ML20138P925
| ML20138P925 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/23/1985 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8512260352 | |
| Download: ML20138P925 (11) | |
Text
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1 Public Service ri i
Electric and Gas j.
Company Corbin A. McNeIH, Jr.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609339-4800 Wce Presiuent -
- Nuclear December 23, 1985 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission
.7920: Norfolk Avenue
-Bethesda, Maryland 20814
. Attention:
Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing DearLMs. Adensam MANUAL / AUTOMATIC INITIATION DESIGN OF BAILEY SOLID STATE LOGIC MODULE HOPE CREEK GENERATING STATION DOCKET NO.' 50-354 As-a result of the telecon held on December 17, 1985 between representatives of Public Scrvice Electric and Gas Company (PSE&G), Bechtel, and.the NRC concerning manual / automatic initiation design of Bailey Solid State Logic Module (SSLM);
PSE&G notes the following:
l.
The single failure criterion is satisfied for each safety-related system that utilizes the SSLMs since the minimum number of operable channels required to perform the safety function is less than the total number of channels provided.
For each monitored variable, a list of the number of channels required to satisfy single failure criteria is provided in Table 3.3.2-1 of the Hope Creek Technical Specifications.
2.
Channel Checks and Channel Functional Tests shall be performed in accordance with Technical Specifications.
These tests are identical to those done on relay plants and will assess the operability of the instrument channels O
as per Technical Specifications.
The operability of the SSLMs is assessed during Logic System Functional, I
Testing.
These tests are performed in accordance with Technical Specifications.
8512240352 851223 PDR ADOCK 05000354 A
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Director'of Nuclear 2
12/23/85 Reactor Regulation t
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In the event you require further information on this subject, do not hesitate to contact us.-
Sincerely, C.
D.H. Wagner USNRC Licensing Project Manager R.W..Borchardt USNRC Senior Resident Inspector l
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OUESTION 210.56 (SECTION 3.9.6)
There are several safety systems connected to the reactor coolant pressure boundary that have design pressure below the rated reactor coolant system (RCS) pressure.
There are also some systems which are rated at full reactor pressure on the discharge side of pumps but have pump suction below RCS pressure.
In order to protect these systems from RCS pressure, two or more isolation valves are placed in series to form the interface between the high pressure RCS and the low pressure systems.
The leak tight integrity of these valves must be ensured by periodic leak testing to prevent exceeding the design pressure of the low pressure systems.
Pressure isolation valves are required to be category A or AC per IWV-2000 and to meet the appropriate requirements of IWV-3420 of Section XI of the ASME Code except as discussed below, e
Limiting Conditions for Operation (LCO) are required to be added to the technical specifications which will require corrective action; i.e.,
shutdown or system isolation when the final approved leakage limits are not met.
Also, surveillance requirements which will state the acceptable leak rate testing frequency shall be provided in the technical specifications.
Periodic leak testing of each pressure isolation valve is required to be performed at least once per each refueling outage, after valve maintenance prior to return to service, and for I
systems rated at less than 50% of RCS design pressure each time the valve has moved from its fully closed position unless justification is given.
The testing interval should average to be approximately one year.
Leak testing should also be performed after all disturbances to the valves are complete, prior to reaching power operation following a refueling outage, maintenance, etc.
The staff's present position on leak rate limiting conditions for operation must be equal to ar less than 1 gallon per minute (GPM) for each valve to ensure the integrity of the valve, demonstrate the adequacy of the redundant pressure isolation function and give an indication of valve degradation over a finite period of time.
Significant increases over this limiting value would be an indication of valve degradation from one test to another.
The Class 1 to Class 2 boundary will be considered the isolation point which must be protected by redundant isolation valves.
In cases where pressure isolation is provided by two valves, both will be independently leak tested.
When three or more valves provide isolation, only two of the valves'need to be leak tested.
210.56-1 Amendment 8
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HCGS TSAR 10/84 Provide a list of all pressure isolation valves included in your testing program along with four sets of Piping and Instrument Diagrams which describe your reactor coolant system pressure isolation valves.
Also discuss in detail how your leak testing program will conform to the above staff position.
RESPONSE
The reactor coolant pressure boundary has been reviewed for interconnecting safety-related low pressure systems.
Table 210.56-1 summarizes the results of this review.
The table identifies the reactor coolant system pressure isolation valves and details the extent of compliance with the staff's position.
Also idontified in Table 210.56-1 are those pressure isolation valves that are leakage tested.
M The HCGS uses two isolation valves.
The isolation valves are periodically leak rate tested as 10 CFR 50, Appendix J, Type C
,f If valves or ASME Section XI, Category A valves.
In the event of isolation valve leakage a safety relief valve will further protect the low pressure system.
As an alternate to conducting a liquid leak rate test using reactor coolant operating pressure, PSE&G proposes to fulfill these leak rate test requirements using the results of the Appendix J, Type C, test program.cnd
- igning ;;ch v;1vc an individ;;l Ic;k d
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In support of conducting Appendix J leak rate testing in place of jgg( a liquid test at reactor coolant system operating pressure, PSE&G
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- ::: triconductfa program consisting of the analytical jg3 justi11 cation andf if nec;;; ri ' physical testing.
The intent of this program /te to ensure that Appendix J testing in conjunction r
"Nb with the pressure relieving device installed in these systems supplies the assurance that the structural intecrity of these N
sys; ems is maintainedd/ M the etent thic pre;r r 10
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- :::::::::, th: pr:::;r: 10:!: tier V !ver ri!! he 10 P r:tc
-tected ir ::::rdene ritF th P"C ct:ff's pe;iti;n ;;ing liquid at r;; ter ceelant syste spcr: ting pre::;rt.
The rc:;lt: Of this pregr;; will bc ::Scitted it th P"O f:r r rice pr!Or te-f; 1 1;;d.
In addition to leak rate testing each refueling outage, each pressure isolation valve will be leak rate tested prior to returning to service after:
1.
Maintenance has been performed that could affect the seat leakage rate; 210.56-2 Amendment 8
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,The resultsiofithis program was submitted to Ms. E. Adensam Is.C4
,~ f rom' Mr. C. A. McNeill -.in ' a letter dated ' December 1985.
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.The systems-rated at <50% of RCS design pressure, each time
.the valve has moved from its fully closed position, except when the testing would put the plant in a limiting condition of operation,.or provisions are made to monitor the low pressure side of the valve for leakage or pressure d'
increases.
Four sets of full size P& ids were submitted under separate cover.
The P& ids that the NRC' staff will need to review this response are identified in Table 210.56:2 m
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4 210.56-3 Amendment 8
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AfCGS FSAR 1:';/A ')
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TABLE 210.56-1 Page.1 of 2 l
SAFETY-RELATED I,CM PRESSURE SYSTEMS CONNECTED TO THE RCPB I
l RPV Containment Ccnnecting Line Pressure Leak Safety-Reltet Mge PenetraMon Descrirtion Isolation Valve Tested __Protectiog _
N 1B P-3 RHR Shutdown BC-V16sta3 is3 t.3 Coolir.q Suction BC-V07It: 3 (a3
.: i -E P-4A RHR Shutdcwn BC-V313taa c:a cs3 g
v Cooling Peturr.
8C-v014t:Its3 (3
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BC-V118ta3 (sa g
'h Pee RHR Shutdowr.
BC-V110t**
(s3 tel Cooling Peturr.
BC-V111ea3is3 (a3 BC-V117ea3 es3 g
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N54 F5A Core Spray BE-V003<aa ea3 (a3 g
bE-V002t3(s tn3 g
BE-V072c: 3 (a3 l
l N5B P5B Core Spray B E-V007 t :3 (33 (sal g
HPCI to Core Spray
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BE-V006t:3ts:
(33 g
,BE-v071 3
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N6A f10 RHR, PPV Head BC-V0203 (n3 cs3 Spray BC-V021ta3 (sa N17A E6A RHR, LPCI BC-V004(a3 csy
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BC-V005t:3tS3 (33 l
BC-V1223 (a3 l
N178 56B RHR, LPCI BC-v016tra ts3 esa g
BC-V017taats3 cas g
BC-V120ts)
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N17C f6D RHR, LPCI bC-V1015a3 is3 (as3 i
BC-V102 casts:
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BC-V121t:3 (s3 l
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TABLE 218. 56-1 (cont %
Page 2 of 2
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' RPV Containment' Cosmecting 1.ine Pressere-Leak Safety-melief-ggggig EggginG 2g Descript ion Isolatious Valve yested Protection N17D PM RHR, LPCI BC-V113ts3 883-top g
BC-V114t*3t*3
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BC-V1198 3 883
-l ta3 1st stessure isolation valve.
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(23 2nd psessure isolation valve.
l 883 Leat rate tested in acecrdance with 10 CFR 50, Appendix J.
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(*3 leak rate tested in accordance with ASME,Section XI.
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(*3 Functic w 11y tested as a Category C check valve in accordance with ASME, Section KI.
