5.0 12-DR-3W Water 6.166 Water 450 699 Water 456 699 15 685 260 N/A 8.2

.p.

I 13-DR-?W Water 6.166 Water 451 2,492 Water 460

....... 2,492 10 2,230 420 N/A 7.4

-o 14-DR-2W Water 6.166 Water 112 689 Water 116 689 10 652 5 N/A 8.6 15-DR-5W Water 6.166 Water 643 2,504 Water 658 (Pre load) 2,504 10 2,360 640 25,500 5.3 16-DR-6W Water 6.166 Water 103 2,500 Water 652 Seal 2,500 54 2,320 295 N/A 8.2 Simulation 20-DR-lS Steam 6.166 Steam 657 2,505 Steam 659 2,505 10 2,110 495 N/A 9.2 21-DR-8S/W Transition 6.166 Steam 656 2,496 Water 641 2,496 10 2,360 660 N/A 9.6 22-DR-9W/W Water 6.166 Water 321 2,490 Water 647 Seal 2,490 17 2,310 678 N/A 6.9 Simulation 23-DR-lS . Steam 6.166 Steam 657 2,505 Steam 659 2,505 10 2,110 440 N/A 8.9 24-DR-6W/W Water 6.166 Water 105 2,505 Water 649 Seal 2,505 88 2,360 690 N/A 8.6 Simulation Notes.

-(1) V 1wn corresponds to maximum mom~nt applied while valve was in the .closing process.

(2) Co , d~ to timP prmv w~~ i~ol;it.f!rl. Ar:t.*i~l r.los11rP or.r:1irP.rl ;it ~n 11nr!Pt _rl t. imo ;ift.P.r i~ol;it. inn.

EPRl/WYLE PHASE Ill PORV TEST .DATA TABLE 4.1.l-3b

SUMMARY

OF DRESSER RELIEF VALVE PERFORMANCE Test 10- 11- 12- 13- 14- 15- 16- 20- 21- 22- 23- 24-Number DR-lS DR-4W DR-3W DR-7W DR-2W DR-SW DR-61i'/ DR-lS DR-8S/W DR-9W/W DR-lS DR-6W/W Pre-Test Leakage(!)

Media Steam Water Water Water Water Water Wateir Steam Water Water Steam Water Pressure (psia) 2,587 2,482 690 2;500 700 2,550 2,46'5 2,527 2,500 2,550 2,515 2,515 Temp (OF) 669 645 450 450 104 581 105 671 672 305 670 104 Leak Rate (GPM) 0.0013 0.0013* 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.00"13 .026 0.0013 Transient Performance Total Valve Opening Time (sec) 0.11 0.065 0.07 0.062 0.11 0.075 0.060 0.17 0.11 0.68 0.13 0.062 Valve Flowrate (lb/Hr) 133,200 295,200 262,800 622,800 388,800 302,400 331,200 129,600 324,000 309,600 132,480 316, 800 Corresponding Valve Inlet Press (psia) 2,318 2,422 692 2,320 662 2,410 2,360 2,296 2,400 2,380 2, 280 2,400 I

Corresponding Valve I-'

I-'

Inlet Temp (OF) 658 652 453 456 117 650 636 648 633 638 645 535 Corresponding Valve Outlet Press (psia) 670 610 248 405 2 621 265i 434 638 618 422 627 Corresponding Valve Outlet Temp (OF) 510 494 408 452 117 497 414 454 495 495 453 495 Corresponding Test Time Relative to Open Command (sec) 4.8 4.7 4.5 4.4 4.4 4.7 9.1 4.3 5.1 6.7 0.5 6.0 Inlet Pressure at Beginning of Valve Closure (psia) 2,030 2,340 680 2,230 650 2,370 14.7 2,110 2,360 2,310 2,105 2,120 Total Valve Closure Time (sec) 0.217 0.31 0.30 0.21 0.23 0.31 (2) .21 .35 1. 74 .023 69.15 Post-Test Leakage(!)

Media Steam Water Water Water Water Water Water Steam Water Water Steam Water Pressure (psia) 2,591 2,465 700 2,250 700 2,567 2,244 2,593 2,476 2,490 2,510 2,435 Temp (OF) 646 600 445 415 104 577 389 631 630 480 669 495 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 .0024 .018 .0119 .026 .024 Notes:

( 1) Recorded leakages of .0013 GPM indicate measured values of less than or equal to .0013 GPM.

(2) Valve closure occured at an undetermined time following the isolation of the PORV which occurred approximately 90 seconds after the valve rlflcqrn ~ j'"tr1;d.

4.t.' CROSBY l{LLlE.r Vl\LVL 4.2.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Crosby relief valve model at the Marshall Steam Station, and during Phase II and Phase III of the Wyle Test Program. The foll6wing is the list of tables that contain the "as tested" test matrices and valve performance data for the Crosby relief valve tested at each of the test facilities.

Test "As Tested" Test Valve Performance Facility Matrix Table Data Table Marshall 4.2.l-la 4.2.l-lb Wyle (Phase II) 4.2.l-2a 4.2. l-2b Wyle (Phase III) 4.2. l-3a 4.2.l-3b 4.2.2 Principal Observations

  • Marshall Steam Station The valve fully opened on demand and fully closed on demand during each of the eleven (11) evaluation tests.

Following several successful actuations performed prior to the evaluation tests, the Crosby valve failed to open on demand during 5 attempts and on.

a subsequent test failed to seat properly. When the valve was disassembled and inspected, one bellows weld fracture was found and a bellows assembly part was found to be improperly machined. The bellows was replaced, the bellows assembly was correctly machined and the valve was reassembled for further tests.

The valve was subsequently cycled fifty (50) times (dry, unpressurized) and twenty-eight (28) times (steam, full pressure/flow) including the eleven (11) evaluation tests. The valve fully opened and closed on demand and no bellows leakage occurred during these tests.

4-13

Wyl e Phase II Prior to Wyle Phase II testing, the test valve (a different valve than that test<:d at Marshall) was disassembled and_ inspected. During this inspec-tion. it was noted that the bellows assembly was incorrectly machined as was the case for the Marshall valve. The bellows assembly was correctly machined prior to Wyle testing.

The valve fully opened on demand and fully closed on demand for each of the six (6) test cycles. Upon disassembly after tests were completed, the pilot bellows was found to leak.

Wyle Phase III The same Crosby valv~ tested during Phase II was utilized during Phase III of Wyle testing.

The va l ve f ul l y opened on dem an d and f u11 y c l os e d on demand for e ac h of t he ten (10) test cycles. Upon disassembly after tests were completed, the pilot. bellows was observed to be damaged.

Be 11 ows Damage In all test cases, the valve fully opened on demand and closed on demand even though the bellows had been damaged. Based on this input and the manufacturer's assessment of valve performance with the observed damage, the damage was determined to have no potent i a1 impact on valve operation.

_'{_(l_l_v_E -~pe_r:!__i_~g/_C_l_ns. i n_g__ T_j!1~~-S.

No direct measurement of stem position was possible for the Crosby reli~f valve design. Therefore, no valve opening or closing stroke times have been reported. Estimates of total opening/closing times (time from energize/de-energize signal to full open/closed) have been made and are reported in the Valve Performance Data Table. These estimates were based on a:celerometer or acoustic emission detector and inlet pressure measurements and the mE'thods used were c9nf i rmed by evaluation of data from other valves tested with stem position indication available.

4-14

I r * '

  • Supplementary Information During both Wyle Phase II and Phase III testing, the valve exhibited a tendency not to seal at very low pressures (below 100 psi). Repeated actuations and/or rapid pressurization of the valve inlet were at times required to obtain proper valve seating .

4-15

EPRI/ MARSHALL PORV TEST DATA (3)

TABLE 4.2.1.-la

'.'AS TESTED" MARSHALL TEST MATRIX FOR THE CROSBY RELIEF VALVE CONDITIONS AT VALVE OPENING TRANSIE~T CONDITIONS TEST TEST FLUID VALVE INLET IN Acc:;'*'.ULATOR TEST DURATION VALVE INLET PRESS. WHEN MAXIM0M DISCHARG pl PRESS. TEMP. FLUID F'lESS. TEMP. (SEC) SIGNAL GI VEN NO. TYPE (PSIA) (OF) PIPE PRESS.

(PSIA) (OF) TO CLOSE VALVE (PSIA)

(PSIA)

STEAM STEAM 2495 (SAT.) SAME AS VALVE INLET 66 2335 375 STEAM STEAM 2485 (SAT.) 25 2350 385 3 STEAM STEAM 2455 (SAT.) 21 2335 385 4 STEAM STEAM 2455 (SAT.) 21 2330 375 5 STEAM STEAM 2455 (SAT.) 18 2335 385 6 STEAM STEAM 2485 (SAT.) 53 2335 135 STEAM STEAM 2485 (SAT.) 22 2345

.p, 135 I

....... 8 STEAM STEAM 2450 (SAT.) 28 2315

J) 135 STEAM STEAM 2435 (SAT.) 25 2310 85 (4) 10
  • STEAM STEAM 2465 {SAT.) 24 2350 135 11 STEAM STEAM 2475 (SAT.) (2) i 2325 375 NOTES:

{!) Maximum Quasi steady discharge pipe pressure.

(2) Not recorded.

(3) Test results are for evaluation tests only. Total of 31 supplementary valve actuation cycles were performed under similar conditions.

{4) Downstream pressure Jppears to be anomalous.

EPRI I MADSHALL rn:iv TEST TABLE 4.2.l-lb nAH

SUMMARY

OF CROSBY RELIEF VALVE PERFORMANCE (3)

  • FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS. COMMOHS Vt'll VC-TOTAL VAL VE (1) VAL VE INLET OUTLET FLOW VALVE INLET TEST TEST OPENING TIME TOTAL VALVE (2) LEAKAGE FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP.

NO. TYPE (SEC) (PSIA) (OF) RATE (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM)

STEAM 0.290 STEAM 2335 (SAT.) 375 168,000 0.150 STEAM 2495 (SAT.) 0.057 A pre-operational leakage

  • 2 test showed 0.904 GPM leakage STEAM 0.380 * * *
  • 0.150 3 STEAM 0.350 *
  • 0.150 *
  • 4 STEAM 0.350 * .* 0.150 * *
  • STEAM 0.380
  • 0.150 STEAM 2495 (SAT.) 0.026 6 STEAM 0.320 STEAM 2335 (SAT.) 135 168,000 0.150
  • STEAM 0. 320 * * *
  • 0.150
  • B STEAM 0.350 * *

~

0.150 *

  • STEAM 0.300 I

.......

  • 0.160 * * *

'-I 10 STEAM 0.300 * * * *

  • 0. 140 * * *
  • 11 STEAM 0.370 0.150 STEAM 2485 (SAT.) 0.045
  • not applicable to this test NOTES:

(I) Opening time measured from t me of energizing solenoid until valve reaches full open position.

(2) Closing time measured from t me of de-energizing solenoid until valve reaches full closed position, (3) Test results are for evaluat on tests only. Total of 31 supplementary* valve actuation tests were performed under similar conditions.

EPRI/ WYLE roPV HSi DATA TABLE 4.2.l-2a "AS TESTED" WYLE PHASE II TEST MATRIX FOR THE CROSBY RELIEF VALVE IN IT !AL CONDITIONS TRANSIENT COHDITIOMS

  • .;..L Vt 1i~Lt. I ( l i ~;i ;...;:,,..,>.J::vL;,;,,:;r;. " \/[;" l'ILET MAXIMUM (2) QUASI STEADY DURATION PRESS. WHEN DISCHARGE MAXIMUM TEST TEST FLUID PRESS. TEMP. FLUID PRESS. TEMP; (SEC) SIGNAL GI VEN PIPE PRESS. PILOT LINE NO. TYPE (PSIA) (OF) (PSIA) (OF) TO CLOSE VALVE (PSIA) B. p.

PSIA) PSIA CR-1-S STEAM STEAM 2150 672 SAME AS VALVE INLET 15 1920 60 945 CR-2-S STEAM STEAM 2495 671 SAME AS VALVE INLET 2140 560 )1000 (3)

CR-3-W WATER WATER 680 376 SAME AS VALVE INLET JS 618 125 200 CR-5-\1 WATER WATER 2510 634 SAME AS VALVE INLET 15 2280 155 775 CR-6-W WATER WATER 2502 505 SAME AS VALVE INLET 19 2100 315 438 CR-7-W WATER WATER 2510 446 SAME AS VALVE INLET 18 2000 230 661 NOTES:

(1) Fluid conditions at the valve inlet irmiediately prior to actuation of test valve.

(2) Maximum Quasi steady discharge pipe pressure.

(3) The 1000 PSIA pressure sensor was over-ranged in this test.

EPRI/WYLE PHASE II PORV TEST DATA TABLE 4.2.l-2b

SUMMARY

OF CROSBY RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL '/,\LVE (!) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENI~G TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (Of) (GPM)

CR-1-S STEAM 0.10 STEAM 2280 661 57 162,000 0.20 STEAM 2000 637 0.0 CR-2-S STEAM 0.07 STEAM 2420 671 560 165,600 0.14 STEAM 2485 653 0.008 CR-3-W WATER 0.10 WATER 622 382 122 410,400 0.20 WATER 660 386 0.0 CR-5-W 11,\TER 0.10 WATER 2400 645 150 385,200 0.20 WATER 2500 651 0.0 CR-6-W WATER 0.05 WATER 2300 505 290 720,000 0.10 WATER 2500 516 0.0 CR-7-W WATER 0.07 WATER 2280 448 215 792,000 0.10 WATER 2500 456 a.a

+::>

I l.D NOTES:

(1) Opening time measured from time of energizing solenoid until valve reaches full open position.

(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.

EPRI/WYLE PHASE Ill PORV TEST DATA TABLE 4.2.l-3a "AS TESTED" WYLE PHASE II I TEST MATRIX FOR THE CROSBY RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS Valve Inlet Back- At Valve Inlet In Accumulator Pressure Maximum Maximum Maximum pressure at Discharge Bending Valve Orifice Test Closure Pipe Moment Acceleration Area Temp Press. Temp Press. Duration Signal Press. Induced(2)Induced Test No. Test Type ( in2) Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psia) (psi a) (in- lb) ( g.' s) 25-CR-lS Steam 10.0 Steam 656 2,505 Stearn 659 2,505 10 2,050 (1) N/A 8.0 26-CR-6S Steam 9.62 Steam 657 2,505 Steam 659 2,505 10 2,037 (1) 31,600 6.7 (Pre load) 27-CR-2W Water 9.62 Water 104 694 Water 108 694 10 620 3 N/A 8.2

.j::>

I N 28-CR-3W Water 9.62 Water 437 695 Water 448 695 10 655 160 N/A 11.6 0

29-CR-lS Steam 11. 7 Steam 656 2,505 Steam 659 2,505 10 2,050 74 N/A 6.4 30-CR-lS Steam 8.82 Steam 656 2,505 Steam 658 2,505 10 2,060 380 N/A 10.4 31-CR-4S/W Trans it ion 8.82 Steam 656 2,510 Water 649 2,510 15 2,313 (1) N/A 9.2 32-CR-SW/W Water 8.82 Water 469 2,505 Water 646 2,505 15 2,290 560 N/A 8.2 Seal Simulation 33-CR-7W/W Water 8.82 Water 294 2,505 Water 648 2,505 15 2,300 580 N/A 8.0 Seal Simulation 34-CR-BW/W Water 8.82 Water 118 2,500 Water 645 2,500 15 2,290 575 N/A 9.4 Seal Simulation Notes:

( 1) PS-4 was inoperative during this test.

