ML19294A677
| ML19294A677 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 02/22/1979 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903080157 | |
| Download: ML19294A677 (30) | |
Text
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hEETING SUhMARY FEB 2 2 1979 Ibcket File iV c:
NRR Reading thR #4 File E. Case D. Bunch R. Boyd D. Ross D. Vassallo W. Camill J. Stolz R. Baer O. Parr S. Varga C. IIeltemes L. Crocker D. Cnitchfield F. Williams R. hhttson R. DeYoung Project Manager: D. flood Attorney, ELD M. Service ACRS (16)
R. Denise L. Rubenstein NRC
Participants:
S. Salah J. hhzetis S. Newberry L. Kopp
- 11. Richings L. Porse P. hhtthews V. Benaroya R. Kirkwood W. LeFave D. Pickett B. Cox
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UNITED STATES
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b NUCLEAR REGULATOHY COMMISSION 3 ' ' D.
h WASHINGTON, D. C. 20555 r
FEB 2 21979 k.....,/
Docket Nos:
50-329 50-330 APPLICANT: Consumers Power Company FACIL,Tz:
Midland Plant, Units 1 and 2
SUBJECT:
SGt!ARY OF b'ELTING ON MIDLAND PL\\NT, UNITS 1 AND 2 CONCERNING CASK DROP, CONTAIN51ENT SGIP 50 DEL TESTS, AND SITU \\M LINE BREAK ANALYTICAL TECHNIQUES On Jaruary 16, 1978, the NRC staff met in Bethesda, Maryland with members of Consumers Power Company (CPCO), Bechtel Associates, Babcock 6 Wilcox Company, Western Canada flydraulic Laboratories Ltd.,
and Ederer Incorporated. Attendees are listed in Enclosure 1.
Hand-outs and viewgraphs used during the meeting are shown as Enclosure 2.
The meeting agenda included three items relative to the NRC staff's safety review of Midland Plant Units 1 and 2:
1.
Revised Steam Line Break Analytical Codes and Analysis By several related requests for additional information (i.e., 222.1, 211.166, 211.168, 211.169 and 211.171), the NRC staff had informed CPC0 that, to be acceptable, the analyses for a postulated main steam line rupture accident must be revised to consider tne effects of an assumed stuck control rod assembly on the power distributions.
CPC0 stated that these revised analyses would require the development and application of a new computer code, BWKIN, by Babcock 6 Wilcox.
BWKIN will be a multi-dimensional core kinetics code with neutronic and thennal-hydraulic coupling, similar to the MEKIN code developed by Massachusetts Institute of Technology and Battelle Laboratories.
Like COBRA, the BWKIN model will permit cross flow between fuel channels. The BWKIN code will utilize the PDQ code for steady-state initial conditions and scoping studies of BWKIN-PDQ viill be performed. Transient analyses with the BWKIN code will utilize the TRAP-2 and RADAR codes.
B6N stated that the revised steam line break analyses for Midland are not expected to result in DNB, even during return to power, and that at worst, if DNB should occur, it will be brief and of limited extent such that no DNB propagation would occur. B6W's statement is based upon studies performed on a similar plant, Three blile Island Unit 3.
The worst case for Midland would occur for a full break opening during beginning of life (BOL) conditions when the core is at full power. During BOL, the highest power
i FEB 2 21979 peaking during steady state conditions occurs at the stuck rod location. The stuck rod has its maximum worth at BOL. At end of life conditions, the highest peak does not correspond to the stuck rod location, but its magnitude is much lower than a BOL peak.
The applicants schedule is based upon a start date of February 1, 1979. Steady-state analyses with BhKIN and PDQ will have been performed by June 1, 1979. The transient and DNER computations will have been performed by October 15, 1979 and documentation of analyses results till be submitted to the NRC st
~f by the end of 1979. The description of the BhTIN code will be included as an appendix to a BSW topical report on rod ejection analyses to be submitted in early 1980.
The staff suggested that a further meeting on this effort would be appropriate about June 1,1979.
2.
Spent Fuel Cask Crane In response to several staff requests for additional information (i.e., 010.10, 010.22, 010.46, 010.57) in which the staff required that the spent fuel cask be prevented from dropping and tipping into the spent fuel pool, CP00 replied that a single-failure proof main hoisting mechanism is being incorporated into the auxiliary building crane. The design is based upon a topical report submitted by Ederer, Incorporated on January 15, 1979. The topical report EDR-1 is entitled "Ederer's Nuclear Safety Related Extra-Safety and Monitoring (X-SAM) Cranes." The report discusses conTormance of tEc design to regulatory guide 1.104 and involves exceptions to the guides positions relative to single hcoks and fa-tor of safety on the wire rope. CPCO stated that related information relative to other Midland specific design parameters will be further addressed by FSAR amendment in April, 1979. CPC0 also stated that the fuel pool area crash pads and spent fuel cask transfer carriage in the existing design will be deleted because these components are no longer needed with the revised design.
3.
Containment Sump Model Tests CP00 advised that hydraulic model studies will be perfonned with a full scale model of the Midland containment sump design in order to assess vortex formation and to determine the trashrack and intake losses. The tests are described in the attached proposal by Western Canada Ilydraulic Laboratories, Ltd.