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(*3 safety relief valve - SC-PSV-F029 provM = overpressure protection. It has a 170 psig l
l-setroint and a 10 gpa capacity.
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473 iafety relief valve DC-PSV-F025E provides overpressere protection. It has a 410 peig I
setrcint and a 10 gpa capacity.
l 883 safety-relief valve BC-PSV-F0254 provides overpressure protection. It has a 410 psig set l
Fressure and a 10 gym capacity.
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(*3 safety relief valve B3-PSV-F017 provides overpressere protection. It has a 100 psig setpoint and a 10 gpa capacity.
S ee3 safety relief valve BJ-PSV-f 020 provides overpressure protection. It has a 100 psig setpoint and a 15 gpm capacity.
casa safety-relief valve BE-PSV-f0122 provides overpressere protection. It has a 500 psig l
setsoint and a 100 gpa capacity.
Ess3 safety-relief valve BE-PSV-F012A provides overpressure protectioc. It has a 500 peig
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setsoint and a 100 gym capacity.
Es33 safety-relief valve BC-PSV-f025C provides overpressere protection. It has a 410 psig l
setsoint and a 10 gpa capacity.
E s* 3 safety-relief valve BC-PSV-F025c provides overpressere protection. It has a 410 peig setsoint and a 10 gpa capacity.
( ** 3 3rd pressure isolation valw. Two of the three valves are required to meet the leak rate l
acceptance criteria.
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4 Amer.dment 8
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t TABLE 210.56-2 P& IDS REVIEWED FOR INTERCONNECTING LOW PRESSURE SYSTEMS M-01-1
.Rev. 9 M-05-1, Sh. 3 Rev. 9 M-06-1 Rev. 6 M-08-0, Sh. 1 Rev. 11 M-08-0, Sh. 2 Rev. 11 M-23-1, Sh. 2 Rev. 5 M-38-0, Sh. 1 Rev. 2 M-41-1, Sh. 1 Rev. 8 M-41-1, Sh. 2 Rev. 7 M-42-1, Sh. 1 Rev. 5 M-43-1, Sh. 1 Rev. 8 c
M-44-1 Rev. 6 M-46-1 Rev. 6 M-47-1 Rev. 7 M-48-1 Rev.
4.
M-49-1 Rev. 9 M-50-1 Rev. 9
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M-51-1, Sh. 1 Rev. 9 M-51-1, Sh. 2 Rev. 10 M-52-1 Rev. 10 M-55-1 Rev. 10 M-56-1 Rev. 8 H-72-1 Rev. 2 Amendment 6
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ATTACHMENT 2
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I$T PROEDURE
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t TE!rrPROCEDURE TO DEVELOP AIR VS. WATER CORRELATION FOR LEAK TE$r!NO OF HOPE CREEE REACTOR COOLANT BOUNDARY VALVES
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I"APPROVEDSY:
APPROVED BY i
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PMOJECT MANAGEA:
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APPROVED 8Y POR:
QUAUTY ENGINEER
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3 APPMOVED BY:
PREPARF.D SY M
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PROJECT ENGINE i
o REVISIONS I
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cara essas aaractao av aart onscaleriou or cwanais -
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10/28/85 All
/pgf Revised Lab Test System Added info to Q.[.f)jf,[f Field Test: Revised wording of basic i
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.jL; M;,/($
Procedure.
2 11/20/85 2
(( ()y,/,,)cAdditional information regarding test ML/[,h ob j.n: t tve 4.
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g///,4v/.y/f Add'1 infomation regarding field test
- j 6 through 18 Anoendix f. new onees.
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r 17701"I Paoca00M NO.
2 uv. No. November 20,1985
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10 PAot oF 1.0 PURPOSE The purpose of this procedure is to present the test methods to be used to develop correlation data for velve leakage with low pressure air or nitrogen in place of high pressure water.
The objective of the test program is to provide PSE&G with both analytical and empirical justification that satisfactory compliance to 10CFR50 Appendix J. Type C Re' testing will meet or exceed the requirement that reactor or coolant pressure boundary 2
isolation valves, at reactor coolant pressure, have an individual leakage of less than one gallon per minute for any valve.
(
The establishment of such justification would eliminate a need to perform the high pressure leak test prior to returning to power after an outage, or after valve repairs.
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In other words, c'imination of the high pressure leak tests could be justified on a 2
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correlation of Typs C tests at 48.1 psig to high pressure leak, tests with water at 1020 poig.
'I
2.0 REFERENCES
I
.i 2.1 Public Service Electric & Gas P.O. #083496
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2.2 PSE&G Speelfication for Acceptability of Using Air Versus Water for Leak
'i Testing of Reactor Coolant Doundary Valves
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2.3 10CFR50 Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors 2.4 Plow of Fluids, Crane Technical Paper No. 4,10 2.5 Flowmeter Computation Handbook, prepared by the ASME Research Committee
'l' on Fluid Meters 3.0 GENERAL REQUIREMENTS
- ![
3.1 Test Specimen, Laboratory Tests The test specimens shall consist of several locally made, very small diameter
.;[4 orlflee fittings, and two or three micrometer valves.
3.2 Test Arrangement, Laboratory Tests t he tea arrunuument shall be a sptcia na depletc<!:chentalle911y la Figuro 1.
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L PLANT SERVICES DIVISION l
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Pecca00na no. I7761-1 nev. no.
2 November 20. 1985 DaTE 3
IO PAGE OF 3.3 Test Instrumentation Test instrumentation shall consist of two pressure gages,0-100 or 150 psig and 0-1500 psi, an inlet temperature measurement thermocouple, a rotometer or mass flowmeter for measuring nitrogen flowrate and a flowmeter for measuring water flowrate. The instrumentation shallbe as shown in Figure 1.
i 4.0 Terr 5
!l 4.1 Laboratory Tests j
t 4.1.1 Each test specimen will be installed in the test system and subjected to a flow test first using nitrogen and then using water. Inlet pressure r-I to the test specimen shall be regulated to 48.1 psig for the nitrogen lI' test, and to 1020 psig for the water Test. ' Water pressure will be obtained using nitrogen over water in the accumulator.
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micrometer valves will each be tested over a range of openings (Turns i1 l1-Open). For each orifice and for each set valve opening the nitrogen flow test will immediately be followed by the water flow test. For
, j' each test, flowrate will be determined using the appropriate flowrate meter. Temperature of the test fluid will be recorded and will be 1
maintained as near the original ambient temperature as reasonable time between tests will allow.
A variation of several degrees r.[,
fahrenheit during nitrogen or air tests is acceptable.
4.1.2 A large range from near zero to over 70,000 SCCM flowrate of nitrogen is desirable and the micrometer valve settings should be adjusted accordingly. Water flowrates from near zero to over 2 OPM 4,
are desirable and settings adjusted accordingly. Test sequence from I
,i nitrogen to water should always be maintained for each orifice and valve setting.
a lc 4.1.3 Data from the laboratory tests for each fluid will be plotted for the series of orifice tests and for each valve series of openings. Bis data as plotted should closely approximate a straight line which would in indicate close agreement with the basta equations for fluid flow through orifices. If such agreement is found, then for each orifice l-area and for each valve and its series of openings, a plot of nitrogen flowrate versus water flowrate will be made. If the previous plots (i
provided straight line relationships, this plot will also provide straight lino relationship 4; and if the datn N ecmhtent for the urlou:1 test specimens, the lines for cach specimen will have nearly tho same slope.
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PLANT SERVICES DIVISION r.40.'"""
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PROCEDURE No. 17761-1 REV.No.
2 DATE NOVamher 20- 1985 A
IO PAGE oF 4.2 Field Tests 4.2.1 If analysis of the above laboratory tests indicate a consistent relationship for the various test specimen openings (i.e., a consistent slope for the nitrogen flowrate versus water flowrate plot), field testing wul be performed by PSE&G.
P 4.2.2 Field testing wul be accomplished in accordance with PSE&G, PSSUG-PTP-GP-2. Air wul be used instead of nitrogen, and test pressures and temperatures wul be held as close as possible to those of the laboratory tests. Valves to be tested willbe selected from those listed in reference 2.2 above, and are installed valves at the Hope Creek
'+
Generating Station.
Testing will be accomplished by PSE&G de-
/,;
signated personnel. Copies of Appendices 4A and 4C of PSSUG-PTP-l Res 2
GP-2 are includ.ed in Appendix I of _this Procedure.
'Ihese two Appendices are the operating instructions for the Volumetries Leak e*
Rate Monitor and for the high pressure hydraulic leak rate monitor respectively. Diagrams of the test systems for these two leak rate l Ret 2
monitors are also included in Appendix 1.
6' 7'
5.0 FINAL REPORT l>$
t 5.1 The final report will be prepared upon completion of alllaborataory and field
(*
testing. Data from the field tests will be compared with the laboratory test data and the extent of correlation noted for field water flowrates as compared i
i to laboratory water flowrates for any given air or nitrogen flowrate.