(2) shown corresponds to maximum moment applied when valve was in the g/closing process

  • EPRI/WYLE PHASE III PORV TEST DATA TABLE 4.2.l-3b

SUMMARY

OF CROSBY RELIEF VALVE_ PERFORMANCE Test 25- 26- 27- 28- 29- 30- 31- 32- 33- 34-Number CR-lS CR-6S CR-2W rR-3W ('O _ ! S CR-lS CR-4S/W CR-SW/W CR-7W/W CR-BW/W Pre-Test Leakage(!)

Media Steam Steam Water Water Steam Steam Water Water Water Water Pressure (psia) 2,550 2,490 739 729 2,512 2,550 2,500 2,500 2,323 2,586 Temp (OF) 647 668 109 407 669 670 580 450 280 115 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.005 Transient Performance Total Valve Opening Time (sec) 0.15 0.17 0.07 0.09 0.15 0.18 0.16 0.08 0.08 0.08 Valve Flowrate (lb/Hr) 158,400 151,200 486,000 316,800 158,400 160,200 316,800 367' 200 374,400 388,800 Corresponding Valve

+>> Inlet Press (psia) 2,276 2,090 630 663 2,250 I

2,265 2,387 2,390 2,390 2,360 N Corresponding Valve Inlet Temp (OF) 645 634 108 440 644 644 644 636 632 632 Corresponding Valve Outlet Press (psia) (2) (2) 1. 153 670 365 (2) 490 494 503 Corresponding Valve Temp (OF) 313 342 109 361 316 430 454 465 467 470 Corresponding Test Time Relative to Open Corrwnand (sec) 4.1 8.3 6.3 3.7 4.8 4.5 6.9 4.9 4.7 6.4 Inlet Pressure at Beginning of Valve Closure {psia) 2,045 2,035 620 650 2,050 2,060 2,310 2,300 2,300 2,290 Total Valve Closure Time (sec) 0.15 0.14 0.18 0.27 0.13 0.12 0.25 0.24 0.29 0.55 Post-Test Leakage(!)

Media Steam Steam Water Water .Steam Steam Water Water Water Water Pressure (psia) 2,495 2,500 698 695 2,555 2,540 2,530 2,590 2,417 2,510 Temp (OF) 595 668 107 382 672 671 587 523 408 375 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 1.13 0.0013 0.0013 0.0013 0.0013 0.004 Notes:

( 1) Re.corded leakages of .0013 GPM indicate measured values of less than or equal to .0013 GPM (2) PS-4 in-operative

4.3 TARGET ROCK RELIEF VALVE 4.3.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Target Rock relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance cjata for the Target Rock relief valve tested at each of the test facilities.

Test 11 As Tested" Test Valve Performance Facility Matrix Table Data Table Marshall 4.3.l-la

  • 4.3.l-lb Wy l e (Phase I I I ) 4.3.l-2a 4.3.l-2b 4.3.2 frincipal Observations M1rshall Steam Station
  • Tile va.l ve fu 11 y opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles.

WJle Phase III Tile valve fully opened on demand and fully closed on demand in eleven (11) oi the twelve (12) test cycles. The valve did not close on demand when the ftill pressure 2500 psi, water seal simulation test (test number 7-TR-7W) was performed. The water just upstream of the valve was llOOF water. For this test, the valve opened on.demand. Upon de-energizing the valve for closure, the valve remained opened for approximately 12 seconds and then closed at an inlet pressure of 2130 psia. The valve was removed from the tE'st facility and disassembled by the Target Rock representative following this test, test 9-TR-6W and again upon completion of all testing of this valve design. No damage was observed which might affect the ability of the valve to open/close on demand .

  • 4-23

Valve Opentng/Closing Times Magnetic limit switches were installed on the casing surrounding the valve stem which provided an indication of stem position. Data from these limit switches was used to obtain stroke and total opening times during the Marshall test. During Wyle testing of this valve, these limit switches began to exhibit sensitivity to test vibrations. Therefore, for all Wyle tests of this valve, stroke times are not reported and estimates of total opening/closing times were obtained utilizing accelerometer and inlet pressure measurements. This method for estimating opening/tlosng times was confirmed by evaluation of data from other valves tested with direct stem position indication available .

4-25

EPRI/ MARSHALL PORV TEST DATA (3)

TABLE 4.3.l-la "AS TESTED" MARSHALL TEST MATRIX FOR THE TARGET ROCK RELIEF VALVE CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS

  • TEST VALVE INLET IN ACCUMULATOR TEST DURATION VALVE INLET PRESS. WHEN MAXIMUM DISCHARG p)

TEST FLUID PRESS. TEMP. FLUID PRESS. TEMP. (SEC)

NO. TYPE SIGNAL GIVEN PIPE PRESS, (PSIA) (OF) (PSIA) (OF) TO CLOSE VALVE (PSIA)

(PSIA)

STEAM STEAM 2475 (SAT. J SAME AS VALVE INLET 68 2310 465 2 STEAM STEAM 2455 (SAT.) 31 2310 465 STEAM STEAM 2435 (SAT.) 59 2295 465 4 STEAM STEAM 2445 (SAT.) 25 2320 465 STEAM STEAM 2455 (SAT.) 25 2335 475 STEAM STEAM 2455 (SAT.) 60 2295 155 STEAM STEAM 2445 (SAT.) 28 2305 155

~

I 8 STEAM STEAM 2425 (SAT.)

N 26 2295 155 m 9 STEAM STEAM 2455 (SAT.) 29 2335 155 10 STEAM STEAM 2475 (SAT.) 30 2335 155 11 STEAM STEAM 2455 (SAT.) I (2) 2325 455 NOTES:

(I) Maximum Quasi steady discharge pipe pressure.

(2) Not recorded.

(3) Test results are for evaluation tests only. Total of 23 supplementary valve actuation cycles were performed under similar conditions .

EPRI /

  • MARSHALL PORV TEST DATA ( 3)

TABLE 4.3.1-lb SUl+lARY OF TARGET ROCK RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VALVE (1) VAL VE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TrME MEDIA PRESS. TEMP. . RATE NO. TYPE (SEC) (PSIA} (OF) (PSIA) (LBM/HR} (SEC) (PSIA) (OF) (GPM)

STEAM 0.440 STEAM 2310 (SAT.) A pre-operational leakage 465 170,000 0.220 STE~.M 2455 (SA~.}

n n u.u test showed 0.0 GPM leakage 2 STEAM 0.520 * * * .

  • 0.210 *
  • STEAM 0.595 . * *
  • 0.200 *
  • STEAM 0.600 * *
  • 0.200 *
  • 5 STEAM 0.610 " * * *
  • 0.200 SHA'1 2475 (SAT.) o.o 6 STEAM 0.490 STEAM 2295 (SAT.) 155 169,000 0.210 * *
  • STEAM 0.520 .. 0.210 * *
  • 8 STEAM 0. 570 * * * *
  • 0.190 * * * *

..,,. 9 STEAM 0.620 * * *

  • 0.170 * " * .

N I

-...J JO STEAM 0.650 * * *

  • 0.190 * . *
  • 11 STEAM 0.585 * * *
  • 0.210 STEAM 2460 (SAT.) 0.0 not applicable to this test NOTES:

(1) Opening time measured from time of energizing solenoid until valve reaches full open position.

(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position, (3) Test results are for evaluation tests only. Total of 23 supplementary valve actuation tests were performed under similar conditions.

EPRl/WYLE Phase Ill PORV TEST DATA TABLE 4.3.>Zo "AS TESTED" WYLE Pll/\SE Ill TEST Ml\TRIX FOR THE TARGET ROCK RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS Valve Inlet Back- At Valve Inlet In Accumulator Pressure Maximum Maximum Maximum pressure at Discharge Bending Valve Orifice Test Closure Pipe Moment Area Temp Acceleration Press. Temp Press. Duration Signal Press. Induced(l)Induced Test No. Test Type ( in2) Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (in-lb) (g's) 1-TR-lS Steam 9.62 Steam 660 2521 Steam 670 2521 7 2132 320 N/A 5.0 2-TR-lS Steam 9.62 Steam 669 2504 Steam 670 2504 7 2134 330 N/A 8.5 3-TR-3W Water 9.62 Water 447 715 Water 454 715 70 639 170 N/A 8.7 4-TR-5\.1 Water 9.62 Water 645 2536 Water 653 2536 15

-+:>

2293 450 N/A 3.6 I

N OJ 5-TR-2W Water 9.62 Water 114 690 Water 114 690 10 616 1 N/A 13.3 6-TR-4W Water 9.62 Water 451 2508 Water 461 2508 10 2196 395 N/A 7.4 7-TR- 7W Water 9.62 Water 113 2505 Water 656 2505 27 Seal 2271 520 N/A 5.6 Simulation 8-TR-5W Water 9.62 Water 648 2494 Water 658 24g4 10 2320 430 N/A 4.4 9-TR-6W ~later 9.62 Water 645 2490 Water 657 2490 10 2302 425 N/A 8.4 17-TR-lS Steam 9.62 Steam 657 2510 Steam 659 2510 10 2028 325 N/A 4.9 18-TR-BS Steam 9.62 Steam 656 2505 Steam 658 2505 (Pre load) 10 2020 315 32,900 3.3 l9-TR-9S/W Trans it ion 9.62 Steam 656 2500 Water 642 2500 10 2310 435 N/A 5.2 Notes:

(1) Value shown corresponds to maximum moment applied while valve was in opening/closing process

EPRJ/WYLE Phase III PORV TEST DATA TABLE 4.3.l-2b

SUMMARY

OF TARGET ROCK RELi EF VALVE PERFORMANCE Test 1- 2- 3- 4- 5- 6- 7- 8- 9- 17- 18- 19-Number TR-lS TR-lS TR-3W TR-SW TR-2W TR-4W TR-7W TR-SW TR-6W TR-lS TR-BS TR-9W/W Pre-Test Leakage (1)

Media Steam Steam Water Water Water Water Water Water Water Steam Steam Water Pressure (psia) 2,500 2,512 675 2,515 673 2,545 2,505 2,521 2,478 2,505 2,485 2,500 Temp (OF) 668 666 447 645 114 448 113 583 589 .668 668 590 Leak. Rate (GPM) 0.0013 0.0013 0.0013 0.0013 .0021 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) 0.35 .300 0.28 0.25 0.21 0.26 0.20 0.29 0.27 0.396 0.365 0.30 Valve Flowrate (lb/Hr) 171, 844 167,040 266,400 367 ,200 442,800 698,400 (2) 356,400 360,000 165,600 162,000 377,300

~

Corresponding Valve I

Inlet Press. (psia) 2,339 2,260 669 2,394 635 N

l..D 2,280 N/A 2,386 2,363 2,243 2,225 2,364 Corresponding Valve Inlet Temp (OF) 664 659 451 649 115 457 N/A 654 650 644 643 633 Corresponding Valve Outlet Press. (psia) 329 325 167 444 0.6 390 N/I\ 430 423 320 312 430 Corresponding Valve Outlet Temp: (Of) 416 414 372 460 115 444 N/A 460 460 411 412 455 Corresponding Test Time Relative to Open CormJand (sec) 2.0 4.8 4.0 5.2 3.2 4.4 N/A 4.3 4.3 4.6 4.9 5.1 Inlet Pressure at Beginning of Valve Closure (psia) 2,125 2,130 640 2,290 620 2,190 Total Valve Closure Time *~. 130 2,320 2,300 2,025 2,015 2,310 (sec) 0.31 .31 .690 0.44 0.84 0.55 12.33 0.46 0.43 0.232 0.24 0.25

~ost-Test Leakage (1)

Media Steam Steam Water Water Water Water Water Water Water Steam Steam Wate.r Pressure (psia) 2,500 2,500 700 2,515 669 2,523 2,356 2,415 2,405 2,525 2,500 2,482 Temp (OF) 668 665 456 650 112 454 432 552 609 669 668 632 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.12(3) 0.0013 0.0013 0.0013 0*.0013 0.0013 Notes:

(1) Recorded leakages of .0013 GPM indicate measured values less than or equal to .0013 GPM (2) VPnturi d~lta pressure sensor over-ranQPd (3) This leakage is considered an upper bound as it includes any test facility by-pass valve packing leakage rates.

  • 4.4 CON1ROL COMPONENTS RELifF VALVE 4.4.1 "As Tested" Test Matrices and Valve Performance Data Tests were_ performed on the Control Components relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Control Components relief valve tested at each of the test facilities.

Test "As Tested" Test Valve Performance Facility Matrix Table Data Table Marsha 11 4.4.l-la 4.4.l-lb Wyle (Phase III) 4.4.l-2a 4.4. l-2b 4.4.2 Principal Observations Marsh1ll Steam Station The v.ilve fully opened on demand and fully closed on demand for each of the seven~een (17) evaluation test cycles.

The valve fully opened and closed on demand during all seven (7) tests perfo~med with normal air supply (air utilized to open Bnd close valve) avail ible. An additional ten (10) tests were performed on this valve utili 'ing the spring force only to close the valve (without air assist on closu*'e). During all of these tests, the valve opened fully on demand.

Howev,~r, during five (5) of these tests, the valve exhibited delay on closu1'e. Closure delay times ranging from two (2) to forty (40) seconds were _c,bserved. Closure delays of less than three ( 3) seconds were observed under steam and steam/preload conditions. Closure delays of twenty (20) and iorty (40) seconds were observed under 2500 psia, 6500f water condi~ions. In all cases where valve closure delays were observed, full closui*e occurred at an inlet pressure at or above 2035 psia.

4-31

I I 1 ,

Tests under each of the conditions which resulted in closure delays were repeated utilizing air for both opening and closing the valve. In all such tests. the valve opened and closed on demand.

Following the first test resulting in a significant closure delay and again upon completion of testing, the valve was disassembled and inspected by the Control Components representative. No damage was observed which might affect the ability of the valve to open or close on demand.

4-33

EPRI/ MARSHALL PORV TEST DATA ( 3)

TABLE 4.4. I-la "AS TESTED" HAR SHALL TEST MATRIX FOR THE CONTROL COMPONENTS RELIEF VALVE CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS VALVE INLET IN ACCUMULATOR TEST

  • DUflA TION VALVE INLET PRESS. llHEN MAXIMUM OISCHARG P'

TEST TEST FLUID PRESS. TEMP. FLU!O PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS.