^
, CPCO plans to start the physical setup for the tests about thrch 1, 1979. Actual testing would be conducted throughout May 1979 and a full report is planned in July 1979. The applicant's consultant stated that turning vanes have been successfully demonstrated by tests for previous plants and in their opinion, need not be r peated on Midland; if turning vanes are included, this would add about two weeks to the schedule.
CPCO requested NRC staff coments on the attached test proposal.
The staff will comment by mid-February 1979.
- j ai//c m Darl S. Hood, oject Manager Light Water Reactors Branch No. 4 Division of Project Management
Enclosures:
1.
Attendees List 2.
Handouts and Viewgraphs
Consumers Power Company Ccs:
Michael I. Miller, Esq.
Mr. S. H. Howell Isham, Lincoln & Beale Vice President Suite 4200 Consumers Power Company One First National Plaza 212 West Michigan Avenue Chicago, Illinois 60670 Jackson, buchigan 49201 Judd L. Bacon, Esq.
Consumers Power Canpany 212 West Michigan Avenue Jackson, Michigan 49201 Mr. Paul A. Perry Secretary Consumers Power Company 212 W. Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esq.
One IBM Plaza Chicago, Illinois 60611 Mary Sinclair 5711 Summerset Drive Midland, Michigan 48640 Frank J. Kelley, Esq.
Attorney General State of Michigan Environmental Protection Division 720 Law Building Lansing, Michigan 48913 Mr. Wendell Marshall Route 10 Midland, Michigan 48640 Grant J. Merritt, Esq.
Thompson, Nielsen, Klaverkamp & James 4444 IDS Center 80 South Eighth Street Minneapolis, Minnesota 55402
e e
Attendees January 16, 1978 D. Ilood DPM R. Vosburgh B6W M. Sakrno CPOO G. Ilanson B6W J. Iloward B6W R. Reed B6W S. Salah NRC S. Bian B6W J. Zabritski CPC0 J. Mazetis NRC S. Newberry NRC L. Kopp NRC
- 11. Richings hRC R. Ilo11ocon EDERER L. Porse NRC P. Matthews NRC V. Benaroya hRC R. Kirkwood NRC W. LeFave NPC D. Pickett h7C B. Cox NRC D. Ilo11ingshead Bech+21 M. Rothwell Bechtel D. Ilay Kieiter Canada Hydraulic Labs R. Elder Bechte.
M. Pratt Bechtel
STEAM LINE BREAK WITil TRAllSIEili PEAKillG INTRODUCTI0il AND BACKGF0VND GEhERAL ANALYTICAL APPROACil BWKlii CODE DESCRIPTIO;l AtiALYSIS
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PATTERN, FEEDBACK CORRELATIONS THERMAL-HYDRAULIC INPUT -
o COOLANT PARAMETERS - INLET FLOW, INLET o
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CLAD PROPERTIES, GAP HEAT TRANSFER COEFFICIENT T
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NORMLIZATION OF BWKIN TO PDQ
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SLB 51ULK R0D PROGRAM OBJECTIVES
-- STUDY TRANSIENT PEAK ASSOCIATED WITH MAXIMUM WORTH STUCK ROD'DURING TRIP.
-- CONFIRM NO PROPAGATION IN THE LIMITED NUMBER OF PINS ~
IN DNB DURING TRIP.
-- PROVIDE ANSWER TO flRC QUESTIONS 211.166, 211.163, 211.169, AND 211.ll1.
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NRC Rd2 QUESTIONS DEC '78 SER MAY '78
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MEETING AGENDA CONSUMERS POWER COMPANY MIDLAND PLANT UNITS 1 AND 2 JOB 7220 AUXILIARY BUILDING CRANE NRC OFFICES, BETHESDA, MARYLAND Jcnuary 16, 1979 11:00 A.M.
ATTENDEES:
NRC, CPCo, Bechtel, and Ederer Responsibility I. Introduction J. Zabritski (CPCo)
A.
Statement of Meeting Purpose B.
Review of NRC Questions C.
Design Intentions Regarding Cask Dolly and Crash Pads II. Ederer's X-SAM System W. Holloran (90lloran Assoc.)
III. Specifics of the Midland Retrofit W. Clark (Ederer)
IV. Summary V. Questions VI. Review of Action Items 12/16/1
MEETING AGENDA CONSU}ERS POWER COMPANY MIDLAND PLANT UNITS 1 AND 2 JOB 7220 CONTAINMENT SUMP TESTING NRC OFFICES, BETilESDA, MARYLAND Janunry 16, 1979 1:00 P.M.
ATTENDEES:
NRC, CPCo, Bechtel, WCHL Responsibility I. Introduction J. Zabritski (CPCo)
II. Statement of Mooting Purpose J. Zabritski III. Review of Midland Design M. Pratt (Bechtel)
A.
Sump design and layout B.
System flourates IV. Discussion of Test Program R. Elder (Bechtol)
A.
Overview B.
Previous testing C.
Test procedures 1)
Series A tests 2)
Series B tests 3)
Series C tests D.
Testing QA program D. Ilay (WCllL)
E.
Test documentation and reporting D. Ilay V. Analysis of Losses from Sump to Pumps M. Pratt VI. Summary VII. Questions VIII. Review of Action Items 12/15/4
t t
i A brief summary of conclusions to date from tests on the ECCS containment sumps f or J.M. Farley units 1 and 2, A.W. Vogtle, and Davis Besse and San Onofre Nuclear Plants.