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- J PLANT SERVICES DIVISION
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17761-1 PROCEDURE NO.
2 REV. NO.
DATE November 20. 1985 PAGE 5
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LABORATORY TEST SYSTEM 9
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LEGEND:
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1.
Pressure Regulator 2.
Vent Valve II 3.
Accumulator L,
I 4.
Water Flowmeter I
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5.
Thermocouple 6.
Pressure Gage p
7.
Orifice or Test Valve Installation 8.
Rotometer or Massflow Meter for GN 2
- 1n Measurement L)
FIGURE #1 7
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PnoctDURE NO.
17761-1 j;J, O '.
nay, no, 2
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DATE November 20. 1985 g
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- l; APPENDIX I o.
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j Procedure No.
17761-1 R.2v. No.
2 Data: November 20, 1985 Page 7 of 18
- APPEND % 4A TEST 'BQUIPMENT OPERA'!TNb INSTRUC110NS LOCAL LEAK RATE MONITOR
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i 1.0 ' Equipment ;-
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'Ihe local leak rate monitor is a portable self-contained instrument that
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. pressurizes.the test volume to a prescribed pressure.
Using a pressure regulator,to maintain test pressure, the;make up fluid to the test volume reqdred to maintain test pressure is measured using a flow meter which is a m-direct measurement of lockage rate.
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, ' ~k 1.2 Leak rate monitor will be operated in accordance to the manufacturer's operating manual
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1.3
. Test tubing (High density polyethylene' tubing' 1/4" x 0.040" wall).
j ' tl 2.0 Leak Rate Test Procedure j
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2.1 Turn power switch on (120V AC) and allow 30 minute warmup.
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- 31; 2.2 Adjust pressure zero control potentiometer to indicate zero pressure (10.1 i
psig).
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- t' 2.3 Connect the instrument to a supply of extra dry nitrogen and adjust nitrogen supply to 150 psig.
L' 7f)Ii 2.4 Flow calibration check (at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)./
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2.4.1 Turn range value and range switch to low.
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2.4.2 Turn mode valve to cal low.
Directs flow through low range cahkated leak.
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2.4.3 Adjust low zero flow transducer potentiometer to indicate zero flow
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i (11.0% of low range).
1-2.4.4 Adjust ressure regulator to apply the calibrated leak check LI j
pressure (determined at least calibration).
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2.4.5 Read flow rate and determine if within range of calibrated leak.
,U Proceed to calibration check the various rcnges by repeating step 2.4.
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'I APPENDIX -4A REV.NO.0
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Procadure No.
17761-1 Rev. No.
2 Date: Noveabsr 20, 1985 Page 8
of 18 2.4.6 - If any range is not within the Test Orifice Cclibration Range eriteria return for repair. All ranges are independe it of each other.
If one range (flow transducer) does not meet its salibration check this does not effect the other ranges and 2.5 Turn range valve to charge and mode value to set test. Adjust pressure regulator to the desired test pressure (-0, + 0.5 psig).
2.6 Connect instrument to the component being tested using the appropriate y
i length tubing with shut off valve at end of test tubing. Valve in off position.
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2.7 Turn range valve to low and mode valve to test.- Adjust pressure regulator to test pressure and allow instrument to stabilize. Determine if test tubing i
1 and test setup leaks and eliminate if any.
' T' 2.8 Open test tubing valve and test component connection valve. Allow test component to pressurize to test pressure (-0,.+ Q.5 psig)..
[,o 3' 4 2.9 When test pressure is obtained allow system to stabilize for minimum of 15 minutes.
4; oj 2.10 Maintain stable test conditions for test period minimum of 15 minutes.
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.2.11 Record data on test sheet.
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' 3.0 System Shutdown l L1.
J 3.1 Close test component connection valve and test tubing valve.
i 3.2 -
Turn mode valve to set test.
3.3 Decrease pressure to zero with pressur? regulator.
hU 3.4 Close nitrogen tank valve.
}:l' 4 3.5
' Disconnect test tubing, test set to test component and test set to nitrogen 3-.j tank.
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q-3.6 Turn power switch off.
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Procsdure No.
17761-1 R:v. No.
2 Date:Novxt.ber 20, 1985 Paga i
cf 18 APPENDIX 4C
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TEST EQUIPMENT OPERATING INSTRUCTIONS HIGH PRESSURE HYDRAULIC LEAK RATE MONITOR 1.0 Equipment
.1.1 he hydraulie leak rate monitor is a portable self-contained instrument that pressurizes the test volume to a prescribed pressure, using a hydraulic pressure
- [,.
regulator to maintain pressure.
Makeup fluid (demin. water), to the test volume required to maintain test pressure, is measured. Using a liquid flow I L' rate measuring transducer provides a direct measurement of in-flow leakage rate.
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t 1.2 High pressure air driven. liquid pump (0-1500 psi output pressure, 5 gpm liquid
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flow with 50 psi,175 SCFM air pressure).
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1.3 Hydraulic leak rate monitor and high pressure air driven liquid pump.will be
-f operated in accordance to the manufacturer's operation manual
\\9 1.4 Hydraulic test hoses with shutoff quick connect (thermoplastic tube with 6
-L
double braid synthetic reinforcement) maximum operating pressure 2000 psi.
Hose ends are to be capped at all times to prevent foreign material from
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entering test hoses.
4-ti 1.5 Test hose shutoff-bleed valve and calibrated high pressure gage (0-1500 psig).
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1.6 ~
he hydraulic leak rate monitor shall be connected to the high pressure air
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driven liquid pump as follows:
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1.6.1 Hydraulic leak rate monitor tank fill connection to hydraulic tank.
3 1.6.2 Hydraulic leak rate monitor drain-tank connection to hydraulic tank
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. [O drain.
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PSSUG-PTP-GP-2 1
APPENDIX 4C I7 REV.0 U
PAGE 1 OF 4 q
IJ aII r 5 9.
Procsdura No.
17761-1 Rsv. No.
2
=~
Date:
November 20, 1985 Page 10 of 18 1.6.3
~ Hydraulic leak rate monitor high pressure connection to-air pump liquid high pressure connection.
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1.6.4 Hydraulic leak rate monitor air connection to air pump air connection.
2.0 Hydraulic leak rate monitor hook up.
.r-2.1 Connect the instrument to a supply of demineralized water (60-100 psig) use
.~]
only localleak rate hydraulic test hose.
?!
n 2.2 Connect the instrument to a supply of station air (125 psig) use station air
- l-j.
hoses.
2 Connect the instrument using hydraulic localleak rate hose to test componen.t,.
7 2.3
.!~d with shutoff-bleed valve and calibrated test gage at. test component end-
...l7(.
~ 3.0 Hydraulic Leak Rate Flow Calibration Check Procedure (At least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
~
3.1 Tum power switch on (120V AC) and allow 30 minute warmup.
t['
3.2
. Adjust low pressure zero control potentiometer to indicate zero pressure (10.1
- g i' psig).
- j p t
3.3
' Connect the instrument to a supply of demineralized water (60-100 psig). Use U
only localleak rate hydraulic test hose.
.i 3.4 Tum switch on low flow transducer to zero.
3.5 Adjust low flow transducer zero potentiometer to indicate zero flow (+ 1.0%
- l" of flow range).
[y g.
..b 3.6 ~
Tum switch on high flow transducer to zero.
.I9 3.7 Adjust high flow transducer zero potentiometer to indicate zero flow (11.0%
- 3. Ii of flow range),
n M
3.8 Connect the instrument drain to suitable drain.
!t
- f ~ "
3.9 Tum DI-WATER valve on.
't b PSSUG-PTP-GP-2 APPENDIX 4C 2<
REV. O 1
J'l PAGE 2 OF 4
!hd FT l
.w
, -, - - - -, ~,,,..
- - -. -, +,
a., - - - -
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,,-.---,,,.---n-n-,
.,n.-~,a,,+,
,,es-
+ +
Proc 2 dure No.
17761-1 Rav. No.
2 Date:
November 20, 1985 Page 11 of 18 3.10 Turn FLOW-RANGE valve to low.
3.11 Turn CAL-CHECK valve to on.
3.12 Adjust hydraulic pressure regulator to apply the calibrated leak check pressure (determined at last calibration).
3.13
. Read low flow rate and determine if within range of calibrated leak. If within tolerance proceed to calibration check the high low range by repeating steps 2.12-2.13 with flow range valve to high.
r 3.14 If any range is not within the acceptance criteria return instrument for repair and calibration. Ranges are independent of each other. If one range (flow I_,,
- transducer) does not meet its calibration check this does not effect the other range and may be used for certified testing.
r,
. 'I 3.15 Turn CAL-CHECK valve ~off.
~'
~~
[ [1;I 3.16 Decrease hydraulic pressure regulator (turn counterclockwise).