NO. TYPE (PSIA) (Of) (PSIA) (OF) TO CLOSE VALVE (PSIA)

PSIA)

STEAM. STEAM 2455 (SAT.) SAME AS VALVE INLET 67 2155 615 STEAM STEAM 2445 (SAT.) 30 2175 615 STEAM STEAM 2425 (SAT.) 31 2175 615 STEAM STEAM 2425 (SAT.) 37 2175 615 STEAM STEAM 2435 (SAT.) 37 2195 615

~

I w 6 STEAM STEAM 2435 (SAT.) 24 2)65 615

~

STEAM STEAM 2405 (SAT.) 25 2145 615 8 STEAM STEAM 2395 (SAT.) 27 2145 615 9 STEAM STEAM 2455 (SAT.) 65 2155 220 10 STEAM STEAM 2445 (SAT.) 18 2095 215 11 STEAM STEAM 2435 (SAT .1 20 2175 215 12 STEAM STEAM 2435 (SAT.) 18 2180 215 13 STEAM STEAM 2425 (SAT.) 23 2170 215 14 STEAM STEAM 2405 (SAT.) 17 2155 215 15 STEAM STEAM 2395 (SAT.) 19 2150 215 16 STEAM STEAM 2405 (SAT.) 22 2155 215 17 STEAM STEAM 2415 (SAT.) (2) 2170 615 NOTES:

(I)

( 2)

Maximum Quast steady disc~arge pipe pressure.

Not recorded.

( 3) Test results are for evaluation tests only. Total of 33 supplementary valve actuation cycles were perfonned under similar conditions .

EPRI I MARSHALL PORV TEST DATA ( 3)

TABLE 4.4.l-lb FLOW MEASUREMENT CONDITIONS Lo!<~GE HEASUREHENTS COHHENTS VALVE TOTAL VALVE (I) VALVE !NLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING T!ME FLUID PRESS. TEHP. PRESS. RATE CLOSING TIME MED!~ PRESS. TEHP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM)

A pre-operational leakage STEAH I.BO STEAM 2155 (SAT.) 605 225,000 I. 00 . STEt.~ 2445 (SAT. J 0.026 test showed 0.0 GPM leakage STEA.~ I. 70 *

  • 1.00
  • STEAM I. 70 *
  • 1.00 *
  • 4 STEAM I. 60
  • 1.00
  • STEAM I. 65
  • 1.00 STE~u 2435 [SAT.) 0.026 STEAM  !. 70
  • 1.95
  • S7t:AM  !. 70 * * *
  • I. 60 *

-+::>

I 8 STEAM  !. 65 * * *

  • 1. 5D STEAM 2455 (SAT. J 0.108 w

(Jl 9 STEAM I. 70 STEAM 2155 (SAT.) 215 225,000 1.00

  • 10 STEAM  !. 70 * * * * ** l.00 . *
  • 11 STEAM 1.60 * * *
  • 1.00 *
  • 12 STEAM  !. 65 *
  • I. DO * * *
  • 13 STEAM 1.60 * * * *
  • l.00 . .

14 STEAM I. 7D * *

  • 1. 70 *
  • 15 STEAM I. 70 * . *
  • I. 65 . * * .

16 STEAM 1.65 * " * *

  • 1.80 *
  • 17 STEAM (3) * * (SAT. J 0.026
  • I.OD STEAM 2415 not applicable to this test

!IOTES:

(I) Opening time measured from til"e of energizing solenoid until valve reaches full open position.

(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position. . .

(3) Test results are for evaluation tests only. Total of 33 supplementary va*lve cycles were performed :.nder similar conditions.

EPRI/WYLE Phase y TESI DAIA TABLE 4 . . -2a "AS TESTED" WYLE PHASE III TEST MATRIX FOR THE CONTROL COMPONENTS RELIEF VALVE INITIAL CONDITIONS(l) TRAnSIENT CONDITIONS Valve Inlet Valve Inlet Accumulator Pressure Maximum Maximum Maximum at Discharge Bending Valve Test Closure Pipe Moment Acceleration Temp Press. Temp Press. Duration Signal Press.(2) Induced(3)Induced Test No. Test Type Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (in-lb) (g's) 35-CC-lS Steam Steam 683 2,760 Steam 678 2,760 6 2,374 468 N/A 12.5 36-CC-2S Steam Steam 683 2,750 Steam 678 2, 750 6 2,280 416 N/A 5.3 (Failed Air) 37-CC-3S Steam Steam 670 2,535 Steam 665 2,535 4 2,370 377 18,000 6.2 (Preload, Failed Air) 38-CC-5W Water Water 440 2,536 Water 449 2,536 5 2,180 400 N/A 13.5 (Failed Air)

I w 39-CC-6W Water Water 103 475 Water 107 475 10 421 15 N/A 9.5 (Failed Air) 40-CC-4W Water Water 392 524 Water 397 524 15 473 145 N/A 5.1 (Failed Air) 41-CC-7W Water Water 633 2,535 Water 654 2,535 25 2,342 480 N/A 6.1 (Failed Air) 42-CC-lS Steam Steam 683 2, 760 Steam 678 2,760 6 2, 340 450 N/A 11.3 43-CC-7W Water Water 645 2,538 Water 649 2,538 2,337 6 510 N/A 7.7 44-CC-7W Water Water 644 2,540 Water 656 2,540 48 2,330 490 N/A 5.5 (Failed Air) 45-CC-lS Steam Steam 683 2,760 Steam 678 2,760 4 2,408 453 N/A 10.7 46-CC-BS/W Trans it ion Steam 664 2,530 Water 647 2,530 6 2,320 500 N/A 11.0 (Failed Air) 47-CC-3S Steam Steam 683 2,760 Steam 678 2, 760 4 2,410 475 39,000 11.4 (Pre load Failed Air)

EPRl/WYLE Phase Ill PORV TEST DATA TABLE 4.4.l-2a (cont'd)

"AS TESTED" WYLE PHl\SE III TEST MATRIX FOR THE CONTROL COMPONENTS RELIEF VALVE (corn' oJ INITIAL CONDITIONS(l) TRANSIENT CONDITIONS_

Valve Inl1;t Valve Inlet Accumulator Pressure Maximum Maximum Maximum at Discharge Bending Valve Test Closure Pipe Moment Acceleration Temp Press. Temp Press. Duration Signal Press.(2) Induced lriduced Test No. Test Type Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psia) (psia) (in-lb) (g's) 48-CC-9W/W Water Water 135 2,540 Water 648 2,540 6 2,340 515 N/A 3.9 Seal Simulation 49-CC-2S Steam Steam 683 2,760 Steam 678 2, 760 l 2,380 440 N/A 11.4 (Failed Air) 50-CC-3S Steam Steam 683 2,760 Steam 678 2,760 2,410 460 38,000 12.2 (Pre load)

I w 51-CC-3S Steam

<.O steain 683 2, 760 Steam 679 2, 760 2,450 473 36,800 13.8 (Pre load Failed Air)

(1) GN 2 PORV Actuation Ullage pressure for all tests was 85 (+/-_ 5) psig.

(2) No Back Pressure orifice was used in the Control Components PORV testing.

(3) Value shown corresponds to maximum moment applied while valve was in opening/closing process.

EPR!/WYLE Phase Ill PORV TEST DATA TABLE 4.4.l-2b SUMMl\RY OF CONTROL COMPONENTS VALVE PERFORMANCE Test 35- 36- 37- 38- 39- 40- 41- 42- 43- 44- 45- 46-Number CC-lS CC-25 CC-35 CC-5W CC-6W CC-4W CC-7W CC-lS CC-7W CC-7W CC-lS CC-85/W Pre-Test Leakage ( 1)

Media Steam Steam Steam Water Water Water Water Steam Water Water Steam Ii ate~

Pressure (psia) 2, 770 2, 760 2,480 2,265 499 520 2,700 2, 740 2,535 2,340 2, 765 ...

2 ,,. , ...

Temp (OF) 682 680 670 412 94 402 640 679 641 637 683 62Cl Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 o. 0013 Transient Performance Total Valve Opening Time (sec) 1.07 1.15 .78 0.69 0.93 1.07 1.05 1.83 0. 76 0.87 1.27 1. 22 Main Disc Opening Time (sec) 0.42 0.42 .43 0.43 0.75 o. 71 0.39 0.66 0.49 0.42 0.61 0.f3 Valve Flowrate (lb/Hr) 257,400 258,500 237,600 900,000 478,800 356,400 489,600 259,200 511,200 482,400 255,600 518,!C*J I

Corresponding Valve f-' Inlet Press (psia) 2,420 2,407 2,320 2,194 426 482 2,370 2,400 2,352 2,345 2,420 2, 3.!5 Corresponding Valve Inlet Temp (OF) 667 666 664 450 116 399 654 677 649 656 666 6.!0 Corresponding Valve Outlet Press (psia) 380 378 350 400 1. 145 475 380 489 476 375 !83 Corresponding Valve Outlet Temp (OF) 432 430 370 430 105 355 460 432 462 260 433 462 Corresponding Test Time Relative to Open Corrmand (sec) 4.3 4.1 1. 9 4.4 4.5 6.5 4.5 5.0 4.9 5.6 4.5 4.5 Inlet Pressure at Begining of Valve Closure {psia) 2,330 2 ,275 2,225 2 ,180 418 466 2,125 2,320 2,320 2,035 2,380 2,3i0 Total Valve Closure Time (sec) 0.68 1.24 2.65 0.79 1.05 1.66 20.65 0.69 1.09 42.24 0. 71 0. 76 Main Disc Closing Time (sec) 0.20 0.19 0.11 0.27 0.48 0.35 0.:18 0.16 0.21 3.8 0.18 0.20

  • EPRI/WYLE Phase III PORV TEST DATA TABLE 4.4.l-2b (cont'd)

SUMMARY

OF CONTROL COMPONENTS VALVE PERFORMANCE Test 35- 36- 37- 38- 39- 40- 41- 42- 43- 44- 45- 46-Number CC-IS CC-25 CC-3S CC-.5W CC-6W CC-4W CC-711 CC-lS CC-7W CC-7W CC-15 CC-85/W Post-Test leakage (Spring Closure) (1)

Media N/A Steam Steam Water Water Water Water N/A N/A Water N/A N/A Pressure (psia) N/A 2,450 2,575 2,545. 521 535 2,510 N/A N/A 2,445 N/A N/A Temp (OF) N/A 646 630 423 100 375 620 N/A N/A .620 N/A N/A Leak Rate (GPM) N/A 0.05 0.04 0.0013 0.0013 0.0013 0.169 N/A N/A 0.104 N/A N/A Post-Test leakage (Spring and Air Closure) (1)

Media Steam Steam Steam Water Water Water Water Steam Water Water Steam Water Pressure (psia) 2,670 2,425 2,575 2,605 521 540 2,525 2,7go 2, 705 2,495 2,680 2,440 Temp (Of) 668 636 630 415 100 35g 610 55g 625 612 678 638

+:> Leak Rate I 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0018 0.0013 0.0013

+:> o.002g 0.0013 0.0013 w

EPRI/WYLE Phase III PORV TEST DATA IABLE 4.4.l-2b (cont'd)

SUMM/\RY OF CONTROL COMPONENTS V/\LVE PERFORM/\NCE Test 47- 48- 49- 50- 51-Number CC-35 CC-9W/W CC-2S CC-3S CC-3S Pre-Test Leakage Media Steam Water Steam Steam Steam Pressure (psia) 2, 780 2,478 2,790 2,788 2, 790 Temp (OF) 685 125 683 684 684 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) .58 1.84 0.50 1.17 0.67 Main Oise Opening Time (sec) .395 1.04 0.302 0.52 0.46 Valve Flowrate (lb/Hr) 255,600 558,000 262,800 262,800 270,000

"""'I Corresponding Valve

+:>

Ul Inlet Press (psia) 2,465 2,365 2,505 2,465 2,525 Corresponding Valve Inlet Temp (OF) 672 587 671 66g 673 Corresponding Valve Outlet Press (psia) 385 500 380 388 397 Corresponding Valve Outlet Temp (OF) 435 460 422 432 410 Corresponding Test Time Relative to Open Command (sec) 2.8 4.2 2.5 3.6 2.2 Inlet Pressure at Beginning of Valve Closure (psia) 2,220 2,335 2,210 2,385 2,390 Total Valve Closure Time (sec) 3.80 o. 78 3.57 0.68 1.17 Main Disc Closing Time (sec) 0.32 0.22 0.26 0.23 0.22

  • EPRl/WYLE Phase III PORV TEST DATA TABLE 4.4.l-2b (cont'd}

SUMMARY

OF CONTROL COMPONENTS VALVE PERFORMANCE Test 47- 48- 49- 50- 51-Number CC-3S CC-9W/W CC-2S CC-3S CC-3S Post-Test leakage (Spring Closure)

Media Steam N/A Steam N/A Steam ( 1) Recorded leakage of 0.0013 GPM indicate measured Pressure (psia) 2,750 N/A 2, 715 N/A 2,795 values less than or equal to 0.0013 GPM.

Temp (OF) 654 N/A 679 N/A 661 leak Rate (GPM) 0.085 N/A 0.0013 N/A 0.078 Post-Test Leakage (Spring &

Air Closure)

Media Steam Water Steam N/A Steam Pressure (psi a) 2, 765 2,522 N/A 2, 780 2, 765 Temp (OF) 643 395 N/A 672 657 leak Rate 0.0013 0.0013 N/A 0.0013 0.0013

+::>

I

+::>

-...J

~ I ' I

  • 4.5 MASONE1LAN RELIEF VALVE 4.5.1 "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Masoneilan relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program. The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Masoneilan relief valve tested at each of the test facilities.

Test "As Tested" Test Valve Performance Facility Matrix Table Data Table Marsha 11 4.5. 1-la 4.5.l-lb Wyle (Phase III) 4.5.l-2a 4.5.l-2b 4.5.2 Principal Observations Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles.

During several supplementary tests performed prior to the evaluation tests, the valve opening stroke times were in excess of three (3) seconds.

The regulated air supply pressure to the air operator was increased from approximately 55 to 60 psig for all evaluation tests.

Wyle Phase III A total of eleven te~.ts were performed. For all tests, the valve opened and closed on demand. The valve was disassembled and inspected by the Masoneilan valve representative. No damage was observed that would affect future valve performance. The cage to body gasket had partially "washed out" during testing .

  • 4-49

The valv(' opening time exhibited a sensitivity to the air supply system pressure supplied to the valve's air actuator. For the tests performed, air supply accumulator pressures were varied between 54+1 and 59+1 PSIG resulting in total valve opening times ranging from 1.6 to 6.4 seconds.

