ML20024D338
| ML20024D338 | |
| Person / Time | |
|---|---|
| Issue date: | 05/18/1983 |
| From: | Morton K NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Corkran T BABCOCK & WILCOX CO. |
| Shared Package | |
| ML20024D328 | List: |
| References | |
| CON-NRC-04-83-168, CON-NRC-4-83-168 NUDOCS 8308040555 | |
| Download: ML20024D338 (29) | |
Text
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APPENDIX A
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NUCLEAR REGULATORY COMMISSION jd47 20 8 3
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NAY 181983 Babcock & Wilcox Contract Research Division ATTN: Mr. T. D. Corkran, Manager Contracts - Legal P.O. Box 835 (1562 BeesonStreet)
Alliance, OH 44601 Gentlemen:
Subject:
Babcock & Wilcox (B&W) Proposal No. R&D 82-291, " Integral System Test Program -- Once-Through Integral System (0 TIS) and Multiloop Integral System Test (MIST) Components" Coninission approval has been received to enter into a contract for the.
subject effort.
It is anticipated that a contract shall be awarded to B&W during the month of June 1983. Accordingly, pursuant to 51-15.205-30 of the Federal Procurement Regulations, precontract costs in an amount not to exceed $150,000.00 are authorized for the purpose of developing the MIST Facility specification.
This specification has been in progress since February 1983 and as of this date, approximately $70,000.00 has been expended by B&W.
It is anticipated that work on the specification shall be completed during September 1983.
The aforementioned precontract costs are allowable to the extent that they would have been allowable if incurred after the date of the contract.
Sincerely, g
Kell _ogg %. Morton, Chief Technical Contracts Branch Division of Contracts Office of Administration 8308040555 830608 PDR CONTR NRC-04-83-168 PDR
ATTACHMENT 1 3.0 PHASE I OTIS PROJECT STATEMENT OF W9RK 3.1 OVERVIEW The OTIS Project (Phase I) component of the Integral System Test Program is structured in ten (10) tasks as shown in Table 3-1.
TABLE 3-1 PHASE I OTIS PROJECT STRUCTURE TASK TITLE 1
Program Management 2
Design Requirements 3
Functional Specification 4
Test Specification 5
Test Plans and Procedures 6
Facility Modification 7
Testing 8
Data Processing Programs Revision and Documentation 9
Data Handling and Analysis 10 Reporting A description of each task is presented in the following sections.
3.2 TASK 1 - PROGRAM MANAGEMENT The Program Management task shall include managing of the program scope, schedule, and budget by the B&W Program Manager, the ARC Technical Manager and X
the UPGD Technical Coordinator.
Preparation of monthly status reports, budget and schedule projections and attendance at Program Management Group (PMG)
Meetings are part of this effort.
In addition, the coordination of ARC and UPGD technical activities and interaction with PMG technical people is included.
Page No. 3-1
i This total management effort shall be a continuous one starting with the effective date of the contract under Task 1 and continting through the end of Task 10 for seventeen (17) months.
3.3 TASK 2 - DESIGN REQUIREMENTS A document entitled, "GERDA Design Requirements," was prepared by UPGD specifying the scaling, components, subsystems, supporting systems, and instrumentation of GERDA. This document shall be updated by UPGD to reflect the Phase I - OTIS Project modifications subject to the review and approval by the PMG. Also, the SAVER Code shall be rerun to predict the primary loop irrecoverable pressure losses with the hot leg isolation valve removed (the valve was removed during the GERDA test program).
The SAVER results will be documented in the Lpdated Design Requirements.
3.4 TASK 3 - FUNCTIONAL SPECIFICATION A " Loop Functional Specification" document was prepared by ARC for the GERDA test facility. This document describes the facility conceptual design based on the design requirements provided by UPGD, and identifies major subsystems, hardware, and instrumentation in the loop. Mechanical dimensions and instrumentation considered critical to the successful performance of the test program are identified in this document.
This document will be revised and reissued reflecting the modifications for the Phase I - OTIS Project.
3.5 TASK 4 - TEST SPECIFICATION A document shall be prepared by UPGD identifying the specific tests to be performed for the Phase I - OTIS Project. This test specification document will X
list important nominal and initial conditions for each test, as well as the general conduct and evolution of each planned test subject to the review and approval by the PMG.