1.
Eddies and verticity shed f rom structural members, valves, restraints, etc. are very weak in approach flows of 1 fps or less.
veloc.ities of less than 1 fps, the trash rack bars on the 2.
Atscreen cages covering the cumps removed angu'.ority and/or circ-ulation in the flow as it passed through the trash rscks.
Flow from the trash rack normal to the plane of the grt. ting.
exits 3.
A single layer of 1-1/4 in, by 3/16 in, flat har grating with a spacing of 1-3/16 in. t otally eliminated large free surface vortices which were force. t o develop by tnrning vanes over an unprotected demonst rat est f or both vert ical and horizont al int ake.
This wnn intakes of 10 to 24 in. diameter and for intake flows of up t o 8600 gpm.
4.
The single layer of grating was effective in eliminating vortices which otherwise would have had air core diameters ranging f rom 1/16 in, to approximately 2 in.
5.
The most potentially adverse flow conditions at the lutakes were established by blockage on the trash rack screens.
Vortices formed within the trash rack screen cage could be totally 6.
eliminated by a grating cage over the intake.
7.
Grating acts as a flow straightener and eliminates the circulation necessary tc support a vortex core.
H.
Intake loss coef f t elent a wit h a grating cage in place were as fallows:
For the ANO-2 and SONGS plants:
ANO-2 SONGS
- 1.01 to 1.25 1.42 to 1.55
- includes loss in 2 elbows
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TABLE 1 DIMENSIONS AND OPERATING VARI ABLES OF T11REE PLANT INTAKES INTAKE ARKANSAS NUCLEAR SAN ONOFRE MIDLAND ONE UNIT NUCLEAR STN NUCLEAR PLANT UNITS 263 UNITS 162 SIZE 24 in, diam 24 in. diam 24 in. diam 3325 gpm 3900 gpm 4450 gpm 1 RGE e.34 <<
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@ 1-3/16" cc RANGE OF 0.13-0.50 fps 0.06 0.23 fps 0.35-0.50 rps LOC TIES TO SUMP MAXIMUM SUMP WATER 210*F 190*F 227'F TEMPERATURE
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Flow circulation, angularity and eddies generated by the "far 1.
l field",will be eliminated by the trash rack bars.
The trash i
rack is the model boundary.
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Flow conditions without blockage due to the geometry outside the l
2.
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be developed by blockage.
The two sumps are geometrically similar, subject to the same flow 3.
rates and depths of submergence therefore only a single sump need be modelled.
The effectiveness of a trash rack and/or a grating cage of similar 4.
to similar flow rates, in precluding free surf ace I
size, and subject vortices has been documented for other plants (J.M. Farley, Vogtle, ANO, SONGS). Therefore tests with and without the trash rack in place in which a free surf ace vortex is forced to develop without the trash rack are not necessary, t
Tae potentially most adverse conditions for the intake are generated 5.
aithin the trash rack by blockage conditions. Tests will be i
conducted to show that a grating cage over the intake effectively precludes vortices from developing within the trash rack.
Intake loss coefficients and vortex formation are a function of 6.
The model will be constructed at a scale of 1:1 Reynolds number.
and tests will be run at prototype Reynolds numbers equal to or greater than prototype values to give accurate results and minimize j
scale effects.
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6 CONSUMERS POWER COMPANY f'
(
MIDLAND PLANT UNITS 1 AND 2 l'
t PROPOSAL FOR CONTAINMENT SUMP TESTING SUBMITTED TO BECHTEL POWER CORPORATION
[
IF L.
r-BY 6-WESTERN CANADA IIYDRAULIC LABORATORIES LTD.
i.
PORT C0QUITLAM, B.C.
be OCTOBER, 1978 pa M
l e
TABLE OF CONTENTS Page 1.
SUMMARY
1 2.
INTRODUCTION 2
2.1 Purpose 2
2.2 Intake Description 3
3.
Tile MODEL 5
3.1 Rationale of Study 5
3.2 Model Description 6
4.
TEST PROGRAM 8
5.
REPORTING 10 6.
ESTEMATED TIME AND COSTS (DELETED) 11 7.
PERSONNEL 14 i
l TABLE I 15 FIGURES 17 APPENDIX A - Quality Assurance Requirements For Physical Model Studies APPENDIX B - Personal Resumes
9 4
i9 4
LIST OF FIGURES 1.
PLAN OF PROPOSED TEST FACILITY 2.
SECTION OF TEST FACILITY 3.
CONFIGURATION FOR TRASIIRACK BLOCKAGE TESTS 9
e G
4 e
4 w
e-l 1.
SUMMARY
l' I
Hydraulic model studies are proposed at a 1:1 scale to assess vortex formation and to determine the trashrack and intake ossec l
associated with the Midland Nuclear Generating Station Emergency Core Cooling System intakes following a LOCA.
The study will be undertaken in a 60 ft long by 25 ft wide by 12 ft deep concrete tank using water heated to 180 F.
The model will consist of trashrack and screen cage and will reproduce all structo-al shapes, piping and ancillary equipment located inside the trashrack r-boundaries. The 24 in dia. Intake will be modelled using fibreglass pipe. Viewing windows in the tank will permit visual observation and video recording of flow phenomena in the sump.
Testing will be conducted at the minimum postulated operating u
water level with an augmented discharge of 7800 USgpm which will produce prototype Reynolds numbers in the model.