Valve opening times were also found to be sensitive to the size of tubing.

used in the air supply system. Figure 4.5.2-1 depicts the air supply system utilized during testing. The original air supply system utilized during the checkout of the Masoneilan valve had 1/4" tubing between the solenoid valve and the air actuator, as recommended in the valve manufacturer's instruction manual. When the tubing size was increased to 1/2", dry stroke times in the range of 2 seconds were obtained.

Table 4.5.2-1 summarize'., the observed relationship between accumulator pressure, actuator inlet pressure, and valve opening stroke times.

4-50

I I ) I TABLE 4.5.2-1

SUMMARY

OF RELATIONSHIP BETWEEN AIR SUPPLY PRESSURE AND MASONEILAN RELIEF VALVE OPENING TIME Air Supply Accumulator Pressure Air Actuator Total (Equal to Inlet Press Valve Regulator 2 Seconds Opening Setting) After Actuation Time Conditions (Psig) Signal (Psig) (Sec)

See TABLE 4.5.l-2a 5;~-MN-lS 54+/-1 53.0 1.64 5:l-MN-2S 54+/-1 52.0 1.84 54-MN-4W 54+/-1 51.5 3. 7J 5~i-MN-3W 54+/-1 48.5 6.39 56-MN-SW 56+/-1 52.5 3.08 5?-MN-3W scr:.1 53.0 2.54 SB-MN-SW 59+/-1 52.0 1.95 60-MN-7S/W 59.:!:.l 53.0 1. 81 61-MN-SW/W 59.:!:.l 53.0 1.97 62-MN-9W 59.:!:.l 53.5 3.08 Note: All tests shown above utilized 1/2 11

(.435 11 I.D.) diameter: air supply t11hinn hPtwPPn c::.nlPnnirl ;mrl .:iir .:1rt11.:1tnr 4-51

,--~1 /A ,--~ uC(; Power In

.0

_ _ L?

/

cY PS-5 Solenoid P'

(1" orifice)

'I B

'----- ----** 6 ,, ____ _,_I,.....

c

'~

1211 Tubing to !4 11 Pipe Reducer(.172" IIJ) 14' 6" B=. .435 ID Tubing C= . 935 ID Tubing Regulator NC= Normally Closed

-L 100 psi supply Nitrogen Accumulator (Volume, 4F+ 3 )

Figure 4.5.2~1 Air Supp'y System

{Wyle Phase III)

  • 4-53 Ma so neil an PORV

EPRI/ MARSHALL PORV TEST DATA (3)

TABLE 4.5.1-la "AS TESTED" MARSHALL TEST MATRIX FOR THE MASONEILAN RELIEF VALVE CONDITIONS AT VAL VE OPEN I NG TRANSIENT CONDITIONS TEST TEST FLUID VALVE INLET PRESS.

IN ACCUMULATOR TEST DURATION VALVE INLET PRESS. WHEN MAXIMUM DISCHARG pl NO. TEMP. FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN TYPE (PSIA) (OF) PIPE PRESS.

(PSIA) (OF) TO CLOSE VALVE (PSIA)

(PSIA STEAM STEAM 2495 (SAT.) SAME AS VALVE INLET 66 2205 525 STEAM STEAM 2475 (SAT.) 32 2215 535 STEAM STEAM 2455 (SAT.) 32 2205 535 4 STEAM STEAM 2455 (SAT.) 33 2215 535 STEAM STEAM 2495 (SAT.) 33 2245 545 6 STEAM STEAM 2485 (SAT.) 64 2195 175 STEAM STEAM 2505 (SAT.) 31 2235 185 8 STEAM STEAM 2475 (SAT.) 35 2215 175

~

I STEAM STEAM 2455 (SAT.)

CJ1 41 2205 175

~ 10 STEAM STEAM 2465 (SAT.) 36 2215 185 11 STEAM STEAM 2485 (SAT.) (2) 2225 545 NOTES:

(1) Maximum Quasi steady discharge pipe pressure.

(2) Not recorded. .

(3) Test results are for evaluation tests only. Total of 18 supplementary valve actuation cycles were performed under similar conditions .

£PR! I "MARSHALL PORV TEST DATA (3)

TABLE 4.5.1-lb SUMl"ARY OF MASONEILAN RELIEF VALVE PERFORMANCE:

FLO\/ MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS "COMMENTS V~LVE TOTAL VALVE (1) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLU!D PRESS. . TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (;>SIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM)

STEAM 2.000 STEAM 2205 (SAT.) 525 199,000 1.700 STEAM 2445 (SAT.) 0.025 A pre-operational leakage test showed 0.0 GPM leakage 2 STEAM 1. 900 * . * *

  • 1.600 " .
  • STEAM 1. 750 . . " 1.600 * . .
  • STEAM 1.800 1. 600
  • STEAM 1.800 *
  • 1.600 STEAM 2485 (SAT.) 0.022

+=>

6 STEAM 2.100 STEAM 2195 (SAT.) 175 197,000 1. 700 *

  • I

(.J1 U1 STEAM 1.800 * * .. . 1.600 * * . .

8 STEAM 1. 650

  • 1. 600
  • 9 STEAM 1.600 . . *
  • 1.600 . . *
  • 10 STEAM 1. 700 * . 1.600 * * .

11 STEAM 1.900 *

  • 1.700 "STEAM 2485 (SAT.) 0.065 not applicable to this test NOTES:

(I) Opening time measured from t me of energizing solenoid until valve reaches full open position.

(2) Closing time measured from t me of de-energizing solenoid until valve reaches full closed position, (3) Test results are for evaluat on tests only. Total of 18 supplementary valve cycles were performed under similar conditions._

EPR!/WYLE Phase III PORV TEST DATA TnP1 t" /4 C i ") ...

"~ ~ '* J' \ - t.. 'C "AS TESTED" WYLE Pll/\SE Ill TEST MATRIX FOR THE

. MASONEILAN RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS Valve Inlet At .Valve Inlet In Accumulator Pressure Maximum Maximum Maximum Air at Discharge Bending Valve Accum. Test Closure Pipe_ *Moment Acceleration Press. Temp Press. Temp Press. Duration Signal Press.(2) Induced(4)Induced Te~t Nn. Test Type (psig)(l) Fluid (Of) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psia) (in- lb) (g's) 52-MN-lS Steam 54 Steam 683 2,765 Steam 679 2,765 7 2,415 358 N/A 13.4 53-MN-2S Steam 54 Steam 683 2,758 Steam 678 2, 758 . 8 2,370 346 . 35,600 3.9 (Pre load) 54-MN-4W Water 54 Water 444 2,530 Water 448 2,530 12 2,150 396 N/A 9.1

.+::>

I (JI (j) 55-MN-3W Water 54 Water 445 678 Water 450 678 11 652 153 N/A 11.2 56-MN-5W Water 56 Water 104 675 Water 116 675 11 593 38 N/A 4.5 57-MN-3W Water 58 Water 444 . 674 Water 445 674 11 640 156 N/A 2.0 58-MN-5W Water 59 Water 101 675 Water 101 675 20 570 14.7 N/A 5.0 59-MN-6W Water 59 Water 648 2,533 Water 650 2,533 9 2,355 435 N/A 4.6 60-MN-7S/W Transition 59 Steam 670 2,535 Water 647 2,535 9 2,350 425 N/A 4.0 61-MN-BW/W Water 59 Water 115 2,640 Water 656 2,640 17 (3) 450 N/A Seal 5.9 Simulation 62-MN-9W Water 59 Water 327 2,672 Water 325 2,672 6 2,340 112 N/A 10.3

I 1 I 1 TABLE 4.5.1-2a (Cont'd) MASONEILAN Notes:

(1) All values+ 1 psi.

(2) No back pressure orifice used during Masoneilan valve testing.

(3) Inlet pressure transducer failure.

(4) Value shown corresponds to the maximum moment applied while the valve was in the opening/closing process .

  • 4-57

EPRl/WYLE Phase III POR~ TEST DATA TABLE 4.5.l-Zo

SUMMARY

.OF MASONEILAN RELIEF VALVE PERFORMANCE Test 52- 53- 54- 55- 56- 57- 58- 59- 60-MN- 61-MN- 62-Number MN-lS MN-25 MN-4W MN-3W MN-SW MN-3W MN-SW MN-6W 75/W 8W/W MN-9W Pre-Test Leakage(!)

Media Steam Steam Water Water Water Water Water Water Water Water Water Pressure (psia) 2,745 2,780 2,515 830 707 765 685 2, 771 2,565 2,615 . 2,690 Temp (OF) 682 678 437 422 90 450 96 646 645 J04 316 Leak Rate (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0021 Transient Performance Total Valve Opening Time (sec) 1.64 1. 84 3. 73 6.39 3.08 2.54 2.39 1. 95 1. 81 1.97 3.08 Main Disc Opening Time (sec) 1.49 1.69 3.54 6.00 2. 74 2.20 2.05 1. 79 1.63 1.80 2.92 Valve Flow Rate (lb/Hr) 228,600 230,400 846,000 324,000 525,600 338,400 532,800 460,800 468,000 478,800 (3)

.j:::. Corresponding Valve I

U1 Inlet Press (psia) 2,480 2,510 2,220 652 593 642 5go co 2,395 2,400 (2) (3)

Corresponding Valve Inlet Temp (OF) 670 672 451 450 117 445 113 650 653 650 (3)

Corresponding Valve Outlet Press (psia) 340 335 362 148 2.0 152 2.0 420 410 430 (3)

Corresponding Valve Outlet Temp (OF) 415 417 424 353 109 355 103 445 435 450 (3)

Corresponding Test Time Relative to Open Command (sec) 4.2 3.8 4.9 5.5 5.7 4.7 8.6 4.2 3.r 8.0 (3)

Inlet Pressure at Beginning of Valve Closur*e (psi a) 2,420 2,360 2,125 648 580 635 550 2,350 2,350 (2) 2,350 Total Valve Closure Time (sec) 1.87 1.88 1. 79 1. 33 1. 39 1.4 1.46 1.89 1. 93 1.94 1.80 Main Disc Closing Time (sec) 1. 59 1.60 1.68 1.22 1.23 1.2 1.26 1.58 1 ..60 1.62 1. 73 Post-Test Leakage(!)

Media Steam Steam Water Water Water Water Water Water Water Water(4) Water(5)

Pressure (psia) 2,775 2,780 2,425 765 663 685 640 2,575 2,417 2,635 2,645 Temp (OF) 672 678 433 435 117 434 134 638 640 485 313

~ate (GPM) 0.0013 0.0013 0.0013 0.0013 0. 0.0013 0.0013 0.0013 0.0013 0.37 0.04

I f ) I TABLE 4.5.l-2b (Cont'd)

(1) Recorded leakages of .0013 GPM indicate measured leakages of less than or equal to .0013 GPM.

(2) Inlet pressure transducer not thermally isolatedo (3) Venturi delta pressure sensor improperly isolated.

(4) .. Leakage decreased to .066 GPM in 45 minutes.

(5) *Leakage increased to .079 GPM in 109 minutes

  • 4-59

I l ' t 4.6 COPES-VULCAN RELIEF VALVE (316 W/STELLITE PLUG.AND 17-4PH CAGE) "

4.6.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Copes-Vulcan relief valve model (316 w/Stellite Plug and 17-4PH Cage) at the Marshall Steam Station and during Phase III of the Wyle Test

. Program.

The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Copes-Vulcan relief valve tested at each of the test facilities.

Te*;t "As Tested" Test Valve Performance Fac i Ii ty Matrix Table Data Table Marshall 4.6.1-la 4.6.l-lb Wyle (Phase III) 4.6. l-2a 4.6.l-2b

  • It should lie noted that no preload test was performed on this valve design since the capability of the Copes-Vulcan valve to operate under an applied bending moment was demonstrakd during testing of the same valve body with a 17-4PH plug and cage (see section 4.:7).

4.6.2 Principal Observations Mars fl a 11 Ste am St at i on The valve fully opened on demand and fully closed on demand for each of eleven (11) evaluation test cycles.

Wyl e Phase II I A total of nine (9) tests were performed on this valve design.

For all tests the valve fully opened and fully closed on demand. Following test completion, the valve was disassembled and inspected by the Copes-Vulcan representative. No damage was observed that would affect future valve performance.

4-61

EPRI/ MARSHALL r'GRV TEST DATA (3)

TABLE 4.6.1-la "AS TESTED" ~ARSHALL TEST MATRJX FOR THE COPES-VULCAN (316 W/STELLITE PLUG 4~0 17-~PH CAGE) RELIEF VALVE CONDITIONS AT VALVE OPEUING TRANSIENT CONDITIONS VALVE INLET IN ACCUMULATOR TEST DUP.A TION VALVE lf,LET PRESS. WHEN MAW'UM DI SC.-l~.RG pl TEST TEST FLUID PRESS. TEMP. FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS.

NO. TYPE {PSIA) (OF) (PSIA) (Of) TO CLOSE VALVE {PSIA)

{PSIA)

STEAM STEAM 2475 {SAT.) SAME AS VALVE INLET 41 2155 635 STEAM STEAM 2460 {SAT.) 18 2155 635 STEAM STEAM 2450 (SAT.) 16 2155 635 4 STEAM STEAM 2455 (SAT.) 16 2165 635 STEAM STEAM 2465 {SAT.) 20 2165 635 STEAM STEAM 2460 (SAT.) 55 2135 215 STEAM STEAM 2435 {SAT.) 18 2155 215

.;:::. 8 STEAM STEAM 2450 {SAT.) 17. 2155 215 I

(J) 9 STEAM STEAM 2455 {SAT.) 23 2165 215 N

10 STEAM STEAM 2465 (SAT.) 17 2175 215 11 STEAM STEAM 2460 (SAT.) (2) 2160 635 NOTES:

(1) Maximum Quasi steady discharge pipe pressure.

{2) Not recorded.

(3) Test results are for evaluation tests only. Total of 16 supplementary valve actuation tests were perfonned under similar conditions .

SUMMARY

OF COPES-VULCAN EPRI I

( 316 MARSHALL TABLC: ~.6 W/STELLITE PLUG A,D PORV TEST DATA

.* -i~

17-4?H

( 3)

CAGE) RELIEF V~LVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VALVE (1) VALVE INLET OUTLET FLOW TOTAL VAL'IE [2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLUID PRESS. TEMP. PRESS. RATE CLOS iNG TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM)

A pre-operational leakage STEAM 1. 70 STEAM 2155 (SAT.) 635 236,000 1. 60 STEAM 2435 (SAT.) 0.066 test showed 0.0 GPM leakage STEAM 1. 70 * * *

  • 1. 50 *
  • STEAM . 1. 75 * * *
  • 1. SJ *
  • 4 STEAM 1.65 * * * * . 1. 55 * * *
  • STEAM 1. 85 * * * *
  • 1. 60 STEAM 2455 (SAT.) 0.058 6 STEAM 1.80 STEAM 2135 (SAT.) 205 232,000 1. 50 * * *
  • STEAM 1.40 * *
  • 1. 60 * *
  • 8 STEAM 1.40 * * *
  • 1. 55 * * *

+:>

I 9 STEAM 1.40 * * * *

  • 1. 60 * * *
  • O'I w 10 STEAM l. 70

" * * *

  • 1. 65 * * *
  • 11 STEAM 1.45 *
  • 1. 50 STEAM 2465 (SAT.) 0.054 not applicable to this test NOTES:

(1) Op~ning time measured from time of energizing solenoid until valve reaches full open position.