Page No. 3-2
i 1
3.6 TASK 5 - TEST PLANS AND PROCEDURES X
A Project Technical Plan shall be prepared for the Phase I - OTIS Project.
The Project Technical Plan shall specify the program objectives, identify items critical to successful completion of those objectives, and present the technical approach of the project.
A Quality Assurance Plan shall be prepared for review by the PMG.. This document specifies the verification methods to be followed in order to assure compliance with the Project Technical Plan.
X Technical Procedures shall be written for all phases of the test program.
The technical procedures shall include the details required for test performance.
Information on the decay power curve, valve alignments, etc., shall be included.
3.7 TASK 6 - FACILITY MODIFICATION Facility Modifications consist of the following items:
X e
Add reactor vessel head vent and flow restrictor between upper plenum and upper head of reactor vessel.
e Guard heat upper and top plenums of reactor vessel.
o Guard heat pressurizer surge line.
e Relocate the cold leg flow measurement by adding a new flanged section in the cold leg near the OTSG outlet.
e Install Cold Leg Suction branched leaks (including extra critical flow leak orifices).
e Install string TC's and pitot tubes in steam generator.
Page No. 3-3
3.8 TASK 7 - TESTING A summary of the test program for Phase I - OTIS Project is presented in Table 3-2.
Additional testing will be performed as directed by the PMG. As indicated, the Phase I testing shall consist of 13 test points and will require a testing period of approximately 9 weeks.
X Appendix C contains an expanded description of the OTIS test matrix.
X If additional testing (and data analysis) is possible the tests described in Table 3-3 will be performed as directed by the PMG.
3.9 TASK 8 - DATA PROCESSING PROGRAMS REVISION AND DOCUMENTATION The data acquisition, data reduction, and data handling computer programs shall be modified to include the instrumentation added to GERDA in the Phase I -
OTIS Project.
(The added instrumentation primarily consists of control thermocouples which accompany the new guard heaters.) Also, the color graphics X
display shall be modified to show the additional leak site at the reactor vessel top plenum. This provides the loop operator with an indication of active leak sites throughout the test loop while testing is in progress.
The existing documentation for the data processing programs shall be updated, and the programs shall be certified upon completion of the modifications.
Page No. 3-4
TABLE 3-2
SUMMARY
OF PHASE I OTIS PROJECT TESTS TEST NO. OF TEST POINTS 1.
Benchmark - Link OTIS to GERDA 1
2.
Characterization of Reactor Vessel HPV - Test 1
features peculiar to OTIS Project:
Reactor Vessel HPV (with RV Upper Head Typicality) 3.
Leak Configuration - Leak size and isolation 3
effects on SBLOCA transient; parameterize on leak size.
4.
Secondary Characteristics - Steam generator 2
level and control.
5.
High Pressure Injection Capacity - HPI capacity 1
and control.
6.
HPI Cooldown - No AFW or leak, throttle HPI.
1 7.
Composite Transient - Transitions among cooling 1
techniques: Leak-HPI, to HPI and PORV, to steam generator cooling.
2 8.
Leak Location - Orifices for 20 cm leak in 2
CLD line and PORY will be available for determination of leak location effect on SBLOCA transient.
(Test proceeds as per Test 3.)
9.
Low Head High Pressure Injection - Composite 1
test to be run with 1/2 installed HPI capacity and 1700 psia shutoff head.
(Test proceeds as Test 7.)
X 13 Page No. 3-5
's TABLE 3-3 ADDITIONAL TESTS FOR PHASE I - OTIS PROJECT '
TEST NO. OF TEST POINTS X
e Rerun of Test 7 or 9 without guard heaters.
1 X
e Steam Generator Depressurization Rate - Test i
represents new category approaching Steam Line Break testing. Maximum depressurization rate to be determined by facility limitations.
Previous testing indicates at least 210 psf / min possible.
X e
Feed / Bleed Cooldown - HPI cooldown test with I
delayed ECCS actuation.
(Test proceeds as Test 6.)
X e Natural Circulation Mode Transition - Composite 1
test using maximum wetting AFW nozzles.
(Test proceeds as Test 7.)