2
^
4.0 Leak Rate Test Procedure 4G l
' 4.1 Maintain hydraulic tank at 1/2 - 3/4 full during complete test using the DIWATER tank needle val re.
l
} }r, 4.2 Turn flow range valve to high flow and mode valve to test.
- i 4.3 Turn switch to high pressure transducer.
- I,i
- .i.
4.4 Turn AIR valve on, air transducer, regulator decreased (counterclockwise).
[l ['
- 4.5 Increase high pressure by increasing AIR pressure regulator and adjust high t;
pressure relief regulator to the maximum high pressure. This will relieve pump pressure to tank and maintain test pressure flow by adjusting AIR lq regulator.
4.6 Crack bleed valve and purge hydraulic test hose of air. Turn valve to off
- ]s j
position.
l~J' PSSUG-PTP-GP-2
[' ' ( i -
APPENDIX 4C RU G i^~
PAGE 3 OF 4 9.
l u
m a
.6
- 7. -
Procedure No. 17761-1
+
Rsv. No.
2 Date:
November 20, 1985 Page 12 of 18 4.7.
Turn test commponent valve on and determine component head presure,
~
record.
4.8 Adjust high pressure relief regulator to test pressure plus head pressure.
~
4.9 Open hydraulic test hose valve and allow test component to pressurize to test pressure plus head pressure.
.,[
4.10 When test pressure is obtained, allow system flow to stabilize. Stabilization is a steady flow rate at test pressure.
4.11 Record data on attached test sheets.
1,7,
- 5.0 System Shutdown m
5.1 Reduce high pressure by reducing air pressure.. regulator to air pump j.
(counterclockwise) to the~ pretest he'ad pressure turn mode valve to off.
4
- ?'
5.2 Reduce high pressure by reducing air pressure regulator to air pump y
(counterclockwise).
o
. :' #1 5.3 Turn air valve off.
- ! h
]
5.4 Turn test component valve off.
t n
,L 5.5-Turn test connection valve to bleed.
Relieve test pressure from hydraulic ll test hoses.
'J r; i 5.6 Disconnect hydraulic test hoses DIWATER to instrument, instrument to test
!.\\
component. Cap all hydraulic test hose ends.
i
![l 5.7 Turn station air off and disconnect station air hose to instrument.
]
5.8 Drain hydraulic tank and disconnect drain hose from instrument.
!O PSSUG-PTP-GP-2 APPENDDC4C
,l3 REV.O J
PAGE 4 OF 4
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ATTACHMENT 3 1
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r I
r-CER'IYFICATION TEST REPORT OF l
AIR VS. WATER CORRRLATION s
l FOR LEAK TESTING OF HOPE CRRRK REACTOR COOLANT 1
BOUNDARY VALVES r
3 5$. l'i
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REVISIONS
^
es=
TEST REPORT NO. 17761-1 November 20, 1985 DATE.
M SCIENTIF#C SERVICES AND SYSTEMS GROUP l CEV NO l DATE PAGES AFFECTED
! B)
A Pp'.
i DESCRIPTION OF CH ANGES
[ h. { g g fJranges in text anc organi::ation f or A
11/20/85. through S
(;/
l customer clarity.
i f
l9 New page, " Appendix I" 10 through 29 l
l l
Page number change only.
30 New page, " Appendix II" 31 through 36 Page number change only.
e.
37 through 71
- WM, New pages
- Appendix III - Field Test Calibration Sheets.
ri 4
1-I.
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. Li e
fu
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- n, ir
- ibo i
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4
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- 9 Form 10%3 Rev. 4 74 f
u
_i -
M icFS1gS CERTIFICATION S5"*c5S LABORATORIES GROUP Huntsville, Alabama 35807 j
1 TWX (810)726-2225 Phone (205)837-4411 17761-1 REPORT NO.
Public Service Electric & Gas Company Hope Creek Generating Station CUSTOMER F. O. NO. 083496 P.O. Box A Hancocks Bridge NJ 08038 CONTRACT l
1 NUMBER OF PAGES November 6,1985 DATE A
1.0 REQUIREMENTS l
I.
6:t The specimens for laboratory testing were subjected to tests in accordance with
, jj Wyle Test Procedure No. 17761-1, Rev.1. The specimens for field testing were subjected to tests in accordance with PSE&G LLRT Procedure PSSUG-PTP-GP-2, I'
as indicated in the Wyle Test Procedure.
,i 9 p The objective of the test program, which this report is intended to support, is to l
provide PSE&G with analytical and empirical justification that satisfactory compliance to 10CFR50 Appendix J, Type C testing will meet or exceed the requirement that reactor coolant pressure boundary isolation valves, at reactor 1
coolant pressure, have an individual leakage of less than one gallon per minute for
- f,[
any valve.
'l The establishment of such justification would eliminate a need to perform the i
i.
high presst're leak test prior to returning to powe after an outage, or after valve
' I Il repairs. In other words, elimination of the higa pressure leak tests could be justified on a correlation of Type C tests at 48.1 p ig to high pressure leak tests
! ['
with water at 1020 psig.
l Lj l';
i-STATE OF ALADAMA 1 m a s aa ase ao en: 3 'cr mes :t am 5 o o " na er man.
j
- ncivo,ng sc.c as or cons.oent.ai cama;es, reswting r,crn wre i sicec a; ss 1 npSon
,being dufv oworn.
J~^ ' s )*
~
PR
- i deposes s
- The information contained in this report of complete and f
6 1
,.I carefully ndle to the t of his knowledge true and correct in all respects jMQ g
APPROVED BY.
,,1 OUAUTY ASSU CE i
/
N'otgPubiic in and for the State of Alabama at large.
My Commission expiree
,19 FORM 1019A. Rev. Jan '84
i PAGE NO.
2 TEST REPORT NO.
17761-1 REV. A 2.0 SPECIMEN lA For laboratory tests: six local prepared orifices with nominal diameters as follows:
.012 in
.020 in.
.031 in.
.040 in.
.052 in.
.060 in.
- l and two 1/4 inch micrometer valves.
[
For field tests: identified penetrations as per PSEG.
1
,r
~
3.0 PART NO.
lA There are no part numbers for the localprepared orifices. For the field tested I
valves, sufficient data for fullidentification is provided in the Field Test Data Sheet, Table 5, Appendix '. For the micrometer valves:
[
j Mfgr.
- HOKE P/N 1315G4Y i
- NUPRO P/N SS-2M-S6 7
i 4.0 SERIAL NUMBERS - None.
3
(
l 5.0 PROCEDURES l
(A Q
l The flow of fluids through an orifice may be expressed as follows (see L
I reference 2.4 of the Test Procedure, " Crane Technical Paper No. 410"):
E*
q = YCA rate of now where q
=
net expansion factor for compressible flow through 7
j Y
=
orifices, nozzles, or pipe flow coefficient for orifices and nozzles C
=
cross sectional area of the orifice A
=
I gravitational constant 2g
=
differential static pressure (head) across the orifice or
(
=
nozzle P=
weight density of the fluid f
l
[
C Huntsville Facility b
FAGE NO.
3 TEST REPORT NO.
17761-1 REV. A The expansion factor (Y) for compressible flow is a function of:
i 1.
The specific heat ratio k, which varies slightly with different pressures 0
and temperatures.
For air and nitrogen at 68 F and 14." psia, the specific heat ratios are 1.4 and 1.41 respectively.
2.
The ratio (# ) of orifice or throat diameter to inlet diameter.
- 3.'
Ratio of downstream to upstream absolute pressures.
7 Y~
If all the above conditions were held fixed except for area, the flowrate R
~ through a set of similar orifices would be directly proportional to the area of qrLI-the orifice, and a plot of flowrate versus area would be linear.
- L I' For the laboratory tests, a series of six different sizes of orifices were prepared by drilling holes in metal plates. No partIeular attution was given I
4 3];-
to accurate sizing or to finishing the edges of those holes. These orifice plates
~
i;.'-
along with two micrometer valves were used as specimens to gather correlated n-
' flowrate data for nitrogen at low pressure, and then water at high pressure
^
5 over a range of areas and valve openings (valve turns).
t For a meaningful correlation to exist between the laboratory data for the 4
,b nitrogen versus water flowrates it was assumed that the laboratory data for each fluid would exhibit close correlation with the above linear relationship of I:tl flowrate versus area. This further assumed that variations in the finish of the edges of the six orifices, and that slight variations in temperature of the
[
-nitrogen (compressible) fluid would not be significant. The following analyses j.
of the laboratory test data show these assumptions to be valid and that a close
! Il linear relationship exists for flowrate versus each set of specimen area variations.
(.
i
! n
,-!]
t 5I' q
La
- 4.,.
f.
I' I
WYLE MM Huntenne Fecahty
_ _ _. -., -.. - ~ _. _....... - _. _ _ _ _ _..
_ _., _ _ - _ _.. _,..., _ _ _.. ~,, _ _ _.. -, _ _ _ _ _ _., -
. ~...
e PAGE NO.