(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.

(3) Test results are for evaluation tests only. Total of 16 supplementary valve actuation tests were also performed under similar conditions.

EPRl/WYLE Phase Ill PORV TEST DATA TM! E 4.6.1-2~

"AS TESTED" WYLE PHASE Ill ltST MATRIX FOR THE COPES VULCAN(316 W/STELLITE PLUG AND 17-4 PB CAGE)RELIEF Vl\LVE INITIAL CONDITIONs(l) TRANSIENT CONDITIONS Valve Inlet At Valve Inlet In Accumulator Pressure Maximum Maximum Maximum at Discharge Bending Valve Test Closure Pipe Moment Acceleration Temp. Press. Temp Press. Duration Signal Press.(2) Induced Induced Test No. Test Type Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (in-lb) (g's) 71-CV-316-lS Steam Steam 682 2, 715 Steam 677 2, 715 6 2,333 460 N/A 7.0 72-CV-316-3W w~tPr i..,::!te!"' ~~6 ...? , .........

~~~

WJt2:"" ~~2 2,545 4 2,170 387 N/A 4.6 73-CV-316-4W Water Water 442 675 Water 442 675 10 626 193 N/A 7.7 74-CV-316-5W Water Water 105 675 Water 92. 675 10 562 174 N/A 8.6 I

CJ) 75-CV-316-6W Water Water 274 2,710 Water 261 2, 710 5 2,230 (3) N/A

.p. 7.6 76-CV-316-2W Water Water 647 2,535 Water 654 2,535 5 2,350. 531 N/A 3.9 77-CV-316-75/W Transition Steam 670 2,532 Water 657 2,532 6 2,343 555 N/A 12.6 78-CV-3i.6-8W/W Water Water 134 2, 725 Water 554 2, 725 16 2,350 640 N/A 7.8 Seal Simulation 79-CV-316-9N/W Transition GN 2 262 1,533 Water 299 1,533 6 1,300 150 N/A 5.1 (1) GNz PORV Actuation Ullage Pressure for all Tests was 86 (: 1) psig.

(2) No Back Pressure Orifice was used in the Copes-Vulcan 316 PORV Testing.

(3) PS-4 In operative during this test.

  • EPRI/WYLE Phase III PORV TEST DATA lABLE 4.6.l-2b

SUMMARY

OF COPES VULCA~(316 W/STELLITE PLUG AND 17-4 PH CAGE} RELIEF VALVE PERFORMANCE 71-CV 72-CV 73-CV 74-CV 75-CV 76-CV 77-CV *78-CV 79-CV 316-lS 316-3W 316-4W 316-5W 316-6W 316-2W 316-75/W 316-BW/W 316-9N/W Pre-Test Leakage(!)

Media Steam Water Water Water Water Water Water Water Water Pressure (psia) 2,755 2,530 923 805 2,695 2,573 2,605 2,730 1,600 Temp (OF) 685 470 441 100 270 643 624 116 299 Leakage (GPM) 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0040 0.0013 Transient Performance Total Valve Opening Time (sec) 0.60 0.55 1.01 0.98 0.64 0. 72 0.70 0.61 0.78 Main Disc Opening Time (sec) 0.39 0.48 0.66 0.60 0.55 0.56 0.60 0.53 0.56 Valve Flow Rate (lb/Hr) 255,600 1,008,000 388,800 619,200 1,173,600 540,000 540,000 612,000 864,000 Corresponding Valve

-+::>

I O">

Inlet Press (psia) 2,443 2,190 638 580 2,270 2,_390 2,365 2,480 1~330 t.n Corresponding Valve Inlet Temp (OF) 669 449 444 100 281 649 651 632 299 Corresponding Valve Outlet Press (psia) 410 387 188 0 (2) 531 540 610 82 Corresponding Valve Outlet Temp (OF) 427 350 362 90 250 400 448 482 278 Corresponding Test Time Relative to Open Command (sec) 2.7 1.6 2.8 .4.2 1. 8 1. 7 2.2 4.0 2.5 Inlet Pressure at Beginning of Valve Closing (psia) 2,310 2, 160 628 565 2,220 2,350 2,345 2,320 1,300 Total Valve Closing Time (sec) 1.43 1. 31 0.60 0.66 1.44 1.38 1. 37 1.44 0.88 Main Disc Closing Time (sec) 1.16 1.16 0.49 0.53 1.28 1.16 1.16 1.24 0. 76 Post-Test Leakage(l)

Media Steam Water Water Water Water Water Water Water Water Pressure (psia) 2,185 2,615 735 675 2,630 2,518 2,475 2,625 1,560 Temp (OF) 647 426 427 100 257 608 631 445 281 Lr:>ak Rate (psia) 0.035 0.0013 0.0013 0.0013 o.orm 0.015 0.00~2 O.Oln 0.0011

TABLE 4.6.l-2b (Cont'd)

Notes:

(i) Rec1Jrded leakages of 0.0013 indicate values of less than or equal to

0. 0013.

(2) ,PS-4 .in-operative during this test.

4-66

~. .

    • 4.7 COPES-VULCAN RELIEF VALVE (17-4PH PLUG AND CAGE) 4.7.1 "As Tested" Test Mat.rices and Valve Performance Data Tests were performed on the Copes-Vulcan relief valve model with the 17-4PH Plug and Cage at the Marshall Steam Station and during Phase III of the Wyle Test Program.
  • I The following is the list of tables that contain the "as tested" test matrices and I valve performance data for the Copes-Vulcan relief valve tested at each of the test facilities.

Test "As Tested" Test Valve Performance FacilJ!t Matrix Table Data Table Ma,rshall 4.7.l-la 4.7.l-lb Wy le ( Phase I I I ) 4.7.l-2a* .4. 7. l -2b

  • 4. 7. 2 Principal Observations Marshall Steam Station The valve fully opened on demand and closed on demand for each of the eleven (11) evaluation test cycles.

After these tests were completed, a new set'of 'the same design cage and plug parts were installed and the valve was cycled to investigate the cage to body gasket performance and to support other Marshall Steam Station test functions. The valve fully opened on demand and fully clos.ed on demand for the next 43 cycles. Six (6) of these cycles were performed under full pressure/flow conditions. The remaining cycles were either dry, unpres-surized actuations or openings/closings performed in conjunction with other valve testing. During the next 5 full pressure/flow tests performed, the valve did not fully close on demand. However, the valve always closed to within 13% of the full closed position. Disassembly showed galling of the cage and plug guiding surfaces.

4-67

  • Wyle Phase III A total of eight (8) te~ts were performed on this valve design.

tests, the valve fully opened and fully closed on demand.

During all Following completion of testing, the valve was disassembled and inspected by the Copes-Vu 1can representative. The cage to body gasket had partially "washed out" during testing . . No damage was observed that would affect future valve performance .

  • 4-69

EPRI/ MARSHALL PORV TEST DATA (3)

TABLE 4.7.1-la "AS TESTED" MARSHALL TEST MATRIX FOR THE COPES-VULCAN (17-4PH PLUG AND CAGE) RELIEF VALVE CONDITIONS AT VALVE' OPENING TRANSIENT CONDITIONS VALVE INLET IN ACCUMULATOR TEST VALVE INLET MAXIMUM ~l)

TEST TEST FLUID DURATION PRESS. WHEN DISCHARG PRESS. TEMP. FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS.

NO. TYPE (PSIA) (OF) (PSIA) (OF) TO CLOSE VALVE (PSIA)

PSIA)

STEAM STEAM 2455 (SAT.) SAME AS VALVE INLET 77 2145 595 2 STEAM STEAM 2455 (SAT.) 32 2175 605 3 STEAM STEAM 2430 (SAT.) 33 2185 615 4 STEAM STEAM 2475 (SAT.) 37 2210 615 STEAM STEAM 2475 (SAT.) 30 2195 615

.+::>

6 STEAM STEAA 2445 (SAT.) 71 2135 195 I

....... 7 STEAM STEAM 2435 (SAT.) 38 2165 0 195 8 STEAM STEAM 2445 (SAT.) 38 2195 195 9 STEAM STEAM 2505 (SAT.) 49 2195 195 10 STEAM STEAM 2445 (SAT.) 46 2175 195 ll STEAM STEAM 2455 (SAT.) (2) 2185 615 NOTES:

(1) Maximum Quasi steady d~scharge pipe pressure.

(2) Not recorded.

(3) Test results are for evaluation tests only. Total of 22 supplementary valve actuation cycles were performed under similar conditions *

  • EPRI/

MARSHALL ?ORV TEST DATA (J)

TABLE 4.7.1-lb

SUMMARY

OF COPES-VULCAN (17-4PH PLUG AND CAGE) RELIEF VALVE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VALVE (I) VALVE INLET OUTLET FLOW TEST TEST OPEN ING TIME TOTAL VALVE (2) VALVE INLET LEAKAGE FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA NO. TYPE (SEC) (PSIA) (OF) PRESS. TEMP. RATE (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM)

STEAM 1. 600 STEAM 2145 (SAT.) 595 221,000 1. 950 STEAM 2445 (SAT.) 0.788 A pre-operational leakage test showed 0.0 GPl-4 leakage 2 STEAM 1.300 * * *

  • 2.000 . * ..

3 STEAM 1.100 * . *

  • 2.100 *
  • 4 STEAM 1.300 * * * * . 2.000 * * * .

5 STEAM 1. 400 * * . .

  • 2.000 STEAM 2455 {SAT.) 0.304

-+:>

6 STEAM 1.400 STEAM 2135 (SAT.) 195 220,000 1.700 . * *

  • I

---.I STEAM 1. 300 * * . *

  • 1. 700 *
  • f-' *
  • 8 STEAM 1. 300 * .. * *
  • 1.655 .
  • 9 STEAM 1. 400 * * . .
  • 1.700 . .

10 STEAM 1.400 * .. * *

  • 1.600 * * *
  • 11 STEAM 1. 500 . " * *
  • 1. 700 STEP.M 2435 (SAT.) 0.280 not applicable to this test NOTES:

(!) Opening time measured from time of energizing solenoid until valve reaches full open position.

(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.

(3) Test results are for evaluation tests only. Total of 22 supplementary valve actuation tests were performed under similar conditions.

~~~---- ---- _ _ _ _ __

~-=c==c'----'='-'*=-=-=*-::_::-_c-*

EPRI/WYLE Phase Ill PORV TEST noTn TABLE 4.7.l-2a

~/IS TESTED" WYLE PHASE l I I TEST M/\TR IX FOR THE COPES VULCAN {l 7-4 Plf PLUG AND CAGE)RELIEF VALVE INITIAL CONDITIONS(!) TRANSIENT CONDITIONS Valve Inlet At Valve Inlet In Accumulator Pressure Maximum Maximum Maximum at Discharge Bending Valve Test Closure Pipe Moment Acceleration Temp Press. Temp Press. Duration Signal Press.(2) Induced(3)!nduced Test No. Test Type Fluid (OF) (psi a) Fluid (OF) (psi a) (seconds) (psi a) (psi a) (ln-lb) (g's) 63-CV-174-lS Steam Steam 682 2, 745 Steam 676 2, 745 6 2,365 450 N/A 7.2 64-CV-174-2S Steam Steam 682 2, 745 Steam 677 2,745 (Pre load) 6 2,365 470 43,000 10.4 I

65-CV-174-4W Water Water 455 2,535 Water 452 2,535 4 2, 180 425 N/A 5.9

-....i N

66-CV-174-3W Water Water 442 675 Water 441 675 10 630 193 N/A 11.6 67-CV-174-5W Water Water 106 675 Water 109 675 10 572 8.8 N/A 7.7 68-CV-l 74-6W Water Water 647 2,545 Water 653 2,545 5 2,340 537 . N/A 10.9 69-CV-174-7S/W Trans it ion Steam 671 2,545 Water 648 2,545 5 2,332 546 N/A 11.8 70-CV-174-BW/W Water Water 115 2, 715 Water 651 2, 715 16 2,293 618 N/A 12.2 Seal Simulation (1) GN 2 PORV Actuation Ullage pressure for all tests was 86 .:!: 1 psig.

(2) No back pressure orifice was used in the Copes-Vulcan (17-4) PORV testing.

(3) Value shown corresponds to the maximum moment applied while the valve was in the opening/closing process.

EPR!/WYLE II PORV TEST DATA TABLE 4.7.l-Zb SUW*IARY OF COPES-VULCAN (17-4 PH PLUG AND CAGE)RELIEF VALVE PERFORMANCE Test 63-CV 64-CV 65-CV 66-CV 67-CV 68-CV 69-CV 70-CV Number 174-lS 174-25 174-4W l 74-3W 174-5W l 74-6W 174-75/I~ 174-BW/W Pre-Te~t L'!akaa~ (1)

Media Steam Steam Water Water Water Water Water Water Pressure (psia) 2,802 2,745 2,861 1, 185 765 2,615 2,620 2,805 Temp (OF) 684 681 445 442 104 636 634 105 Leak Rate (GPM) 0.0013 0.046 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) 0.57 0.49 0.57 0.97 0.90 0.66 0.52 0.50 Main Disc Opening Time (sec) 0.45 0.40 0.44 0.58 0.52 0.54 0.41 0.41 Valve Flow Rate (lb/Hr) 255,600 265,700 997,200 399,600 630,000 547 ,200 576,000 601,200 Corresponding Valve Inlet Press (psia) 2,477 2,505 2,210 638 585 2, 385 . 2,352 2,430

+:> Corresponding Valve I

Inlet Valve (OF) 670 671 455 w 444 112 648 649 641 Corresponding Valve Outlet Pressb(psia) 375 390 415 191 1.0 525 540 570 Corresponding Valve Outlet Temp (OF) 418 415 400 371 102 400 420 479 Corresponding Test Time Relative to Open CormJand (sec) 2.6 2.1 2.0 3.8 4.1 1. 7 1. 9 5.7 Inlet Pressure at Beginning of Valve Closure (psia) 2,345 2,345 2, 180 632 575 2,340 2,330 2,290 Total Valve Closure Time (sec) 1. 34 1. 34 1.15 0.54 0.61 1.29 1.27 1. 35 Main Disc Closing Time (sec) 0.98 o.g5 0.82 0.35 0.40 0.97 0.97 1.35 Post-Test Leakage(!)