Tests will document that positive vortex control is incorporated in the sump design by encapsulating the intakes with a grating cage.
Intake loss coeffic-ient.s will be determined and the accuracy of measurement established.
The model will be constructed and tested and a report issued within 4 months of receiving notice to proceed. The study is estimated to cost DELETEp.
I
Page 2 MIDLAND PLANT UNITS 1 AND 2 PROPOSAL FOR TESTING CONTAINMENT SUMP 2.
INTRODUCTION This proposal for hydraulic model studies of the ECCS intake sump for Midland Plant Units 1 and 2 is based on data contained in a Bechtel Memorandum of June 20, 1978 and on the following Bechtel drawings number:
7220 - C - 332(Q)-6 7220 - C - 623(Q)-6
- C - 335(Q)-9
- C - 624(Q)-10
- C - 354(Q)-7
- C - 630(Q)-3
- C - 355(Q)-7
- C - 637(Q)-9
- C - 371(Q)-10
- C - 646(Q)-5 I
- C - 372(Q)-8
- C - 651(Q)-9
- C - 381(Q)-6 610 Sil3 (Q)-2
- C - 462(Q)-2 612 SH3(Q)-7
- C - 463 (Q)-2
- M - 179(Q)-2
- C - 491(Q)-1
- M - 300(Q)-1
- C - 495(Q)-1
- M - 301(Q)-3
- C - 496(Q)-1
- M - 302(Q)-3 2.1 1urpose The purpose of the model studies is to investigate possible vortex formation at the ECCS intakes and to assess head losses through the trashrack and screen cages and through the intake. Vo rt ic es,
Page 3 a
if they were to occur, could cause unexpectedly high intake losses, m
loss of pump capacity due to air entrainment and pump failure due to vibration.
High intake losses may impair the ability of the spray or LPI pumps to draw a suction on the sump, or the ability of the llPI I
pumps to take a suction from the LPI pump discharge.
2.2 Intake Description The ECCS pumps will be supplied by two 24 in. diameter intake pipes which protrude horizontally into sumps at centerline el 589.50 k
ft.
Each intake pipe will draw from a 10,0 ft long by 6.5 ft wide by 5.85 ft deep sump which is formed by dividing a 13 ft long by 10 ft wide pit across its width. The sump floor is at el 587.92 ft.
The dividing wall extends upwards to the top cover plate and across the full width within the trashrack. The entire trashrack enclosure will be covered by a flat cover plate. The elevation of this cover P
plate is to be confirmed by Bechtel.
The trashracks are formed of 3-1/2 in, by 3/8 in. vertical bars spaced at 1-3/8 in. centers with crossbars spaced at 2 in.
A medium screen of 3/8 in. square opening and a fine screen with 0.04 in.
^
~
openings will be inside the trashracks. A flat floor area between F
1.75 ft and 5.75 ft wide surrounds the sump inside the trashrack.
m The expected normal operating discharge per intake is 4450 USgpm r
with a possible maximum of 6000 USgpm at runout conditions. Total u
flow t hrough bot h int aker, may reach 12000 USnpm during simultaneous runout conditions.
The anticipated post LOCA water temperature may P
reach 227 F.
The minimum postulated post LOCA water lavel in the F
w
Page 4 sumps is 596.0 f t with a possible maxicium water level of 602.8 f t.
e I
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Page 5 3.
Tile MODEL 3.1 Rationale of Study
,It has been found in previous studies for the Davis Besse Nuclear Generating Station that the vortex formation process cannot be reliably modelled at scales below 1:1. A 1:1 scale using water heated to a maximum of 180 F is proposed for this study.
Tests on similar ECCS sumps indicated that the trashracks acted as flow straighteners for the range of approach velocities postulated for each plant during post LOCA conditions.
The flow straightening ability of the grating effectively " uncoupled" flow conditions within the sump f rom the ef fect of the containment geometry, structural members and piping external to the,trashrack.
It was shown that screen blockage was predominant in establishing flow conditions within the sump.
The trashrack size and range of approach velocities for three other plants tested are compared below to the Midland Plant.
Trashrack Bar Size Range of Approach Plant And Spacing Velocities, fps J.M.
Farley - Unit 2 1-1/4" x 3/16" 0 1-3/16"cc 0.14 - 0.53 Arkansas Nuclear One -
1-1/4" x 3/16" @ 1-3/16"cc 0.13 - 0.50 San Onofre Cencrating 2-1/4" x 3/16" x 1-3/16"cc 0.06 - 0.23 Station Midland - Units 1 & 2 2-1/4" x 3/16" @ 1-3/16"cc Approx,0.35 - 0.50 It can be seen from the above that the depth to spacing width of the Midland trashrack bars is equal to or greater than the other plants
1 Page 6 tested while approach velocities are similar.
The Midland trashrack will be an effective flow straightener and therefore an adequate model boundary.
The main sump of the Midland plants is divided into two geometri-cally similar sumps, one for each train. The main sump features with respect to vortex potential and intake lossas, such as intake diameters, flow rates, depth of submergence, and overall geometry are similar for the two sumps.
There are two minor dissimilarities.
The trashrack clearance from the edge of the sump is 1.0 ft less on one side of the sump than on the other and the alignment azimuth of one intake leads directly from the sump whereas the second intake makes a 15 bend as it passes through the sump wall. Neither of these differences is significant relative to vortex potential or intake losses when compared to the predominant influence of screen blockage.