4 TEST REPORT NO-17761-1 REV. A
=
a 5.1 Laboratory Tests Six orifice sizes and two micrometer valves were installed and tested as required. The test data is included in Appendix 1, Tables 1 through 4.
Two runs were made using the HOKE micrometer valve. 'Ihe first run provided good data but was considered insufficient in coverage of the lower range of Guld flow. A second run was made providing a greater range of data.
1 i
Test fluid temperatures were local ambient and varied slightly between tests.
For the water (incompressible) test fluid, the temperature differences are considered insignificant.
For the nitrogen (compressible) test fluid, 0
[
temperatures varied not more than 2 F throughout the duration of a given f
6 test.
On an absolute temperature basis, the effect of this temperature y
variation is considered insignificant regarding now variation.
i f
Water flow data was recorded in gallons per minute (GPM) and nitrogen gas flow data was recorded in actual cubic centimeters per minute (ACCM) and 7
E converted to standard values (SCCM).
I 5.1.1 Analysis of the Laboratory Test Data i
1 f
The flowrate data for each test orifice and valve versus the orifice area or number of turns opened (Valve Turns) for the micrometer valves was plotted f
using a linear plotting program. A least square fit was computed for each and I
a slope and intercept provided. In each case, the data plotted (Figures 1, 2, 3, i
i 4,9 and 10) shows a high linear correlation over significant range of the data.
1 The data plotted for the NUPRO micrometer valve appeared to be bilinear.
f Two fits were determined and two plots are provided for each test nuid. A I
{
j straight line is plotted for a low range valve opening below 0.5 turns, Figures 5
/
{
l and 6, and for a higher range above 0.5 turns, Figures 7 and 8.
I f
The reason for the bilinear relationship is assumed to be a result of the non-linear relationship of the valve area opened with respect to valve turns. The decreased nowrate for the more " opened" valve setting supports this r
assumption. Regardless, the straight line relationships of the data as shown in all cases, figures 1 through 10 of Appendix I, exhibit the correlation desired.
1
{
f l
wns Lamonaronias r
Hutitsville FaClhty
a 6
rA;E No.
5 TEST REPORT NO.
17761-1 REV. A 5.1.2 Correlation of Nitrogen Versus Water Flowrates The laboratory tests were conducted such that for each test condition with lA nitrogen at 48.1 psig and ambient temperature, an identical test was run using water at 1020 psig and ambient temperature. A plot of the nitrogen flowrate versus the water flowrate for each identical test specimen area or opening is shown in Figure 11, Appendix 1. The best fitting straight line through each of l
the four sets of data points was determined by linear regression methods. The slope and intercept of each line was computed by the linear regression v
le program used.
The correlation of these lines with the data points was
- :i A
t.
computed to be very high, over 99%
s-
[
The four test specimen lines are shown on the correlation plot, Figure 11, ano'
]I the slope and intercept for each is as follows:
Slope Intercept
- 7
. Line 1 Orifices 38532
-1149
.l Line 2 HOKE Micrometer Valve, Run'1 34556
-2236 i
r, j
Line 3 NUPRO Micrometer Valve 38667
-8791 i
Line 4 HOKE Micrometer Valve, Run 2 33157
-1968
!r j
The equation of Line 3 is:
38667 x GPM -8791 f?
SCCM =
- i..
or for conversion: GPM = SCCM + 8791 Equation (1) g' 38667
.;t.
]f..
The equation of Line 1 is:
38532 x GPM -1149 SCCM
=
SCCM + 1149
.[ '
or for conversion: GPM =
Equation (2)
- l? U 38532
.i
- 1-e a
f I
l 6 4 M LE M M Huntevdee Facility LI
PAGE NO.
6 TEST REPORT NO.
17761-1 REV. A 5.1.3 Equipment Certifiestion and Calibration f
Instrumentation equipment and calibration sheets for the laboratory test system are included in Appendix II.
A photograph of the laboratory test system is shown in Figure 12, Appendix 1.
5.2 PieM Tests h
In that a satisfactory correlation between the water and the nitrogen flowrates was shown by the laboratory tests, field tests were conducted in accordance with the Test Procedure (PSSUG-PTP-GP-2). These field tests,are i.
similar to the laboratory tests. Completed test procedures for each of the 20 valve sets selected and tested are available from Hope Creek Generating
(,
Station records. 'lhe data obtained in these field tests is shown in Table 5, Appendix I. Of the twenty data sets obtained in the field, none has a flowrate f
l~
value greater than the least value recorded during the laboratory tests.
Data A
i:
for each air test in the field was converted to a water flowrate value using the i:
Equations (1) and (2). The computed water flowrates are shown in Table 6, Appendix I as the Correlated Data.
The two equations provide a most r-conservative and least conservative correlation.
L.
i The Line 1 correlated data is conservative for all but 4 of the actual field test g
data and is the least conservative of the two.
Line 3 correlated data is i.
l conservative for all actual field test data and is the most conservative. A F
factor of conservatism is shown for each correlation shown in Table 6 and was t.
obtained by dividing the Correlated Data by the Field Test Actual Water Flow.
i' p
L i
5.2.1 Equipment Certification and Cahbration i
Instrumentation equipment and calibration sheets for the field test system are n
I included in Appendix III.
[
p..
L.
t j'
i l
b EU MM Huntevdle Fac6hty 6
,6 PAGE NO.
7 TEST REPORT NO.
17761-1 REV. A 4
S.S RBULTS AND CONCLUBONS 6.1 Eamdts r
A The laboratory tests showed a high correlation of nitrogen and water flowrates versus area of orifice or valve opening over a significant range of the data (Figures 1-10).
he flowrates for nitrogen versus water for identical orifice areas or valve settings were plotted using linear regression methods.
Four lines were t
determined with very high linear correlation to the data. Two of these lines i;
provide a bounds to the four lines determined within the ranges:
},,
0 - 38000 SCCM Nitrogen at 48.1 psig l
f 0 - 1.2 GPM Water at 1020 psig i
These two lines represent a least conservative and a most conservative approkeh for correlation of nitrogen or air tests at low pressure to water tests
)
' p
. at high pressure (see Figure 11).
U he field tests provided lower flowrate data than any obtained during laboratory tests.
.i
[l
- i For each of the twenty field tests, the air test flowrate was used with I ]
Equations (1) and (2) to compute Correlated Data for Water flowrates. Using
]-
.the least conservative approach, Equation (2), all but four of the correlated i
'1~~r:
data obtained are conservative.
Using the most conservative approach,
!3 Equation (1), all correlated data are very conservative.
t
,4 r.
L i,'
,4 a
1 t
j I
f WYLE LABOSATOINES a
._-,-2.-..
PAGE NO.
8 TEST REPORT NO.
17761-1 REV. A C
6.2 Conehemicas R
6.2.1 Equation (1) of this report provides a conservative correlation from nitrogen or air flowrates to water flowrates for the fluids, pressures, and ranges below:
from: 0 - 38000 SCCM Nitrogen / Air at 48.1 psig to:
0 - 1.2 GPM Water at 1020 psig.
t 6.2.2 Equation (1) of this report, applied as set forth in the above Conclusion, provides a valid and conservative correlation approach to eliminate the need to perform l
high pressure water leak testing on valves which have been satisfactorily tested at low pressure using air or nitrogen.
7.0 QUAIJTY ASSURANCE
['
i' All laboratory work performed on this test program was completed in r-accordance with Wyle Laboratories' Quality Assurance Program which i
complies with the applicable requirements of MIIcQ-9858A, MIL-I-45208A, y
and NASA's NHB 5300.4 (IB & IC).
{
8.0 TEST EQUIPMENT ANDINSTRUMENTATION All laboratory instrumentation, measuring, and test equipment used in the
{^
tcl performance of this test program were calibrated in accordance with Wyle Laboratories' Quality Assurance Program which complies with the p
requirements of Military Specification MIL-STD-45662.
Standards used in if performing all calibrations are traceable to the National Bureau of Standards by report number and date. When no national standards exist, the standards u
are traceable to international standards or the basis for calibration is otherwke documented.
a f'\\
f 1
mu u 1
U j
teuntenete Facihty l
I i
F PA7E NO.~
9 TEST REPORT NO.
17761-1 REV. A 1;1 [
i
!. 9 APPENDIX I I.
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AIR VERSUS WATER CORRELA'I10N FOR LEAK TESTING TABt.E I For Pelic Service Electrie and Gas Company, Hope Creek Generating Station APPENDIX f LABORATORY TESTS Conducted 7/1/85 through 8/27/85 WYLE LABORATORIES, Huntsvine, Alabama Test Size-in /
Flowrate Nitr en Flowrate Water Line Specimen Setting-Turns (Meter Type *)
F psig ACCM SCCM (Meter Type *) "P psig GPM I.ine 1
ORIFICE 0.012 in. dia.