Media Steam Steam Water Water Water Water Water Water Pressure (psia) 2. 747 2, 760 2,685 750 665 2,470 2,240 2,420 Temp (OF) 680 682 422 423 110 593 605 443 Leak Rate (GPM) 0.04 0.073 0.0013 0.0013 0.0016 0.0164 0.011 0.023 Notes:

(1) Recorded leakages of .0013 GPM indicate measured values less than nr equal to .0013 GPM.

~ 4.8 MUESCO CONTROLS RELIEF VALVE 4.8.l "As Tested" Test Matrices and Valve Performance Data Tests were performed on the MUESCO Controls relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program.

The following is the list of tables that contain the "as tested" test matrices and valve performance data for the MUESCO Controls relief valve tested at each of the test facilities.

Test "As Tested" Test Valve Performance Facility Matrix Table Data Table Marshall 4.8. l-la 4.8.l-lb Wyle (Phase Ill) 4.8. l-2a 4.8.l-2b 4.8.2 Principal Observations Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the initial eleven (11) evaluation test cycles.

An additional eleven (11) evaluation tests were performed on the valve with a replacement stem, plug and gaskets. These parts had exhibited wear and the stem was observed to be bent slightly following the first set of tests and a second set of tests was reco~mended by MUESCO Controls for information purposes. The valve fully opened on demand and fully closed on demand for each of the evaluation test cycles. Similar wear patterns were found and the replacement stem was bent slightly.

During supplementary tests prior to the initial evaluation tests, valve opening times as long as* ten (10) seconds and closing times as long as twenty (20) seconds were observed. The air supply solenoid valve supplied by MUESCO was replaced prior to evaluation testing with the solenoid valve

  • 4-75

u~;ed at Marshall for all other air operated relief valve tests. The Marshall air supply line solenoid valve had a larger orifice area than the solenoid valve which was supplied by MUESCO with the test valve.

Wyle Phase III A total of seven (7) tests were performed on this valve design. During all tE*sts the valve fully opened and fully closed on demand. Following completion of testing, the valve was disassembled and inspected by the MUESCO Controls representative. Scratches were observed on the plug gLiding surface.* No damage was observed that wo.uld affect future valve performance.

4-77

EPRI/ MARSHALL PORV TEST DATA ( 3)

TABLE 4.B.1-la "AS TESTE~" MARSHALL TESi MATRIX FOR THE MUESCO RELIEF VALVE CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS VALVE INLET IN ACC.JMULATOR TEST DURATION VALVE INLET PRESS. \.:HEN MAXIMUM DISCHARG pl TEST TEST FLUID PRESS. TEMP. FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN PIPE PRESS.

NO. TYPE (PSIA) (OF) (PSIA) (DF) TO CLOSE VALVE (PSIA)

(PSIA)

STEAM STEAM 2435 (SAT.) SAME AS VALVE INLET 59 2385 255 2 STEAM STEAM 2425 (SAT.) 17 2375 255 3 STEAM STEAM 2415 (SAT.) 16 2375 255 4 STEAM STEAM 2415 (SAT.) 20 2375 255 STEAM STEAM 2415 (SAT.) 16 2375 255 6 STEAM STEAM 2455 (SAT.) 55 2427 80 STEAM STEAM 2455 (SAT.) 16 2415 85 8 i

.i:::. STEAM STEAM 2455 (SAT.) 17 2415 85 I

-....J 9 STEAM STEAM 2455 (SAT.)

I (X) 17 2no5 85 IO 11 STEAM STEAM STEAM STEAM 2445 2455 (SAT.)

(SAT.)

j 18 (2) 2400 2405 75 85 NOTES:

(1) Maximum Quasi steady discharge pipe pressure.

(2) Not recorded.

(3) Test-results are for evaluation tests only. Total of 14 supplementary valve actuation cycles were performed under similar conditions .

TABLE 4.8.l-lb

SUMMARY

OF MUESCO RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VALVE (l) VALVE INLET OUTLET FLOW TOTAL VALVE (2) V1~L VE INLET LEAKAGE TEST TEST OPEN it<G TiME FLviD PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM)

STEAM 2.800 STEAM A pre-operational leakage 2385 (SAT.) 255 100,000 1.750 STEAM 2485 (SAT.) 0.056 test showed 0.0 GPM leakage STEAM 2.900 * * *

  • l. 600
  • STEAM 2.300. * * *
  • l. 550 * *
  • STEAM 2.000 1.550 * .* *
  • STEAM 2.500 * .
  • I. 550 STEAM 2475 (SAT.) 0.046 6 STEAM 2.100 STE~!" 2427 (SAT.) 80 101,000 1.700 *
  • I

-....J STEAM 2.700 * *

  • 1.500 * *
  • I.Cl 8 STEAM 2.500 *
  • 1.600 *
  • 9 STEAM 2.800 * *
  • 1.500 * *
  • 10 STEAM 3.900 . * *
  • 1.600 * *
  • 11 STEAM 2.000 * * .
  • 1.700 STEAM 2455 (SAT.) 0.075 not applicable to this test NOTES:

(1) Opening time measured from ti~e of energizing solenoid until valve reaches full open position.

(2) Closing time measured from time of de-energizing.solenoid until valve reaches full closed position, (3) Test results are for evaluation tests only. Total of 14supplementary valve actuation tests were performed under similar conditions.

EPRI/WYLE Phase Ill PORV TEST DATA TABLE 4.8.l-2a "AS TESTED" WYLE Plll\SE Ill TEST MATRIX FOR THE MUESCO CONTROLS RELIEF VALVE INITIAL CONDITIONS(!) TRANSIENT CONDITIONS Valve Inlet At Valve Inlet Jn Accumulator Pressure Maximum Maximum Maximum at Discharge* Bending Valve Test Closure Pipe Moment Acceleration Temp Press. Temp Press. Duration Signal Press. ( 2) Induced ( 3) Induced Test No. Test Type Fluid (OF) (psi a) Fluid (OF) (psia) (seconds) (psi a) (psi a) (in-lb) (g's) 80-MU-lS Steam Steam 683 2, 755 Steam 678 2, 755 12 2,500 550 N/A 5.1 81-MU-2S Steam . Steam 670 2,535 Steam 665 2,535 6 2,418 50 24,000 5.0 (Pre load) 82-MU-3W Water Water 455 2,536 Water 453 2,536 9 2,410. 184 N/A 9.6

.j::>

I 83-MU-4W Water Water 449 674 Water 452 674 11 674 78 N/A I. 7 co 0

84-MU-5W Water Water 106 677 Water 99 677 11 649 84 N/A 20.2 85-MU-6W Water Water 645 2,534 Water 651 2,534 12 2,442 llO N/A. 4.4 86-MU-75/W Transition Steam 670 2,540 Water 652 2,540 12 2,440 106 N/A 4.3 (1) GN PORV Actuation Ullage pressure for all tests wa~ 49 ! 1 psig.

(2) No 2back pressure orifice was used in the Muesco PORV testing.

(3) Values shown corresponds to the maximum moment induced while valve is in the opening/closing process.

  • EPRI/WYLE Phase , PORV TEST DATA TABLE 4.8.I-2b

SUMMARY

OF MUESCO CONTROLS RELIEF VALVE PERFORMANCE Test

  • 80- 81- 82- 83- 84- 85- 86-Number Mu.::is M0-25 MU-3W MU-4W MU-SW MU-6W Mu-;1s;w Pre-Test Leakage (1)

Media Steam Steam Water Water Water Water Water Pressure (psia) 2,765 2,620 2,605 . 705 780 2,590 2,560 Temp (OF) 680 660 421 447 100 532 6411 Leak Rate (GPM) 0.0013 0.0026 0.033 0.0026 0.0013 0.032 0.0238 Transient Performance Total Valve Opening Time (sec) 2.09 2.03 2.20 2 .10 2.50 2.12 1.91 Main Disc Opening Time (sec) 1.88 1. 77 1.94 1.65 2.04 1.88 1.68 Valve Flow Rate (lb/Hr) 112,300 93,600 435,600 171,000 280,800 226,800 223,200

~ Corresponding Valve I

():>

...... Inlet Press (psia) 2,625 2,432 2,445 674 654 2,465 2,484 Corresponding Valve Inlet Temp (OF) 677 666 453 452 117 650 657 Corresponding Valve Outlet Press (psia) 540 50 182 75 3 108 98 Corresponding Valve Outlet Temp (OF) 304 295 370 308 107 340 330 Corresponding Test Time Relative to Open Command (sec) 5.1 3.4 3.8 4.5 5.9 6.5 3.6 Inlet Pressure at Beginning of Valve Closure (psia) 2,490 2,410 2,410 672 648 2,435 2,430 Total Valve Closure Time (sec) 2.32 2.09 1.95 1.46 1.47 2.31 2.21 Main Disc Closing Time (sec) 2.26 1.93 1.88 1.42 1.44 2.23 1.98 Post-Test Leakage (1)

Media Steam Steam Water Water Water Water Water Pressure (psia) 2,760 2,600 2,665' 785 685 2,480 2,43~*

Temp (OF) 661 669 435 436 100 610 6241 LP~k R~t.<> (r,PM) 0.00it5 0.0048 O.fJ38 0.0013 0.0011 OJM9 0.02113

... --~,_ ..........- ..

Notes:

TABLE 4.8.l-2b (Cont'd)

(1) Recorded leakages of .0013 GPM indicate a measured value of less than or equal to .0013 GPM.

I .

4-82

  • 4.9 FISHER CONTROLS RELIEF VALVE 4.9.1 "As Tested" Test Matrices and Valve Performance Data Tests performed on the Fisher Controls relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program.

The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Fisher Controls relief valve tested at each of the test facilities.

Test "As Tested" Test Valve Performance Facility Matrix Table Data Table Marshall 4.9.l-la 4.9.l-lb Wyle (Phase III) 4.9.l-2a 4.9.l-2b 4.9.2 Principal Observ~tions Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles. At the conclusion of these tests, the va l ve was d i s as s em bl e d and ga11 i ng was observed on the p l ug and c age mat i ng surfaces.

In addition to the evaluation tests, three other sets of cycles were performed on the valve. The first two sets of cycles were performed on a set of cage and plug parts which did not represent the correct Fisher Controls design for the PORV application. During the first set of cycles, the valve always closed on demand to within 4% of the full closed position on each cycle. After the cycles were completed, the valve was disassembled and galling was observed on the plug and cage mating surfaces. The galling was more severe than the evaluation test cycle galling pattern. A second set of tests were then performed using the same internals after they had been refurbished. For those tests, the valve fully opened on demand and fully closed on demand for each of 14 cycles.

4-83

The evaluation tests were then performed on a set of cage and plug parts with correct clearances. These are the tests discussed in the first paragraph cif this section and they represent Fisher Controls PORVs sup-*

plied to PWR plants with the correct internals.

A fourth set of cycles were performed on a set of trim with the correct design clearances. The *valve fully opened on demand and fully closed on demand for each cycle. A galling pattern similar to that observed in the evaluation tests was observed. Again, it was less severe than the pattern observed when the valve did not fully close on demand Wyle Phase III During all ten (10) tests performed, the valve fully opened arid fully closed on demand.

Fisher Controls Incorporated authorized the Control Specialists Company to perform maintenance on Fisher valves during the Wyle tests. Following completion of testing a Control Specitlists representative disassembled and inspected the Fisher PORV. Scratches were observed on the plug and cage guiding surfaces.

At EPRI request, each relief valve manufacturer 1 s representative made an engineering assessment of the potential effects of observed *damage on futur*e valve operation for all other PORVs tested. Prior to initiation of Wyle testing of the Fisher valve, Fisher Controls and Control Specialists took the position that no such assessment would be made for this valve and therrfore, none was made upon completion of testing.

4-85

EPRI/ MARSHALL PORV TEST DATA (3)

TABLE 4. 9. I- la "AS TESTED" MARSHALL TEST MATRIX FOR THE FISHER CONTROLS RELIEF VALVE CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS TEST VALVE INLET IN ACCUMULATOR TEST DURATION VALVE INLET PRESS. WHEN MAXIMUM DISCHARG pl TEST FLUllJ PRESS. TEMP. FLUID PRESS. TEMP. (SEC)

NO. TYPE SIGNAL GIVEN PIPE PRESS.

(PSIA) (OF) (PSIA) (OF) TO CLOSE VALVE (PSIA)

PSIA)

STEAM STEAM 2435 (SAT.) SAME AS VALVE INLET 88 2235 490 2 STEAM STEAi'! 2420 (SAT.) I' I 39 2235 485 3 STEAM STEAM 2395 (SAT.) I 34 2250 485 4 STEAM STEAM 2415 (SAT.) 48 2255 495 STEAM STEAM 2415 (SAT.) 37 2255 495 6 STEAM STEAM 2415 (SAT.) 72 2230 155 7 STEAM STEAM 2430 (SAT.) 20 2265 155

.+:::>

8 STEAM STEAM 2415 (SAT.)

I 24 2255 155 Co 9 STEAM STEAM 2410 (SAT.)

CJ) 23 2255 155 10 STEAM STEAM 2415 (SAT.) 22 2255 160 11 STEAM STEAM 2435 (SAT.) (2) 2275 495 NOTES:

(1) Maximum Quasi steady discharge pipe pressure.

(2) Not recorded.

(3) Test results are for evaluation tests only. 7otal of 21 supplementary valve actuation cycles were performed under similar conditions .

EPRI I .MARSHALL PORV TEST DATA (3)

TABLE 4.9. !-lb

SUMMARY

OF FISHER CONTROLS RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONDITIONS .LEAKAGE MEASUREMENTS COMMENTS VALVE TOTAL VALVE (1) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLUID PRESS. TEMP. PRESS. RATE CLOS ING TIME MEDIA PRESS. TEMP. RATE so. TYPE (SEC) (PSIA) (OF) (PS!A) (LBM/HR) (SEC) (PS!A) (OF) (GPM)

A pre-operational leakage STEAM 12. 300 (4) STEAM 2235 (SAT.) 485 180,000 I .200 STEAM 2455 (SAT.) 0.243 test showed a.a GPM leakage STEAM 13. 350 (4) * * * *

  • 1.200 * *
  • STEAM 16.200 (4) * * *
  • 1.000 . *
  • 4 STEAM. 17.400 (4) * *
  • 1.100 *
  • STEAM 13.600 (4). * *  !. 100 STEAM 2415 (SAT.) 0. 112

+::>

6 STEAM 2.650 STEAM 2230 (SAT.) 155 178,000 1.100 * " *

  • I

():) STEAM 2.800 * *

  • 1.000 * * *
  • 8 STEAM 2.200 * * * *
  • 0.950 * * *
  • 9 STEAM 2.100 * * * *
  • 0.950 * *
  • IO STEAM 2.300 * * *
  • 0.800 * .
  • Il STEAM 3.300 * * *
  • 0.900 STEAM 2415 (SAT.) 0. 108 not applicable to this test NOTES:

(I) Opening time measured from time of energizing solenoid unti'l valve reaches full open. position. .