X e Feed / Bleed Cooldown - HPI cooldown tests varying 2
PORV capacity for bleed.
One test simulating PORY line break, one test simulating PORV and safeties. Facility 21imits capacity to equivalent of 77 cm leak.
(Test proceeds'as Test 6.)
Page No. 3-6
3.10 TASK 9 - DATA HANDLING AND ANALYSIS Upon completion of each test in the Phase I - OTIS Project, Quick-Look Plots X
shall be generated immediately using the existing software.
Preliminary data shall be transmitted from the Data Acquisition System to the VAX computer at ARC where the data shall be reduced to engineering units and calculated parameters of interest. The data shall then be sorted to select the most important parameters and a sufficient number of data scans for preliminary analysis.
The set of sorted data shall be electronically transferred to CPGD in Lynchburg, Virginia, where analysis of the data shall be performed and plot files for approximately 50 plots for each test point shall be prepared. The plot files shall be routed to ARC, UPGD, and potentially other sites (for interested parties among the participants) where the plots can be automatically generated.
It shall be the responsibility of the receiver to adapt to the B&W plot file fomats.
Approximately ten work days after the completion of each test point a copy of the Quick-Look Plots shall be sent to the PMG representative of each organization.
An uncertified data tape shall also be sent to NRC data bank about ten days after each test.
For each test, the results shall be reviewed to check for consistency and validity of the measurements. This shall be accomplished by comparing redundant measurements, checking instrument zero readings, calculating component and system energy balances and by performing a general review of the experimental results.
Errors and other anomalies detected in the data shall be corrected and the tapes on which the data are stored shall be revised and reissued up to two times. The data plots shall be regenerated, if necessary, to correct identified errors.
3.11 TASK 10 - REPORTING A draft final report shall be issued after all testing and analyses are completed for review and approval by the PMG. Following approval by the PMG, a X
final camera-ready report shall be furnished suitable for publication. The final report shall be comprehensive and self contained, and shall include certified and interpreted test data for all test categories.
Page No. 3-7 I
4.0 PHASE I OTIS PROJECT SCHEDULE The schedule for the OTIS Project (Phase I) is shown in Figure 4-1.
This X
component of the IST Program spans a period of 17 months.
The schedule for the Phase I - OTIS Project is based on a PMG authorized start date of June 1,1983 and on the availability of GERDA for facility modifications on October 1,1983.
1 r
Page No. 4-1
6.0 PHASE II - MIST FACILITY SPECIFICATION
6.1 INTRODUCTION
A Facility Specification shall be prepared for the Multiloop Integral System X
Test (MIST) Facility.
The purpose of the specification is to define the basic scaling requirements, component configurations, instrumentation locations and the test requirements. This document shall consist of three main sections: the Design Requirements, Loop Functional Specification, and Test Specifications.
Each of these is described below.
The results of the Facility Specification (i.e., the conceptual loop design) shall be reviewed and approved by the PMG.
6.2 STATEMENT OF WORK 6.2.1 Task 1 - Design Requirements The Design Requirements section shall provide the scaling requirements and philosophy to proceed from the plant to a scaled model. The results of this section shall be used as the input to the Loop Functional Specification.
This effort shall include and address:
Compilation of Elevations, Volumes, Metal Mass, and Major Plant Parameters e
For all 177FA, lower loop plants, compile the elevations of the Reactor Coolant System, Reactor Vessel, Core, and Reactor Coolant X
Pumps, and Steam Generator.
As a minimum, the following elevations shall be considered:
t I'
Page No. 6-1 I
=
Reactor Vessel Downcomer (DC) top,(inside surface) e e
RVVV spillover and centerline o
DC to lower plenum flowpath e
elevation of highest and lowest flow hole in the flow distributor Inside surface of Reactor Vessel bottom Core e
lower grid, top and bottom faces e
bottom of fuel e
fuel centerline e
top of fuel e
upper grid, top and bottom faces Outlet e
hot leg (HL) nozzle centerline e
plenum cylinder flow hole centerline e
bottom face of plenum cover o
top of RV (inside surface)
~
Hot Leg Upturn to vertical interface Hot leg U-bend (HLUB)
~
l e
start and end e
top, inside lower surface of pipe HL to steam generator interface Steam Generator Inlet nozzle-upper plenum interface Upper tube sheet e
upper surface e
lower surface l
Tube support plates centerlines AFW nozzle centerlines Lower tubesheet e
upperface l
e lowerface Page No. 6-2 4
g--
p.