It is proposed that only one sump be modelled and tested.
The test results will be applicable to both sumps in both Units 1 and 2.
Modelling and testing one of two geometrically similar sumps was undertaken by W.,C.H.L. for the ANO-2 and S0.NGS. plants.
The tests would be conducted en the minimum postulated water level since this produces the maximum velocities through the screen, the lowest ambient pressure in the intake, and thus the greatest potential for vortices to develop.
3.2 Model Description A 10.0 ft long by 6.5 ft wide by 5.85 ft d2cp sump will be constructed in a 60 f t long by 25 ft wide by 12 ft deep concrete
Page 7 tank, Figure 1 and 2.
The sump will be an exact 1:1 scale model of the North sump of Unit I and South sump of Unit 2.
A 24 in diameter fibreglass intake pipe will enter the sump horizontally at centre 31ne el 589.50 f t.
The pipe will be carried straight and level for a distance of 18 pipe diameters beyond the intake before a bend is introduced Icading the pipe to an exit port through the tank wall.
The 30 in. diameter shroud will cover the 24 in. diameter intake within the sump.
The solid divider wall will be constructed along one side of the sump and extending the full length of the trashrack enclosure to a top el 597.00 ft.
The trashrack and screen cage will be constructed to top el 597.00 ft around the sump.
All auxilliary equipment or structures inside the trashrack enclosure, such as columns and water level recorders, will be modelled to el 599.00.
All proposed testing vill be carried out at the minimum postu-lated water level.
The top of the trashrack cage will be lef t open unless it is divided to construct a cover plate below the minimum water levels.
An observation tunnel with viewing ports will be constructed to permit viewing for vortex formation around the intake.
6 The water in the tank will be heated using two 2.5 x 10 BTU /hr gas heaters.
Flow through the intake will be recirculated to diffusers at eac h end of the tank using a 7511P pump.
Piczometer taps will be installed in the floor inside and outside of the trashrack cage and in the 24 in. diameter pipe.
Page 8 4.
TEST PROGRAM The main test program to examine flow conditions at the intake and to determine head loss coef ficients across the trashrack and grating cage will be carried out in three test series, Series A, B and C, Table 1.
Test Series A and B will examine flow conditions at the intake entrance and determine loss coefficients with a water temperature of 180 F and discharges augmented above prototype flows to proe' ace Reynolds numbers equivalent to those occurring in prototype.
Test Series A will examine the intake without blockage, both with and without the grating cage in place and with five rationally determined 50% trashrack blockage conditions, Figure 3.
Test Series B will demonstrate the effectiveness of the grating cage to suppress internal vortices which will be generated using experimentally determined conditions of 50% or greater trashrack blockage. Tests will be run at a model discharge of 7800 USgpm, developing Reynolds numbers equivalent to prototype operation at 6000 USgpm and 227 F temperature, and at the maximum model discharge to test the conservatism of the design. Tests will be run at plant mininum water 1cvel.
It is our experience that the formation of a wall or floor vortex is not solely a fune. ion of percent blockage but also a function of where blockage occurs.
This is a central weakness in all non-generic solutions, as one cannot be sure that all possible blockage s. nfigura-tions have been tested. The purpose of Series B tests is to force the 9
Page 9 formation of a wall or floor vortex, without the grating cage in place, and to demon.etrate that the grating cage over the intake pipe will preclude the formation of such vortices.
The test sequence in this phase will be as follows:
1.
The grating cage will be removed and blockage conditions established which produce a wall or Iloor vortex entering the intake with an air core.
The blockage will be equal to or greater than 50 p-l cent of the screen area.
2.
The gratins -age 21 1 be reinstalled for the blockage condition above and the effect of the cage on the vortex will be noted.
3.
The discharge in the model will be increased to demonstrate the conservatism of the grating cage design with respect to vortex prevention.
Test Series C will consist of 20 tests with 50 perc'ent blockage to determine a mean value of the intale loss coefficient and to establish confidence limits.
The following parameters will be recorded during the test program:
1.
Flow rate 2.
Water Temperature 3.
Intake elements in place, that is, screen and/or grating cages 4.
Piezometric levels 5.
A written description of flow conditions The intake loss coefficient will be calculated from the plazometric levels for each test.
Photographs and/or video tape records will be taken where feasible.
Page 10 5._
REPORTING A tablulated test program, together with a detailed sketch of the test arrangement, will be forwarded for approval prior to commencing construction and testing.
The study will be undertaken following the Q/A program of Western Canada Hydraulics Laboratory, Appendix A.
Bi-monthly status reports will be forwarded after commencement of construction.
A short form report will be prepared within two weeks of completing the test program.
This will be prepared to facilitate SCE's submission to NRC.
A final report will be prepared covering the purpose, program, procedures, results and conclusions of the study.
The report will include the test data, and results of previous experience, and i
positive conclusions drawn with respect to the adequacy of the sump de.'ign in preventing the formation of air-entraining vortices.
A draft of the final report will be submitted for approval.
O
6.
ESTIMATED TIME AND COSTS This section deleted Pages 11,12 and 13 removed
(
Page 14 7.
PERSONNEL
/11 proposed work will be reviewed and approved by Mr. D. Hay, Managing Director of Western Canada Hydraulic Laboratories Ltd.