2 (SS float) 72 48.1 4400 4301 5
78 1020 0.12 1
2 ORIFICE 0.020 3 (glass 72 48.1 9200 8992 5
78 1020. 0.29 2
flaat) 3 ORIF;CE 0.031 1
72 48.1 22000 21504 5
78 1020 0.58 3
4 ORIF;CE 0.040 1
72 48.1 36000 35188 5
78 1020 0.96 4
5 ORIFICE 0.052 1
72 48.1 63000 61579 5
78 1020 1.60 5
6 ORIFICE 0.060 1
72 48.1 79500 77707 5
78 1020 2.06 6
2
?2E Flowrate Meter Type - see item no., Instrumentation Equipment Sheet
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1 NITR0 GEN FLOW (SCCN) YS ORIFICE AREA (SQ IN.) LSQ Flf FOR 1.139974E-94 :(X(:
2.827434E-93, SLP 2,763453E+97 INIRf 842,8265 I
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2.827434E-03, SLP 717.2145 INTRf 5.165318E-82 i
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AIR VERSUS WATER CORRELATION FOR LEAK TESTING TABLE 2 For Public Service Electric and Gas Company, Hope Creek Generathg Station APPENDIX I LABORATOltY TES'IB Conducted 7/1/85 through 8/27/85 WYLE LAllORATORIES, Huntsville, Alabama Flowrate. Nitro Flowrate. Water Test
- Size-in /
(Meter Type *) gen psig ACCM SCCM (Meter Type *)
F psig (IPM I.ine F
Line Specimen Setting-Turns 2 hns 5
68 1020 0.09 1
IlOICE 2
3 3
72 48.1 4600 4496 5
68 1020 0.18 2
1/4 neh 4
3 72 48.1 5800 5669 5
68 1020 0.24 3
Micrometer 4
5 3
72 48.1 9200 8992 5
68 1020 0.32 4
g, 5
6 3
72 48.1 11400 11143 5
68 1020 0.38 5
&n 1) 6 7
3 72 48.1 13100 12804 5
68 1020 0.44 6
7 8
3 72 48.1 15500 15150 5
68 1020 0.51 7
8 9
3 72 48.1 17000 16616 5
68 1020 0.56 8
9 10 3
72 48.1 19400 18962 5
68 1020 0.62 9
10 11 3
72 48.1 21400 20917 5
68 1020 0.68 10 11 i
12 3
72 48.1 23400 22872 5
68 1020 0.73 11 12 13 3
72 48.1 25300 24729 5
68 1020 0.75 12 g
ou 13 14 3
72 48.1 27800 27173
%{
14 v
15 3
72 48.1 28820 28170
((
?l Cs C
" 3' Flowrute Meter Type -see item no., Instrumentation Equipment Sheet
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NITROGEN FL014 (SCCM) YS, UALYE TURNS LSQ FIf FOR 3 :M: 14, SLP 2052,297 l
INTRI-1650,945
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WATER FLOW (GPN) YS, YALYE fURNS{ H0XE 1315G4Y LSQ FIf FOR 3 :(X(: 12, SLP i
6,145449E-02
.. E 5 _E.e E h.
T i
i
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TABLE 3 AIR VERSUS WATER CORRELA'I10N FOR LEAK TESTING APPENDIX I For Public Service Electrie and Gas Company, Hope Creek Generating Station ~
LABORATOILY TESTS Conducted 7/1/85 through 8/27/85 WYLE LABORATORIES, Huntsville, Alabama 2
Flowrate Nitro Flowrate ~ Water Test Size-in /
(Meter Type *) gen psig ACCM SCCM (Meter Type *) "F psig GPM f.ine F
Line Specimen Setting-Turns 1
0.04 5
73 1020 0.31 1
NUPRO 2
0.08 1
72 48.1 18000 17593 5
73 1020 0.fil 2
1/4 imb 3
0.12 1
72 48.1 23000 22481 5
73 1020 0.77 3
. Micrometer 4
0.16 1
72 48.1 28500 27857 5
73 1020 0.97 4
gyg 5
0.20 1
72 48.1 34000-33233 5
.73 1020 1.12 5
6 0.24 1
72 48.1 40000 39097 5
73 1020 1.35 6
7 0.28 1
72 48.1 45500 44473 5
73 1020 1.38 7
8 0.40 1
71 48.1 62500 61205 5
73 1020 1.85 8
9 0.60 1
71 48.1 76500 74915 5
73 1020 2.12 9
i 10 1
0.80 1
71 48.1 80000 78342 5
73 1020 2.20 10 11 l
1.00 1
71 48.1 84000 82259 5
73 1020 2.40 1I i'
1.20 1
71 48.1 87500 85687 5
73 1020 2.50 12 g
12 8"
13 1.40 1
71 48.1 89500 87645 5
73 1020 2.58 13 E
5 73 1020 2.fio 14
%2 14 1.60 1
71 48.1 Note 1 N$
5 73 1020 2.70 15 15 1.80 1
71 48.1 Note 1
.x.x V
5 73 1020 2.84 16 16 2.00 1
70 48.1 Note 1 w-GU*
Note 1: Flow meter readings not on calibration curve; no data.
- .L Flowrate Meter Type -see item no., Instrumentation Equipment Sheet
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, SLP 16402.5 INIRI 65367..':_____
1-t
+,89E+05:
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- o e
l WATER FLOW (GPM) YS, YALYE filRNS; MllPR0 SS-2M-S6 LSQ FIf FOR.4 :M: 2, SLP i
.556667 INTRT 1,753111 i
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+
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For Pihlic Service Electrie and Gas Company, Hope Creek Generating Station.
TABLE 4 (pg.1 of 2)
AIR VERSUS WATER CORRELA'I10N FOR LEAK TESTING APPENDIX I LABORATORY - TESTS Conducted 7/1/85 through 8/27/85 WYLE LABOltATORIES, Huntsvine, Alabama Flowrate Nitro Flowrate Water Test Size-in /
(Meter Type *) gen psig ACCM
.SCCM (Meter Type *)
F psig GPM I,ine F
Line Specimen Setting 'litrns 1
1 2A 78 48.1 440 425 1
liOKE 2
2 1-1/2 2A 78 48,1 1200 1160 1/4 inch 3
2 2A 78 48.1 2200 2126 5
75 1020 0.08 3
Mimmte 4
2-1/2 2B 78 48.1 3360 3248 5
75 1020 4
g,33 5
3 2B 78 48.1 4460 4311 5
75 1020 0.16 5
(Run 2) 6 3-1/2 3A 78 48.1 4800 4639 5
75 1020 6
7 4
3A 78 48.1 6200 5992 5
75 1020 0.25 7
8 4-1/2 3A 78 48.1 6600 5379 5
75 1020 8
9 5
3A 79 48.1 8400 8104 5
75 1020 0.32 9
10 5-1/2 3A 79 48.1 9400 9069 5
75 1020 10 l'1 6
3A 79 48,1 10000 9647 5
75 1020 0.38 1I o
E" 12 6-1/2 3A 79 48.1 11000 10612 5
75 1020 12 5'
13 7
3A 79 48.1 12000 11577 5
75 1020 0.44 13 2 s'
., R 14 I.
7-1/2 3A 79 48.1 12800 12349 5
75 1020 14 zz i
15 8
3A 79 48,1 14400 13892 5
75 1020 0.50 15 m-u Q Of '--
+
E 3.'.
Flowrate Meter Type -see item no., Instrumentation Equipment Sheet i
U AIR VERSUS WATER CORRELATION FOR LEAK TESTING TAHI,E 4 (pg. 2 of-2).
For Pihlic Service Electrie and Gas Company, flope Creek Generating Station APPF.NDIX i LABORATORY TESTS Conducted 7/1/85 through 8/27/85 WYLE LABORATORIES, Huntsvine, Alabama Flowrate Water Test
- Size-in /
Flowrate Nitrogen Line Specimen. Setting 'Ibrns (Meter Type *)
F psig ACCM SCCM (Meter Typc*) "F psig GPM I.ine 16 8-1/2 3B 79-48.1 16200 15629 5
75 1020 16 llOKE 17 9
3B 79 48.1 16800
'16208 5
75 1020 0.55 17 1/4 inch 18 9-1/2 3B 80 48,1 18200 17525 5
75 1020 18 Micrometer 19 10 3B 80 48.1 19000 18296 5
75 1020 0.62 19 ygg
~20 20 10-1/2 3B 80 48.1 20200 19452 5
75 1020 (Run 2) 5 75 1020 0.65 21 21 11 80 48.1 22 12 80 48.1 5
75 1020 0.69 22 1
23 13 80 48.1 5
75 1020 0.73 23 24 14 1
78 48.1 24500 23680 5
75 1020 0.77 24 25 15 5
75 1020 0.81 25 26 16 5
75 1020 0.85 26 e
27 17 1
78 48.1 28500 27546 5
75 1020 0.87 27 E
5 75 1020 0.89 28 37 28 18 29 19 5
75 1020 0.93 29 zz PP 30 20 1
78 48.1 31000 29963 5
75 1010' O.94 30 gzg e
?