(2) Closing time measured from time of de-energizing solenoid until valve reaches full .closed posltfon. .  ; ,

(3) Test results are for evaluation tests only. Total of 21 supplementary valve*actuat1on cycles were perfonned under similar cond1t1ons.

(4) The valve opened slowly because the Fisher Controls representative had increased the spring force to insure minimum seat leakage.

EPRI/WYLE Phase III PORV TEST DATA TABLE 4.9.l-2a "AS TESTED" WYLE PHASE II I TEST Ml\ TRIX FOR THE FISHER CONTROLS RELIEF VALVE INITIAL CONDITIONS(l}

TRANSIENT CONDITIONS Valve At _/'id lve Inlet Inlet In Accumulator Pressure Maximum Maximum Maximum at Discharge Bending Valve Temp Test Closure Pipe Moment Acceleration Test No. Press. Temp Press. Duration Signal Test Type Fluid (OF) (psi a) Fluid (OF) Press.(2) Induced(3}Induced (psi a) (seconds) (psi a} (psi a) (in-lb) (g's) 87-FS-lS Steam Steam 683 2, 760 Steam 678 2,760 6 2,395 370 N/A 2.1 88-FS-2S Steam Steam 683 2, 760 Steam 678 2,760 6 2,400 330 (Pre load) 38,300 2.0 89-FS-3W Water

  • Water 452

-+::>

2,664 Water 454 2,664 5 2,430 I

350 N/A 2.1 o:i co 90-FS-411 Water Water 447 685 Water 456 685 10 666 138 N/A 1. 7 91-FS-5W Water Water 101 684 Water 94 684 10 612 N/A 1.8 92-FS-611 Water Water 264 2,668 Water 257 2,668 4 2,390 410 N/A 3.2 93-FS-7W Water Water 648 2,536 Water 650 2,536 6 2,395 400 N/A 2.5 94-FS-8S/W Trans it ion Steam 669 2,530 Water 653 2,530 6 2,380 372 N/A 7.4 95-FS,-9W/W Water Water 203 2,704 Water 655 2. 704 15 Seal 2,420 450 N/A 19.5 Simulation 96-FS-lOW/W Water Water 123 2,700 Water 657 2, 700 15 Seal 2,400 450 N/A 11.2 Simulation

( 1) G~ PORV Actuation Ullage pressure for all tests wa5 69 2 (!) 1

( 2) No back pressure orifice was used in the Muesco PORV t~sting. psig.

( 3) Value shown corresponds L, the 111aximum moment induced while valve 1s in the opening/closing process .

EPRI/WYLE Ph as ORV TEST DATA TABLE 4.9.l-2b

SUMMARY

  • OF FISHER VALVE PERFORMANCE Test 87- 88- 89- 90- 91- 92- 93- 94-Number 95- 96-FS-lS FS-2S FS-3W FS-4W FS-5W FS-6W FS-7W FS-85/W FS-9\.//W FS-lOW/W Pre-Jest Leakage(!)

Media Steam Steam Water Water Water Water Water Water Water Water Pressure (psia) 2,780 2, 785 2,680 705 710 2, 715 2;535 2,575 2, 765 2, 715 Temp (OF) 682 682 455 431 96 262 649 643 191 Leak Rate (GPM) 112 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) 0.34 0.38 0.64 1.05 2.32 0. 70 0.54 0.41 0.65 0.65 Main Disc Opening Time (sec) 0.24 0.27 0.53 0.82 2.10 0.58 0.42 0.29 0.54 0.54 Valve Flow Rate (lb/fir) 216,000 216,000 756,000 284,400 460,800 853,200 410,400 385,200 432,000 432,000 Corresponding Valve

.j:::>

I Inlet Press (psia) 2,555 2,559 2,460 670 OJ 625 2,430 2,426 2,400 2,493 2,490

<.o Corresponding Valve Inlet Temp (OF) 674 674 453 453 102 268 649 656 648 650 Corresponding Valve Outlet Press (psia) 295 295 308 138 340 380 372 410 410 Corresponding Valve Outlet Temp (OF) 390 385 275 350 91 230 435 434 445 445 Corresponding Test Time Relative to Open Command (sec) 2.5 2.9 . 1.2 4.3 4.0 1. 7 3.1 4.2 8.4 8.4 Inlet Pressure at Beginning of Valve Closure (psia) 2,380 2,390 2,420 665 615 2,390 2,395 2,390 2,420 2,410 Total Valve Closure Time (sec) 0.33 0.33 0.38 0.25 0.27 0.36 0.35 0.35 0.36 0.36 Main Disc Closing Time (sec) 0.17 0.18 0.22 0.13 0.15 0.22 0.17 0.16 0.18 0.18 Post-Test Leakage( I).

Media Steam Steam Water Water Water Water Water Water Water Pressure (psia) Water 2,780 2, 765 2, 715 745 670 2,700 Temp (OF) 2,605 2,460 2,620 2,700 683 677 443 435 101 250 637 leak Rate (GPM} 670 468 457 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0. 001.3 0.0013 0.0013 0.0013

(1)

TABLE 4.9.l-2b (Cont'd)

Recorded leakages of 0.0013 indicates values of less than or equal 0.0013.

to I '

1:

4,...90

  • 4.10 GARRETT RELIEF VALVE 4.10.1 "As Tested" Test Matrices and Valve Performance Data Tests were performed on the Garrett relief valve model at the Marshall Steam Station and during Phase III of the Wyle Test Program.

The following is the list of tables that contain the "as tested" test matrices and valve performance data for the Garrett relief valve tested at each of the test facilities.

Test "As Tested" Test Valve Performance Facility Matrix Table Data Table Marshall 4.10.1-la 4.10.1-lb Wyle (Phase III) 4.10.l-2a 4.10.l-2b t .10.2 Principal Observations

  • Marshall Steam Station The valve fully opened on demand and fully closed on demand for each of the eleven (11) evaluation test cycles.

Additional cycles were performed on the valve. Following 46 of these cycles, body to bonnet gasket leakage developed. In all cycles, the valve fully closed on demand. Disassembly showed wash-out of the cage to body gaskd. As a result of the test observations, Garrett incorporated design modifications into the test valve for Wyle Phase III tests and into valves being supplied to PWR plants.

Wyle Phase III The valve fully opened and fully closed on demand during all ten (10) tests performed. Upon completion of testing, the valve was disassembled and inspected by the Garrett Corporation representative. No damage was

  • observed which would affect future operation.

4-91

EPRI/ MARSHALL PORV TEST DATA (3)

TABLE 4.10.1-la "AS TESTED" MARSHALL TEST MATRIX FOR THE GARRETT RELIEF VALVE CONDITIONS AT VALVE OPENING TRANSIENT CONDITIONS TEST TEST VALVE INLET IN ACCUMULATOR TEST OUllATIO~

VALVE INLET PRESS. WHEN MAXIMUM OISCHARG pl FLUID PRESS. TEMP. FLUID PRESS. TEMP. (SEC) SIGNAL GIVEN NO. TYPE (PSIA) (OF) PIPE PRESS.

(PSIA) (OF) TO CLOSE VALVE (PSIA)

PS!A)

STFAM STEAM 2435 (SAT.) SAME AS VALVE INLET 79 1995 815 2 STEAM STEAM 2435 (SAT.) 23 2035 820 STEAM STEAM 2415 (SAT.) 25 2015 815 4 STEAM STEAM 2415 (SAT.) 28 2030 815 STEAM STEAM 2425 (SAT.)

+:> 30 2050 825 I

l.O 6 STEAM STEAM 2450 (SAT.)

N 44 2015 335 STEAi~ STEAM 2465 (SAT.) 15 2075 355 8 STEAM STEAM ~455 (SAT.) 12 2055 340 STEAM STEAM 2445 (SAT.) 16 2055 345 10 STEAM STEAM 2435 (SAT.) 17 2.055 345 11 STEAM STEAM 2455 (SAT.) (2) 2075 815 NOTES:

(1) Maximum Quasi steady discharge pipe pressure.

(2) Not recorded.

(3) Test results are for evaluation tests only. Total of 68 supplementary valve actuation cycles were performed under similar.conditions.

TABLE 4.10.1-lb

SUMMARY

OF GARRETT RELIEF VALVE PERFORMANCE FLOW MEASUREMENT CONOITIONS LEAKAGE MEASUREMENTS COMMENTS

'!.~~VE TOTAL VALVE (1) VALVE INLET OUTLET FLOW TOTAL VALVE (2) VALVE INLET LEAKAGE TEST TEST OPENING TIME FLUID PRESS. TEMP. PRESS. RATE CLOSING TIME MEDIA PRESS. TEMP. RATE NO. TYPE (SEC) (PSIA) (OF) (PSIA) (LBM/HR) (SEC) (PSIA) (OF) (GPM)

A pre-operational leakage STEAM 0.195 STEAM 19g5 2 STEAM 0.205 * *

(SAT.)

800 293,000 2.350 1.990 STEAM 2445 (SAT.)

0.006 test showed 0.0 GPM leakage 3 STEAM 0. 195 . * * *

  • l. 760 . * *
  • 4 STEAM 0.215 * *
  • *
  • l.895 *
  • 5 STEAM 0.205 . * *
  • 2.015 STEAM 2615 (SAT.) 0.008
6. STEAM 0.205 STEAM
  • 2015 (SAT.) 335 292,000 1.750 * *
  • 7 STEAM 0.215 *
  • l.600 . * * .

8 STEAM 0.210 * . * *

  • 1.630 * * *
  • 9 STEAM 0.220 * * *
  • 1. 730 * * * *

~

I l.O 10 STEAM 0.215 * * * * . 1. 700 * * *

  • w 11 STEAM (3) * * * * * (3) STEAM 2495 (SAT.) 0.010 (5)
  • not applicable to this test NOTES:

( l) Opening time measured from time of energizing solenoid until valve reaches full open position.

(2) Closing time measured from time of de-energizing solenoid until valve reaches full closed position.

( 3) Not recorded (4) The results are for evaluation tests only. Total of 68 supplementary valve cycles "".er.~ perfo';l'j~~ounnsder similar conditions.

(5) The leakage test was conducted after 66 supplementary tests were performed under s m ar con

  • 1 1

EPRI/WYLE Phase III PORV TEST DATA TABLE 4.10.l-2a "AS TESTED" WYLE PHASE I!! TEST MATRIX FOR THE GARRETT RELIEF VALVE INITIAL CONDITIONS TRANSIENT CONDITIONS Valve At Valve Inlet Inlet In Accumulator Pressure Maximum Maximum. Maximum at Discharge Bending Valve Temp Test Closure Pipe Moment Acceleration Test No. Press. Temp Press. Duration Signal Test Type Flu.id (OF) (psia) Fluid (OF) Press.(1) lnduced(3)Induced (psi a) (seconds) (psi a) (psia)(2) *(in-lb) (g's) 97-GA-lS. Steam Steam* 683 2, 760 Steam 682 2,760 4 2,346 580 N/A 12.2 98-GA-2S Stearn Steam 683 2, 760 Steam 679 2, 760 4 2,275 623 33,200 (Pre load) 8.7 99-GA-3W Water Water 438 2, 760

+::> Water 461 2,760 4 2,030 485 N/A I 7.2 l.O

+::> 100-GA-4W Water Water 447 683 Water 460 683 12 610 255 N/A 12.3 101-GA-5W .Water Water 104 686 Water 94 686 11 495 25 N/A 12.2 102-GA-6W Water Water 249 2,640 Water 258 2,640 3 1,880 92 N/A 12.6 103-GA-7W Water Water 648 2,758 Water 653 2,758 3 2,4~0 780 N/A 6.8 104-GA-8S/W Transition Steam 682 2, 760 Water 653 2, 760 6 2,420 800 N/A 5.2 105-GA-9W/W Water Water 293 2, 755 Water 651 2,755 16 2,225 875 N/A Seal 5.8 Simulation 106-GA-lOW/W Water Water 130 2, 760 Water 650 2, 760 16 2,210 860. N/A Seal 8.7 Simulation Notes:

(1) Values shown were measured 50" downstream of valve exit (same location as for all other PORV's tested).

pressure sensor (PS-6) was mounted irnnediately downstream of the valve, For this valve an addition~l discharge pipe (see section 5.0 for plot of observed pressure).

(2) No back pressur~ orifice was used in the Garrett PORV testing .

. (3) Value shown corresponds to maximum moment applied whfle. valve was in the opening/closing process.

----*--~

  • EPRI/WYLE Phase III PORV TEST DATA TABLE 4.10.l-2b SUMMllRY OF-GARRETT RELIEF VALVE PERFORMANCE
  • rest 97- 98- 99- 100- 101- 102- 103- 104- 105- 106-Number GA-15 GA-2S GA-3W GA-4W GA-5W !JA-6W GA-7W GA-8S/W GA-9W/W GA-lOW/W Pre-Test Leakage (1)

Media Steam Steam

  • Water Water Water Water Water Water Water Water Pressure (psi a)* 2,820 2,665 2,770 775 690 2,610 2,820 2,795 2,815 2,785 Temp (OF) 676 675 414 395 98 222 611 599 282 122 Leak Rate (GPM) 0.0013 0.0013 0.0021 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 0.0013 Transient Performance Total Valve Opening Time (sec) 1.24 0.59 0.40 0.59 0.68 0.38 0.37 0.54 0.38 0.43 Main Disc Opening Time (sec) 0.13 0.13 0.26 0~51 0.59 0.25 0.22 0.29 0.26 0.25 Valve Flow Rate (lb/Hr) 378,000 372,600 (2) 489,600 900,000 1,681,200 813,600 792,000 784,800 792,000

~

I Corresp.onding Valve

'° U'l Inlet Press (psia) 2,415 2,386 (2) 618 510 1,900 2,486 2,460 2,390 . 2,360*

Corresponding Valve Inlet Temp (OF) 674 669 (2) 461 106 266 648 650 646 642 Corresponding Valve Outlet Press (psia) 573 562 (2) 255 14.7 92 770 765 750 745 Corresponding Valve Outlet Temp (OF) 350 390 (2) 400 96 228 330 497 508 505 Corresponding Test Time Relative to Open Command (sec) 2.1 1.8 (2) 4.5 4.0 1.6 L2 2.9 5.4 6.6 Inlet Pressure at Beginning of Valve Closure (psia) 2,310 2,240 2,030 610 490 1,860 2,1180 2,410 2,220 2,210 Total Valve Closure Time (sec) 0.60 0.58 0.78 1.42 1.04. 0.75 0.85 1.18 0.92 0.90 Main Disc Closing Time (sec) 0.25 0.24 0.47 1.09 0.81 0.48 0.56 0.52 0.58 o.. 61 Post-Test Leakage (l)

Media Steam Steam Water . Water Water Water Water Water Water Water Press (psi a) 2,825 2,755 2,850 805 685 2,560 2,695 2,725 2, 775 2,780 Temp (OF) 681 681 405 399 97 221 583 592 470 415 i_,,~~ R~tP (GPM) 0.0011 o.orn 1 0.l'JQ] 3 0.1')013 O.OOlJ 0:0011 0.0011 o.nn1J 0.0011 0.0013

Nates:

TABLE 4.l0.1.-2b (Cont'd).