The studies will be carried out under the direction of Mr. W.A.
McLaren, P. Eng., Head of the Laboratories' Special Projects section.
The project engineer will be Mr. W. Schriek, P. Eng.
Biographical resumes of these staff members are presented in Appendix B.
Support-ing staff consisting of engineers, technicians and skilled tradesmen will be available from W.C.H.L. staff as required.
Close liaison will be maintained during the program with Bechtel engineers.
W.C.H.L. encourages the participation of Client personnel in studies at the Laboratory and is prepared to make available a limited amount of office space, if required.
_ TABLE I PROPOSED TEST PROGRAM Series A - Primary Objectives: For the unblocked trashrack and five rationally selected blockage conditions determine trashrack and intake loss coefficients and demonstrate that no vortices occur.
Determine the effect of the grating cage on the intake loss coefficient.
Test Discharges Water Level Temperature Blockage Number USgpm Elevation, ft o
Condition Grating Cage In Place p
(Figure 3)
A1 7800 596.0 180 None No A2 7800 596.0 180 --
Ncne Yes A3 7800 596.0 180 A
Yes A4 7800 596.0 180 3
Yes A5 7800 596.0 180 C
Yes A6 7800 596.0 180 D
Yes A7 7800 596.0 180 E
Yes Series B - Primary Objective: To demonstrate the effectiveness of the grating cage to suppress vortices.
Procedure:
- 1. Without the grating cage ir -1.ce ex,*rimentally determine blockage conditions that generate vortices from either the sump aalls, floor or ceiling.
- 2. For selected blockage conditions frem (1), conduct the test !;equence described below.
Tests conducted at an intake discharge greater than the design discharge demonstrate the conservatism of the design.
Test Discharges Water Level Temperature Blockage Number USgpm Elevation, ft o
Condition Grating Cage In Place g
B1 7800 596.0 180 No B2 7800 596.0 180 Yes B3 Max 596.0 18G Yes
TABLE 1 (cont)
Series C - Primary Objective :
Repeat a 50 percent blockage test to show test results r'productibility, e
and subsequently determine the mean loss coefficients, standard deviation and confidence limits.
Test Discharges Water Level Terggrature Blockage G
e h Place Number USgpm Elevation, ft F
Condition Cl to C20 7800 596.0 180 A
Yes 9
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24"O INTAKE LABORATORY FLOOR SECTION A-A (SCALE I" : 4')
3 o
C 21 NOTE Model section from Figure 1.
N SECTION OF TEST FACILITY WESTERN CANADA HYDRAULIC LABORATORIES LTD.
Wie638 A-WCH
FIGURE 3
I l
t A-DEBRIS UNIFORMLY DISTRIBUTED.
I l
TRASH RACK BLOCKED 50% OVER FULL HEIGHT BY ALT E R N ATE l' -)
3* WIDE OPEN AND BLOCKED STRIPS.
t' r i
L_. __ _ _ _ _. _ _J 0- TOP HALF BLOCKED BY FLOATING DEBRIS.
TRASH RACK BLOCKED OVER UPPER s'
ONE HALF AROUND PERIPHERY.
s.s }
s
' s y' s
C - LOWE R HALF BLOCKED BY SUBMERGED DEBRIS.
N TRASH RACK BLOCKED OVER LOWER s
ONE HALF AROUND PERIPHERY.
'-,,'h
yf t
D-UPSTREAM H ALF BLOCKED BY DEBRIS.
t TRASH RACK BLOCKED OVER FULL HEIGHT
- s OVER 50'/o OF ITS AREA IN THE FLOW PATH.
,. ',, ~
'h
' ~~ NI I
i E-UPSTREAM HALF BLOCKED BY DEBRIS.
TR ASH RACK BLOCKED OVER FULL HEIGHT.
OVER 50 /o OF ITS ARE A IN THE FLOW PATH.
N-s' 8
i unnemmus INDICATES SOLID WALLS IND! CATES TRASH RACK BLOCKAGE CON FIG U R ATION FOR TRASH RACK BLOCKAGE TESTS WESTERN CANADA HYDRAULIC LABORATORIES LTD.
SCll 3681A-WCM
O S
9 APPENDIX A QUALITY ASSURANCE REQUIRDIENTS FOR PilYSICAL MODEL STUDIES I
l
1.
PROJECT ORCANIZATION All laboratory projects are under the direction of the Fianaging Director.
Ea ch project is assigned a Project Engineer and Project Technician.
Additional short term technical staf f for design, con-struction and/or testing is drawn from the technical pool or other projects.
The functions of project personnel aie, but not necessarily limited to, the following:
lbnaging Director Approves model designs and modifications prior to forwarding for the Client's approval.
Approves test programs prior to forwarding for Client approval.
Approves test procedures.
Reviews data gollection techniques, records, and data analysis to confire checks ha'e been made, adequate records taken, and test results and analysis are consistent with test procedures and objectives.
Reviews and approves interim and final reports.
Project Engineer Provides day to day supervision of model construction, testing and data analysis.
Checks conformance of model construction and modifications to approved drawings.
Initiates test program and procedura for approvals.
Initiates modifications for approval.
Undertakes and/or supervises testa.
Reduces and/or supervises reduction of test data.
Arranges for independent checks on data collected, data reductions and design calculations.
Supervises instrumentation calibration and checks.