> i~
Flowrate Meter Type - see item no., Instrumentation Equipment Sheet
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+,75E+00 s
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,,.3 AIR VERSUS WATER CORRELA'110N FOR LEAK ' TESTING TAHl.E 5 (pg. l of 2)
For Pihlic Service Electrie and Gas Company, Hope Creek Generating Station APPENDIX 1 FIELD TESTS Conducted 7/09/85 through 10/17/85 WYLE LABORATORIES, HuntsviDe, Alabama LLRT DATA Penetra-AIR TEST W ATER TEST tion Valve (s) Valve Valve Type Valve Pressure Leakage Date Pressure ieakage Date Line I.D.
No.
Description Size psig SCCM
'85
. psig GPM
'85 1.ine 1
P3 BC-V164 RHR Shutdown Gate 20" 48.3 256 10/12 1020 0.04 10/13 i
Cooling Suction 2
P3 BC-V071 RHR Shutdown Gate 20" 48.5 470 10/12 1020 0.03 10/13 2
Cooling Suction 3
P4A BC-V013 RIIR Shutdown Gate 12" 48.1 18 8/15 1015 0.005 8/15 3
Cooling Return 4
P4A BC-V014 Stop Check 12" 48.2 15 8/08 1015 0.002' 8/08 4
P4A BC-V118 Globe 1"
5 P4B BC-V110 Globe 12" 48.4 50 8/14 1020 0.005 9/10 5
6 P4 ti 11C-V111 Stop Check 12" 48.3 165 9/03 1020 0.003 9/10 6
g P41<
BC-V117 Globe 1"
7 P5A BE-V003 Core Spray Gate 12" 48.2 7/20 1020 0.014 7/10 7
8 PSA BE-V002 Stop Check 12" 48.4 230 9/18 1020 0.013 9/10 8
ff BE-V072 Globe 1"
GU Gate 12" 48.3 2.78 9/17 1020 0.056 9/24 9 y 9
P5B BE-V007 y
I"
.u
. _ ~..-
AIR VEESUS WATER CORRELATION FOR LEAK TESI1NG TAHLE 5 (pg. 2 of 2)
For Pt&lic Service IDeetrie and Gas Company, Hope Creek Generating Station APPENI)IX I FIELD TESTS Condmeted 7/09/85 through 10/17/85 WYLE LABORATORIES, HuntsviDe, Alabama LLRT DATA Penetra-AIR TEST WATEli TES P tion Valve (s) Valve Valve Type Valve Pressure Leakage Data Pressure 1,enkage Date Line I.D.
No.
Description Size psig SCCM
'85 psig GPM
'85 I,ine B
Stop CM l2" 48.3 2.78 9/17 1020 0.048 9/24 10 10 Core Spray BE-g, t,,
11 P10 BC-V020 RHR,RPY Globe 6"
48.3 27.1 10/01 1020 0.001 10/17 II Head Spray 12 P10 BC-V021 P
Gate 6"
48.4 2.0 10/02 1020 0.001 10/17 12 13 P6A BC-V004 RilR, LPCI Gate 12" 48.1 0.9 1020 0.004 13 14 PGA BC-V005 Stop Check 12" 48.3 1267 1020 0.002 14 PGA BC-V122 Globe la 15 PGB BC-V016 Gate 12" 48.1 40.9 9/11 1020 0.04 9/10 15 16 P6B BC-V017 Stop Check 12" 48.3 437 9/09 1035 0.03 9/10 16 P6B BC-V120 Globe 1"
17 P6D BC-V101 Gate 12" 48.4 315 9/11 1035 0.01 9/12 17,,
18 P6D BC-V102 Stop Check 1"
48.5 360 9/11 1035 0.004 9/12 18 :nyy P6D BC-V121 Globe 1"
19 P6C BC-V113 Gate 12" 48.3 40.8 7/09 1020 0.05 8/30 19 20 P6C BC-V114 Stop Check 12" 48.5 305 7/29 1020 0.004 8/30- 20
-o
-s e P6C BC-V119 I,
Globe 1"
y NT
<.~
m e- -m
-~
.~
r<=:a m
m m
.3 7
Page No. 27 FIGURE 11
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Peg 2 No. 28 Test Rsport No. 17761-1 REV. A For PubMe Service Beetric and Gas Company, Hope Creek Generating Station FIRLD TEST DATA COMPARIBON TO TABLE 6 LABORATORY TESTS' CORRELATION DATA APPENDIX I WYLE LABORATORIES, Huntsville, Alabama 2
3 4
6 1
Field Test Field Test Lab Test 5
Lab Test 7
Line Actual Actual Correlated Data Factor Correlated Data Factor Air Flow Water Flow Most Conservative Least Conservative SCCM GPM GPM GPM 1
256 0.04 0.233 5.8 0.036 0.9 2
470 0.03 0.239 7.9 0.042 1.4 3
18 0.005 0.227 45.
0.030 6
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5 50 0.005 0.228 45 0.031 6.2
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i 11 21.7 0.001 0.228 228 0.030 30 7
I 12 2.0 0.001 0.227 227 0.030 30 i
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20 305 0.004 0.235 58 0.038 9.5 1
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Line No. of Field Test Data, Table 5
Appendix I
.i 2.
Actual Field Test Leakrate in SCCM i
L l
3.
Actual Field Test Leakrate in GPM 4.
Lab Test computed correlation using Field Test Air Flow Actual SCCM with equation (1),
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Factor Indicating conservatism = Correlated IMta feomputed)
GPM, most conservative.
5.
Actual Field Test Water Flow GPM I
L 6.
Ditto 4 above, but for least conservative Line 1, equation (2), in GPM.
i 7.
Ditto 5 above for least conservative.
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UQUlO AND GAS. FLOWMETER CAllBRATION SERvlCE Phase 59 M 559 3335 Cerritos Avesse Las Alemitos, Calif. 90720 a
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PSEG Rese :rch Corpori:sion RESE ARCH AND TESTING LABOR ATORY INSTRUMENT CALISRATION PRCOED. E EA M CAllBRATION TEST NO. FOR Leak Rate Monitor TYPE mg SERIAL Mo. /T Co. No. NOC DATE B' E *8f upg, Vo /_.
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(- RESEARCH & TESTING LABORATORY LRM FLOW CALIBRATION ( MFG VCLUMETRICS SERIAL NO 115 PS NC 580c ( J STANDARD LRM ( TEMP BAR PRESS-TIME FLOW FLOW RESULTS F PSIA MIt> SCCM SCCM ( 74.4 14.7 1.00 1978.9 1993.0 .70 OK 74.4 14.7 1.00 1575.3 1592.0 .83 OK r" 74.4 14.7 1.00 1183.3 1196.0 .63 OK g 74.4 14.7-1.00 988.1 998.0 .49 OK 74.8 14.7 .99 794.3 800.0 .28 OK 74.8 14.7 .99 596.6 599.0 .11 OK /* ' g 74.8 14.7 .99 398.7 399.0 .01 OK / ^ '74.8 14.7 .95 207.4 206.0 .02 OK 0.0 0.0 0.00 0.0 0.0 +0.00 v. ( 0.0 0.0 0.00 0.0 0.0 f0.00 l S* ( BROOKS FLOW RATE CALIBRATORS SERIAL NO. 8306H67406 l { BAR PRESS SERIAL NO. 2686 { r: CALIBRATION PERFORMED BY J SOBAN DATE CALIBRATED 8/2/85 ( a t t i i ( j r [' v j ( Page No. 40 g . Test Report No. 17761-1 'I k. REY.A .i k gj i
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S' PSMG Rew::n h Capor:::!on RESEARCH AND TESTING LABORATORY INSTRUMENT CAllSRATION PROCEO. ECEUEIT' CALiSRATION TEST NO. F OR Lea. Pate Menitor TYPE PAGE SERIAL N0. S 9El CO. MO. 70N DATE 9-S-C HFR. 'G CAP. h am Dmm S ce-M. A n n n e c NW. g - gy s j Flcw Integrity l Electric.1 Integrity 1 I I I ,p Range l Press l F1bw Range Ficw l () l SCC:: l PSIG l Min l Max l l Min l Hax ( I noe I jo. n l 96 l n2 l Seca l l t h I /o.n I7W I 90F l rceu I I i one 1 6o. o D.Ro I 4'. 9o I CAM i l i i I ..I I I I I l i != l l l I I I I I l i I I i l i b l l I I i i i i l i !F] l riew checks + 4s fs 8 i i i. .i, I t I i i I I i i i s.- l I I I i l I } l l l l i I i l Fi I I I i I l l l j l l l j [ l l I I l l l l I i l l l 1 ! T1 Page No. 43 ,.{ Test Report No. 17761-1 j l l I REV.A I I I i I i l l l l c I I I I I I[" l I i OCN m/ l l l l aavrevea T._DAu.&'-Au j i i i (6 u l l i ;J I L.m i 3 _m . gig.,, ,i w =., L
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PSIEG Research Corporation RESEARCH AND TESTING LABORATORY TEST DATA SHEET TEST ORCER NO. TEST PR OCEDUR E ID ENT. DATE OF TEST k~S"M( PERFORMED AT DESCRIPTION OF MATERI AL ?M OMt #
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r e maaneo eastavus=r co.. inc.. moarveur. u o7om isosi assasse. retax: isese: DATA SHEET Mark '.* Flow Meter CUSTOMER Public Service Electric & Gas Research Corp. 3g73 12/20/84 REFERENCE _, P.O.No. Pf06729' MODEL Mark V- -SJ SERIAL NO. 3733 h" 30795 MATERI ALS : Sensing Element 17-4 PH Seal Teflon Housing T304 s.S. Flange Target T303 S.s. LINE CONNECTIONS Threaded Pipe Hovising %" MNPT NATURAL FREQUENCY (in air) 137.0 Hz TARGET TYPEe ACR-604 VISCOSITY AT CALIBRATION 1.0 eps SPECIFIC GRAVITY 1.0 e FLOW RANGE
- 0. 2 - 2.0 Gallons / Minute FLUID Water REYNOLDS NO. (R ) RANGE. AT CALIBRATION 1,016 - 10,160 D
PRESSURE RATING 3000 psi Maximum Pressure Sensing Element { Element #39056 s Schedule 40 P i TEMPERATURE RANGE - 65 to + 300
- F BRIDGE RESISTANCE Input 351.2 ohms, Output 351.2 ohms.