(1) Recorded leakages of .0013 .GP M indicates measured values less than or equal to .0013 GP M..

(2) Venturi delta pressure sensor over-ranged 4-96 *

  • 1.

Section 5 REFERENCES "Valve Selection/Justification Report," Interim Report, December 1981, EPRI Valve Test Program staff, et al.

2. "Test Condition Justification Report," Interim Report, April 1982, EPRI Valve Test Program Staff, et al.
3. Valve Inlet Fluid Conditions for Pressurizer Safety and Relief Valves in B&W 177FA and 205FA Plants, March 1982.
4. Valve Inlet Fluid Condit ions for Pressurizer Safety and Relief Valves in Combustion Engineering Plants, March 1982.
5. Valve Inlet Fluid Conditions for pressurizer Safety and Relief Valves in Westinghouse Plants, January 1982 .
  • 5-1
  • APPENDIX A DEFINITION OF KEY TERMS AND PARAMETERS F6R SAFETY VALVES .

The definitions are provided for each of the Safety Valve tables presented in section 3.0.

The following definitions apply to Tables 3.1.1.a, 3.2. l .a, 3.3.1.a, 3.4.1.a, 3.5.1.a, 3.6.1.a and 3.7.1.a:

KEY TERMS AND PARAMETERS DEFINITION Valve Description The valve description is a list of design and name-plate information for the test valve.

Inlet Piping Each element of the piping between the accumulator Configuration tank (tank 1) and the valve inlet is listed along with its length and inside diameter. The elements are listed sequentially from the tank (nozzle) to the valve inlet (inlet flange). Letter designations have been assigned to each configuration and that letter is referenced in this table .

  • A-1

The following definitions apply to Tables 3.1.1.b, 3.2.l.b, 3.3.1.b, 3.4.1.b, 3.5.1.b, 3.6.1.b and 3.7.1.b:

KEY TERMS AND PARAMETERS Test No.

DEFINITION There is a unique identification number for each test.

These numbers were assigned in ascending order to the tests when they were conducted; however, the numbers are not continuous. For example, tests on one of the valves were numbered 403, 406, 408 .... Every valve test performed is li~ted in the tables.

For some of the tests, the valves were cycled opened and closed more than once. The test procedure typ-ically called for continued system pressurization to obtain three-to-five minutes of test time for each test. If the .valve closed within seconds after opening, system repressurization .was permitted to continue and the valve was cycled open and closed

  • through multiple cycles until the planned test dura-tion was completed. In the case of transition tests, system repressurization was again permitted and the valve cycled as often as required in order to obtain the stea~-to-water transition. For the tests which resulted in multiple cyqles of the test valve, all of the data for the first cycle has been listed in the tables. For the subsequent cycles, the data has been provided for the key valve test parameters related to the fluid type, valve opening, peak and closing pressures, back pressures and valve stability. The first cycle of the multiple cycles has been designated as cycle 11 a 11 and the remaining cycles have been designated as b, c, d . . . .

11 11 T1 *st Type The following types of tests were performed:

Steam - the fluid at the valve inlet and in the accumulator tank (tank 1) at test initiation and throughout the test was steam.

L.S. - these tests were loop seal tests. Just prior to test initiation, the fluid at the valve inlet was subcooled water and the fluid in the accumulator was steam. Once the loop seal water was discharged, the test fluiu was steam.

Trans. - these tests were transition tests. Prior to test initiation, the fluid at the valve inlet was steam and the fluid in the upper and lower portions of the accumulator tank were steam and saturated water, respectively. The valve opened on steam and closed on saturated water during the transition test .

A-2 *

-, 1*

.<<l' 1',

  • L.S. Trans. ~ these tests were loop seal transition tests. The test was the same as a transition test except that the fluid immediately upstream of the safety valve was subcooled water.

Water - the fluid at the valve inlet and in the accumulator tank at test initiation and throughout the test was approximately saturated water, 550°F water or 400°F water. The water tests progressed from satura-ted water to the 55QOF water test and finally the 400°F water test. Target Rock test included cold loop seals.

~alve Ring Settings Valve ring positions are listed for the safety valve adjusting rings. Descriptions of the reference posi-tion for each of the safety valve manufacturer's valves tested are as follows:

Crosby Valves have two adjusting rings, an upper or guide ring and a lower or nozzle ring. Positions in the table are given in notches relative to the level position.

For the upper ring, the level position (O notches) is the position when the bottom of the upJ!er ring is flush with the bottom of the disc ringll). For the lower ring, the level position (O notches) is the position when the top surface of the lower ring is in contact with the bottom of the disc ring. Positive ring positions are positions where the rings have been moved up from the level position and negative ring positions are positions where the rings have been moved down from the level position.

Field positions for the upper ring are provided by Crosby in notches relative to the "highest locked position" which is the upper limit of the ring's travel. The lower ring field positions are the same as the level positions. Both of the ring field positions are marked by Crosby on the valve.

Dresser Valves have three adjusting rings, termed upper, middle and lower rings. Positions for the upper ring are given in notches relative to the position where the top of the upper ring is flush with the top of the holes in the guide. Positions for the bottom surface of the middle ring and the top surface of the lower ring are relative to the seat plane. The term "level position" is not applicable to the Dresser safety valves.

TiTTue disc ring is not an adjusting ring A-3

Field settings may be provided by Dresser relative to the bottom of the disc holder instead of the seat plane. The Dresser Instruction Manual re-lates the disc holder* plane to the seat plane in terms of notches for the lower and middle rings.

The Target Rock Valve does not have adjustment rings so the ring setting column is not applicable.

Inlet* Piping Configuration Refer to the definitions applicable to Tables 3.1.l.a through 3.7.l.a.

Condition at Valve Opening The fluid type, pressure, temperature and pres-surization rate are listed for tank 1 and the fluid and temperature are tabulated for the valve inlet.

All conditions are listed at the point in time when the valve initially begins to open. Specific parameters are as follows:

Fluid - the fluid types are described under the definition for test type. For transition tests, two fluids are listed fo1* tank 1. The first fluid listed is the fluid in the top of the tank and the second fluid listed is the fluid in the lower portion of the tank.

Pressure - the pressure is the valve main disc initial opening pressure.

Temperature - the temp9ratures for steam con-ditions correspond to the state reached by pres-surizing steam which was initially saturated at a nominal pressure of 2300 psia. Note (1) is used in the tables instead of a ni.;merical temperature value for these cases.

Pressurization Rate - The pressurization rate is determined from the accumulator (tank 1) pressure at the time the test valve began to open.

Transient Conditions. The peak inlet pressure, back pressure, and liquid flow which occur while the valve is open are tabulated. In addition, the induced bending moments are tabulated. Specific parameter definitions are as follows:

A-4

  • Peak Tank 1 Pressure - This is the maximum pressure observecr---;-r; tank 1 during a test.

P2ak Back Prssure - This is the maximum sustained outlet pressure just downstream of the test valve which was observed during a test.

During transition and water tests, the same back pressure orifice was used in the discharge piping as was used in the high back pressure steam tests with the exception of the Dresser 31709NA safety valve. For this valve, the intermediate back pressure orifice was used.

Induced Bending Moment Opening/Closing - The mo-ments tabulated are the maximum bending moments imrosed on the test valve discharqe flange by the discharge piping. The first value listed is the larger of the bending moments during valve open-ing or valve closing when both values were avail-able. If only one moment was available, that value was listed.

Maximum Steady Liquid Flow - The maximum water flow rate for which a stabl~ flow measurement was obtained .

A-5

- he following definitions apply to Tables 3.1.1.c, 3.2.1.c, 3.3.1.c, 3.4.1.c,

. 5. 1 . c, 3. 6. 1 . c and 3. 7. 1 . c :

KEY TERMS AND PARAMETERS DEFINITION Test No. Refer to the definitions applicable to Tables

. 3. 1. l. b through 3. 7. l. b.

Test . Type Refer to the definitions applicable to Tables 3.1.l.b through 3.7.l.b.

Pre-Test Valve Leakage Pre-test valve leakage was measured before each test. The purpose of the valve leakage measure-ments were to insure that leakage during the multiple tests of a test series was within a range that the valve manufacturer assessed would provide representative valve performance. The leakage procedure and leakage range were only related to the safety valve tests and were not based on PWR plant leakage procedures. The leakage test and leakage range were included as part of the test procedure in order to determine whether or not a test should be performed. If leakage occurred which exceeded the manufacturer's recommended test range, the valve was disassembled and the seats were normally lapped and in some cases replaced.

The leakage data is included to supplement the valve performance information.

Specific test parameter definitions are as fol-lows:

Media - the media is the fluid at the valve inlet used for the leakage test.

Nominal Valve Inlet Pressure and Temperature-these are the approximate conditions at the valve inlet when the leakage test was performed.

Leakage Rate - Leakage is expressed as gallons per minute of condensed leakage. One gpm condensed leakage is equivalent to a leakage rate of about 500 lbs/hr of steam.

Valve Opening The data includes safety valve opening pressure,

~nd Closing opening ti111e, closing pressure, valve blowdown and an assessm(?nt of valve stability. These parameters describe the valve performance from valve opening through valve closure and are defined as frillows:

A-6

  • Initial Valve Opening Pressure - this is the test valve inlet static pressure at which there is a 111t'il'.LJt't1blv lift ol t11e disc away fro111 the closed position. The pressure is measured in the ac-cumulator (tank 1). The initial valve opening pressure corresponds to the main disc lift for the Crosby and Dresser test valves and corresponds to the pilot disc lift for the Target Rock test valve.

Opening Pop Pressure - the pop pressure is the value of increasing inlet static pressure at which the main disc for all three manufacturer's designs moves in the opening direction at a faster rate as compared with corresponding movement at higher or lower pressures.

Opening Simmer time - Simmer time is the time elapsed between initial valve opening pressure and the valve pop pressure (see Figure A-1).

  • Opening Pop Time - This was the effective time for the valve stem to move from the closed position to the rated lift positiori. In cases where the pop starts from an intermediate lift and/or the valve does not reach rated lift, the slope of the stem position is extrapolated to give a pop time for the entire lift range. The pop time does not include the stem acceleration time which normally occurs at the beginning of the pop. This is included with the total simmer time (see Figure A-1). Pop time is not applicable to subcooled water tests.

Tank 1 Pressure at Valve Closure - Closing pressure is the pressure at which the valve main disc re-establishes contact with the seat (reseats). The pressure is measured in the accumulator (tank 1).

% Slowdown - Slowdown as used herein is the dif-ference between the design set pressure and the actual reseating pressure expressed as a per-centage of the design set pressure.

NOTE: ANSI S95.l defines blowdown relative to the actual popping pressure.

Valve Stability - the valve stem behavior while the valve is open is defined as follows:

Chatter - chatter is rapid reciprocating motion of the movable parts in which the disc contacts the seat .

  • A-7

Flutter - flutter is rapid reciprocating motion of the movable parts in which the disc does not contact the seat.

Stable - the. va*lve opens, remains open and closes without flutter and/or chatter.

In some tests, combinations of these behaviors occurred (e.g. loop seal discharge) and the com-binations are clarified by a footnote on a case-by-case basis.

Post-Test Leakage The definition for the pre-test valve leakage applies except that the post-test valve leakage measurement was conducted after the test was com-pleted. In tests with multiple cycles, the post-test leakage data are listed for the first cycles but were measured after the last cycle.

  • 1, i:

I I 1 A-8

Representation of Typical Safety Valve Stem Position as a Function of Time Rated Li ft z

0 I-

):::> VJ I 0

\.0 a.

E:

Extrapolate to Rated Lift, w

I-If Necessary VJ Zero }Extrapolate to Zero Lift Lift Simmer Time Time

-- ------------- - - - - - - - - - - - - - - - - - - - - * - - -~-- -------~-

The following definitions apply to Tables 3.1,l.d, 3.2.l.d, 3.3.l.d, 3.4.l.d, 3.5. l.d, 3.6. l .d and 3.7.l .d:

KEY TERMS AND PARAMETERS DEFINITION Test No. Refer to the definitions applicable to Tables

3. l. l. b through 3. 7. l. b.

Jest Type Refer to definitions applicable to Tables 3. 1.1.b through 3.7. l .b.

Conditions at 3% The test valve lift position ~nd flow rate were l\ccumu lat ion evaluated at a pressure which was 3% above the valve design set pressure (3% accumulation) during the ;depressurization portion of the steam test transients. The accumulation conditions are pro-vided based on the pressure measured in tank 1 and on the pressure measured in the inlet pipe just upstream of .the safety valve. In each case, the valve lift position and steam flow rate are listed based on the following terms:

% Rated Lift - this value is the lift position of the valve at 3% accumulation and is expressed as a percentage of the valve rated lift; Rated lift is the design lift at which a safety valve attains its rated steam relieving capacity.

% Rated Steam Flow - this value is the steam flow rate through the valve at 3% accumulation expressed as a percentage of the valve rated capacity.

Accumulation data are applicable to high pressur-ization rate steam tests only. Other tests were not designed to produce accumulation above the setpressure.

The inlet pipe pressure is corrected for velocity head to approximate the stagnation pressure at the valve inlet and to eliminate the difference due to static head losses in the inlet piping.

In some steam tests, the 3% accumulation p1*essure was not achieved and that has been noted in the table.

CC1nditions at 6% The definitions for Conditions at 3% Accumulation Accumulation apply except that the valve lift and flow rate data were measured when the inlet pressure was 6~ above the valve design set pressure.

A-10

Liquid Flow The maximum steady liquid flow as well as the Measurement associated pressure and temperature and valve lift positions are listed for the transition and water tests. Definitions for these terms are as follows:

Tank Conditions - the pressure and temperature associated with the measured liquid flow rate are based on tank 1 conditions.

Maximum Steady Liquid Flow - refer to the de-finitions applicable to" Tables 3.1. l .b through 3.7.l.b.

% Rated Lift - the value listed is the lift posi-tion expressed as a percentage of the valve rated lift when the flow rate was measured.Rated lift is the design lift at which a safety valve attains its rated steam relieving capacity .

  • A-11

The following terms were not used in the tables of section 3.0 but were used in the text of the report and are defined for information purposes:

KEY TERM DEFINITION The pressure in the accumulator used to pressurize the air operators of the relief valves tested in.

Wyle Phase III tests.

GN 2 is gaseous nitrogen.

A-12

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