Prepares report drafts.
Testing Technician Provides day-to-day technical support to the Project Engineer.
Operates the model under the direct supervision of the Proj ect Engineer.
Maintains equipment, instrumentation and photographic records.
Project Records are kept in:
a.
Correspondence files.
Incoming correspondence is dated and routed for initialling. All attachments or enclosures remain in the correspondence files except photographs and plans.
b.
Plan files.
Incoming Plans are dated the day received. A list of plan numbers is kept in the project work books.
Plans are filed in a drawer.
c.
Work Books.
Three ring binders are used for keeping test procedures, schedules, plan lists, design calculations, data, data analysis and draft reports.
All files, work books and plans are bound together upon completion of the project and placed in storage for at least 15 years.
2.
DESIGN AND CONSTRUCTION OF Tile MODEL AND MODIFICATIONS Design work is initiated by the Project Engineer and approved by thd Managing Director.
Model construction is supervised by the Project Engineer. Model dimensions will be checked independently of the person responsibic for construction.
The principal checker will be the Project Engineer.
3.
TESTING Test program will be initiated by the Project Engineer, approved by the Managin: Director and forwarded to the client for approval.
The test program will identify the objective of each phase and/or series of tests and identify each test with a number.
If as a result of test results, or other information, modifications are considered necesrary to the model or test program, a revised test program will be forwarded for approval.
Test procedure for the operation of the model will be initiated by the Project Engineer and approved by the Managing Director.
Revisions to the test procedure will be approved
/ the Managing Director.
Flov measuring orifice plates and weirs will be calibrated prior to commencing the test program and a dated record kept in the work books. The calibration would be checked should the testing exceed 6 months.
Other instruments, as required, will be calibrated and adjusted if necessary, prior to use, under supervision of the Project Engineer.
Data collection will be under supervision of the Project Engineer.
Data will be recorded on data sheets which will note the project number, run number, data, test flows, and items measured.
Periodic checks on obtained data will be made by an independent observer, that is, data
- aken by the Project Technician will be checked by the Project Engineer,
and vice versa.
Cencrally, data will be reduced as generated to examine trends
and consistency of results.
A photographic log will be kept noting photo number, test number and date of exposure.
Prints and negatives are kept in work books.
s.
4.
REPORTS A draf t of the final report will be prepared by the Project Engineer and reviewed by the Managing Director.
Following any necessary revision, a copy of the report draft may,be sent to the client for further comment prior to printing if so required.
Transferral of data from work books, or calculation sheets, to graphs and drawings will be checked by the Project Engineer.
Reports will be approved and signed by the Managing Director.
O O
9 S
APPENDIX B PERSONAL RESUMES D. HAY i
l A. McLAREN W.
SCHRIEK
DUNCAN HAY MANAGING DIRECTOR, WESTERN CANADA HYDRAULIC LABORATORIES LTD.
EDUCATION B.A.Sc. (Civil), University of British Columbia, 1964 M.S. (Hydraulics), University of California, Berkeley, 1967 Dip.
H.E., Delft Technological University, Delft, 1968 REGISTRATION Professional Engineer in Province of British Columbia MEMBERSHIPS Associate Member, American Society of Civil Engineers Member, Permanent Association of International Congresses Member, International Association for Hydraulic Research EXPERIENCE 1970 - date Western Canada Hydraulic Laboratories Ltd..
Vancouver, B.C.
Director Managed and provided technical direction for the following studies Hydraulic Structures
- Approach Conditions to Howell-Bunger Valve, Soroako; Marsh Lake Dam; Columbia River, Mica and Revelstoke Projects : Peace River, Site 1 Development; Pend-d'Oreille River; Seven Mile Proj ect; Churchill River, Missi Falls and Notigi Control Structures; Nelson River, Upper Limestone Site Integrated Powerplant and Conventional Powerplant; Beaver Creek Spillway, Alberta; Skins Lake Spillway; Ain Zada Spillway Algeria; Fermatou Howell-Bunger Valve Outlet Structure, Algeria; Coastal and Harbour Model Studies
- Flushing in Small Craft Harbours; Cape Tormentine Ferry Terminal; Point Grey Erosion; Delta Stabilization; Silver Bay, Lake Superior; Wind and Wave Studies, Beaufort Sea; French Creek
\\ Boat Harbour; Deas Slough Marina; Oak Bay Harbour; Royal Victoria Yacht Club; Pacific Environment Ins titute, Quanicassee Nuclear Powerplant; Fraser Survey Docks Extension, Floating Breakwaters; Chemainus Harbour; Gabriola Island Ferry Terminal; Oyster River Estuary; Jericho Beach; Coburg Peninsula; Landslide Genera-ted Waves, Kitimat Inlet; Cooling Water Intake Structure; Pilgrim Nuclear Plant:
River Studies
- Thompson River Erosion, Fitzsimmons Creek Flood Levels; Fraser River, Steveston Harbour,
a River Studies (contd.)
Trifurcation Phase III; Infill, Bristol Island; r-Borrow Pit Migration, Fraser and Pitt Rivers;
['
Vedder River Sedimentation:
Special Studies
- Drop Structures, Poplar Creek; Emergency Cooling Pump Intakes, Nuclear Plants; LNG Pumping Station, Algeria; Flow Circulation Fish Holding Tanks, Beaver Creek Diversion; Island Copper Outfall, Anaconda Britannia Mines Outfall; Kitsault Outfall; Sundance Cooling Pond and Discharge Structure; Port Hardy Breakwater; Libby Dam Releases; Fish Pumps; Oilwater separators; Belle River Nuclear Plant Intake and Diffuser Design, Michigan; Pilgrim f.