(* FORCE FACTOR 0.895 mV/V/kg [ T Recommended 7h Maximum 15 Volts AC or DC VO E i FULL SCALE OUTPUT standard piping (see " Installation") 1.009 Millivolts / Volt Excitation at 2.0 GPM FULL SCALE OUTPUT: short straight run i Millivolts / Volt Dccitation at_ , with l straight run pipe diameters
- upstream, downstream f
ohms a~ cross Pins A - B (or 1 - 2) Calibration Resistor yields an output signa 1 of ',mV/V ~~~~ Accuracy h f, of full scale I ( ) fo' ce calibration, ( X) flow calibration Data based on: r F sn i ELECTRICAL CONNECTIONS: L t o g Terminals B or 2 --- Bridge Output (+) 5 A or 1 --- Bridge Excitatien (+) C or 3 --- Bridge Output (-) f, s D or 4 --- Bridge Excitation (-) E or 5 --- Case cround m Page No. 68 Test Report No. 17761-1 REV.A ' Target type number is its diameter Final // fff in, thousandths of an inch. Acceptance /1## 6 Cifd7 sa F w _ i_
g.. Paga No. 69 + .Ramapo In'Jtrumtnt Co., Inc. Test Report No. 17761-1, Rw. A DATA SHEET MARK X FLOWMETER SYSTEM CUSTOMER Public Service Electric & Cas Research Corporation DATE 4/11/85 FLOWMETER MODEL Mark X-00000I SERIAL NO. 16686 a DTA-8401RDIS 16688 ELECTRONICS-MODEL SERIAL NO. FLOWMETER DETAILS : Outline drawing 32076 MATERIAIS: Metering Tube & Float Type 18-8 S.S. Core 17-4 PH [ Housing T303-304 S.S. Seal Teflon Damper Teflon (Special) FLUID Wa ter SPECIFIC GRAVITY 1.00 6 FLOW RANGE 0.005 - 0.25 CPM METERING TUBE SIZE 253 x 3 p MAXIMUM PRESSURE 3500 Psig: TEMPERATURE RANGE - 65 to 250 op [ ? VISCOSITY: Operating 1.0 cps at calibration 1.0 eps y 7-FULL RANGE OUTPUT (Open Circuit) 256.856 mV/V at 3000 Hz(Approx.) j j' LVDT type K-220-002 ADDITIONAL FEATURES OR DATA: ( x) None, ( ) See next page { - For other details, see specification S 32110 ELECTRONIC DETAILS: Outline drawing 32738 System Wiring 33416-1 FUNCTION: (x ) Flow rate transmitter, ( x) Indicator, ( ) Totalizer, (.) Controller set point (s), contact rating 1q EXCITATION: 3.469 Volts, 3.033 KHz (g qb OUTPUT: Flow Rate-signa 1 4-to 20 mADC in+o IK ohm load ( X) max. DISPLAY:( ) Analog meter, (x) Digital meter. Scale 0-1.999 [T TOTALIZING: Full scale count rate counts per , equivalent .;J to per , with scale factor of j (Example reads .) N1-Counter ( ) included, ( ) remote, ( ) not supplied. 1 [] ( ) Batch Control, contact rating I Counter reset: ( ) none, ( ) manual, ( ) electric, ( ) remote } POWER: (x) 105-125V 50/60 Hz, ( ) 200-250V, 50/60 Hz, ( ) j, J ^ ENCLOSURE TYPE: Rack Mount ' l f,( - ' ADDITIONAL FEATURES OR DATA: ( X) None. ( ) See next page ~ i3; For other details, see s,pecification 533375 Set Set SCALE 1 CALIBRATION SIGNALS Switch position: CAL 1 CAL 2 FACTOR EITS y Simu.lates Flowmeter Signal 68.339 188.416 mV/V m CPM 0.050 0.1875 j; Equivalent Flow Rate 'h Count Rate (Totalizer) ~ ~ i Output Signa 1 7.2 16.0 mADC i J Meter Reading 0.400 1.500 CPM 0.188 Meter Reading (scaled) l- 'In all correspondence, refer to complete model designation and serial
- i number.
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r p o PSEG Research Corp <muhm RESEARCH AND TESTING LABORATORY N PRESSURE GAGE CALIBRATION DATA Performed for 95EJ(0-(? c 5 EARCw gcep .m,s r 6 i O. Location of Test Ps E.e c-- e,= se,4Rcw 0p9. m.6 on/ Test.No. Test Procedure Identification Er,:d (-
- gy 6 Test Date Thydf Description of Test Item n 2 m o me, M r,g Gage No. [ 5' C 7d 8 v Manufacturer mArdsecA)
Model ch S/.33 Accuracyzo.255. ;:5 Standard GAGE READING Pressure PSI l PSI Up Down Average Correction 1 o o O C o r PTO 2 70 250 2 70 0 L SCO TC S~ @ C~ .s~O 5~~ -f (L 7sO 7m 77s'~ 7 g z. - 7._ n, x /000 /CC'O /ccS~ lCO 2. - 2. r I *2 7*o 12 C*O l2TO l 2 70 0 IS*0 0 /SDO trco / SDC O / 74f"~ v[ QTC r 7W n m a.. i ,,.r,. .... / .0, C= f ~ i.- >.. n U... /.;. l j $ sa //.e,e, 4
- f' Permanent Set Test
Calibrated by M. j N8T Performed [* Reviewed by Not required t-Date C - 1. <*' - b*J, [ Test Standard / Equipment 4 itiSE. Bic-i Td L. 6A6 E C Ic'cCds, 7 .j ~ Serial No. 7706 b) i4 - 1 Date of Last Calibration ,o /79[15/ Page No. 70 t' Test Report No. 17761-1 {' /o d ?)9f' Date of Next Calibration REV.A L 461 10/84 j a A
J~ f PSEG Research Corporadon f RESEARCH AND TESTING LA80RATORY ) PRESSURE GAGE CALIBRATION DATA Performed for AT4f $5Sfd/'(/f 6df # A' r d ic) ) l Location of Test Mr6-f-TMt/ ccRP Sc/j Alt /. Test No, i f - Test Procedure Identification _ _ F</d -6,
- E5/. 6 Test Date
.5~~//9./8f I Description of Test Item 0-3000 mc 6~M E Gage' No. [ @ C 7 3 iJ i! q Manufacturer rit,erksfca) Model /.I:J-STJ3 Accuracyn. in ;f. li Standard GAGE READING Pressure 4 PSI p PSI Up Down Average Correction _ I l }' t c n o c O l 2co > cc zw 7ro O i g reo reo reo coo O r, 7sD 770 770 rs o C La /0C0 /C00 /CC0 /CC0 D .) ~ / ysv / 24S~~ /7 s O i2'IE + 2. O i /St%) /CCO / rc6 /WG O .. [7 fG /73~0 / ~?TO / 7S~~0 C i.~1 ,J t 1 S a iTO.k., r ,1,n e.w e ,s- ., /. d4 C L W r.e h
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,a = q Permanent Set Test: Calibrated by I* j W T Performed . Reviewed by ) Not required y/ f1 Date _ l'~ ~ ~1 J - T f lu Test Standard / Equipment ti, iscs b/.n rT L < -ge e_ 6 o-rctOp Serial No.
- 77a, i
l Date of Last Calibration /0/2 gy Page No. 71 Date of Next Calibration /Oki/SI Test Report No. 17761-1 REY.A I. M 1 W 84 J .}}