ML18047A461

EPRI PWR Safety & Relief Valve Test Program:Safety & Relief Valve Test Rept, Interim Rept

ML18047A461
Person / Time
Site:	Palisades
Issue date:	04/30/1982
From:	ELECTRIC POWER RESEARCH INSTITUTE
To:
Shared Package
ML18047A442	List: ML18047A440 ML18047A443 ML18047A445 ML18047A446 ML18047A447 ML18047A448 ML18047A449 ML18047A450 ML18047A451 ML18047A452 ML18047A453 ML18047A454 ML18047A455 ML18047A456 ML18047A457 ML18047A458 ML18047A459 ML18047A460 ML18047A461 ML18047A462
References
V102, NUDOCS 8207160358
Download: ML18047A461 (190)

Text

' ,! '

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.

• 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

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

• EPRI I MARSHALL PORV TEST llATA (3)

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

• PORV A=

'~

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 .

• .EPRI I MARSHALL* PORV TEST DATA (3)

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.

• EPRI / MARSHALL PORV TEST DATA (4)

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