Nuclear Plant Circulating Water Intake Structure, Massachuse tts :
L.
1964 - 1970 Department of Public Works of Canada I'
Regional Coastal Engineer and Territorial l.
Engineer
-Suitability of Air Bubble Breakwaters for Use on B.C. Coast.
d O
W.A. MCLAREf!
SENIOR ENGINEER Bachelor of Engineering (Civil), McGill University, 1960 EDUCATION Master of Science (Glaciology), University of Melbourne, 1968 Engineering Aspects of Heat Disposal from Power Generation -
Summer Session Course, Massachusetts Institute of Tech. 1975 MEMBERSHIPS Member, Canadian Society for Civil Engineering Member, Permanent International Association of Hydraulic Research.
AWARDS Polar Medal EXPERIENCE Western Canada Hydraulic Laboratories Ltd.,
197"> - date Vancouver, B.C.
- Small Boat Harbour Flushing Study
- Cape Tormentine Ferry Terminal - Breakwater relocation
- Reserve Mining Co. - Stabilization of delta foreshore
- Beaufort Sea Study - Meteorology and wave analysis
- Sonatrach LNG Plant - Vortex elimination in pump bays
- Gabriola Island Ferry Terminals - Wind, wave and current assessments
- Warm Water Storage - Stratification of water densities in storage tank
- Sundance Cooling Pond - Cooling pond currents
- Vogtle Nuclear Plant - Emergency cooling system flows
- Arctic Oilspill Equipment - Pump and separator assessment 1971 - 1973 Willis Cunliffe Tait and Co. Ltd., Terrace, B.C.
- Consulting Engineer for communities along Skeena River
- Eurocan Pulp and Paper Co. Ltd. - River training works and infiltration gallery
- Flood damage restoration and river bank protection 1969 - 1970
- Skipper of own 48-ft schooner in Pacific Ocean 1967 - 1969 Sinclair and Knight, Sydney, Australia
- Design of intake works, Carcoar Dam
- Feasibility study for irrigation dams, N.S.W.
- Feasibility studies and design for sewage treatment works i
1964 - 1967 Australian Antarctic Division
- Wilkes, Antarctica,1965 glaciological study
- Thermal ice corer observations, Byrd Station, Antarctica.
1961 - 1963 George Wimpey Central Laboratories, London, U.K.
- Hydrographic and oceanographic survey for Jebal Dhanna oil port development, Persian Gulf
- Hydraulic model studies of Dov'er, Port Talbot, Das Island harbours 1960 - 1961 Canadian Hydrographic Service
- Hydrographic surveys in Lancaster Sound, Frobisher Bay, Moosonee and Great Lakes 1
s March, 1978
9 W. SCllRIEK liYDRAULIC ENGINEER EDUCATION School for Civil Technology, Netherlands,1952 B.E., Civil, University of Saskatchewan, 1961 M.Sc., Hydraulics, University of Saskatchewan, 1963 C.E., Hydrodynamics, Massachusetts Institute of Technolo gy, 1966 REGISTRATION Association of Professional Engineers of Sas ka tch ewan MEMBERSHIPS Member, Engineering Institute of Canada Member, Canadian Society for Civil Engineering Member, American Society of Civil Engineers EXPERIENCE 1973 - date Western Canada Hydraulic Laboratories Ltd.,
Vancouver, B.C.
Coastal and River Studies:
- Fraser River Model Studies - Steveston Boat Harbour River Training for 40' draft; Fraser Estuary Salinity Intrusion
- Fraser River Borrow Hole Migration
- Fitzsimmons Creek Flood Levels
- Alouette River Bridge Pier Erosion Special Studies:
- Outfall design - Island Copper Mine, Port Hardy, B.C.;
Anaconda Britannia Mines; Climax Molybdenum of B.C., Alice Arm, B.C.
- Jet Pumps for Fish Transport
- Autcmatic Fish Tub Washer
- Emergency Cooling Pump Intakes - Davis Besse Nuclear Power Plant; Detroit Edison Co. ; J.M.
Farley Nuclear Power Plant; Alabama Light &
Power Co.
1966 - 1973 Sa'skatchewan Research Council
- Development of pipeline transportation tech-nology of thermal and cetallurgical coals, iron cres, potash, limestone, tailings sands and others for Canadian Industry sponsored by:
(a) Canadian Transport Commission, 3 year program (b) Canadian National Railways, 4 months p rogram
- Feasibility potash solids pipeline (2 1/' years)
- Tarsands tailings pipeline for Syncrude Ltd.
- Copper concentrates by pipeline (Trimac)
- Helically ribbed pipes for sand transport (Dominion Gasket and Mfg. Co.)
^
1963 - 1966 Massachusetts Institute of Technology
- Assistant, Research on sediment transport studies 1963 Underwood and McLellan & Associates
- Construction of sewer and water facilities 1961 Stock, Keith 6 Associates
- Grid road network in Saskatchewan 1954 - 1960 Saskatchewan Department of Highways
- Engineering, design and construction of highways March, 1978