+ -,---
m
Outlet e
outlet nozzle-to-cold leg interface e
outlet plenum bottom Cold Leg Horizontal run, steam generator to reactor coolant pump e
inside top of pipe e
cold leg to reactor coolant pump interface Reactor coolant pump spillover Discharge e
elevation of the HPI injection nozzles e
cold leg to reactor vessel centerline Pressurizer spray centerline Pressurizer Surge line to hot leg connection centerline Low point, inside top of pipe Pressurizer surge line-surge nozzle interface e
bottom inside surface e
pressurizer heater elevations (top and bottom of bank) e top inside PORY, safety elevation e
For one representative 177FA lower loop plant, compile the primary fluid volumes. The following volumes will be included:
Reactor Vessel Upper downcomer (above nozzle centerline)
Lower downcomer (to plenum flow hole)
Lower plenum Core Upper plenum Top plenum (above upper plenum cover)
Page No. 6-3
Hot Leg Horizontal section Upturn Vertical section Stub (vertical run from HLUB to the steam generator inlet nozzl e)
Steam Generator Inlet nozzle Inlet plenum Tubes Outlet plenum Outlet nozzle Cold Leg Suction Piping Bend (steam generator to horizontal)
Horizontal Upbend Stub (vertical run to the reactor coolant pump inlet)
Reactor Coolant Pump Below and above spillover Cold Leg Discharge Piping Horizontal Downturn Sloping Upturn Stub (horizontal run to nozzle)
Pressurizer Vessel Surge line Spray line Miscellaneous Primary system total Steam generator secondary total Page No. 6-4
i I
\\
I e
For one representative 177FA lower loop plant, compile the metal mass of the primary systems. Compile the composition', thickness, including insulation heat transfer area, for each major metal section of the components listed below.
Reactor Vessel Downcomer Lower plenum Core Upper and top plenum Hot Leg Steam Generator Inlet Tubes Outlet Cold Leg Cold leg suction Reactor coolant pump Cold leg discharge Pressurizer Vessel Surge line Spray line Primary System Total Steam Generator Secondary Total e
For the lower loop plants compile the system characteristics and procedures for HPI, primary makeup, LPI, HPV, core flood, auxiliary feedwater, secondary steam dump valve, RCP coastdown curves, and pressurizer heater capacity. The following specific items shall be considered.
Determine plant procedure for the independent or combined use of HPI, makeup, and/or LPI; including ECCS cross-connect procedures.
Page No. 6-5
Determine plant procedures for use of HPV either individually or combined.
Establish plant cooldown procedures emphasizing cooldown rate, pressure-temperature limits, HPI throttling guidelines, and operator action when core voiding is evident.
Establish steam generator level control, feed-up rate, set-point procedures.
Including evaluation of faulted steam generator procedures.
Establish RCP trip-time envelope following a SBLOCA. Determine procedures for pump restart.
Overall Facility Scaling X
Confirm the phenomena to be modeled and tested.
Determine the overall scaling, elevations, power, volume, components irrecoverable pressure losses, and key model features (viz, hot leg, pressurizer ECCS nozzles, steam generator inlet primary distributors and primary / secondary leak locations). Also identify the 177FA lowered loop plant to be used as the reference plant for facility characteristics. Develop conceptual loop layout to be consistent with the desired scaling criteria.
Measurements and Data Processing l
Develop conceptual requirements for instrument types, locations, accuracy, and acquisition frequency.
Plan data processing program.
Design of Core and Reactor Vessel l
l e
Determine the thermal-hydraulics requirements necessary to model the core and vessel. The following shall be considered.
Page No. 6-6
Subchannel enthalpy rise modeling with emphasis on unheated wall effects and vessel wall-to-core heater gap.
CHF evaluation (100% power full flow, low power natural circulation), axial and radial heat flux distribution (average core section or limited section).
Space for burnable poison and control rods.
Core flow distribution modeling with emphasis on nonproprietary X
aspects of the grids and pressure drop characteristics.
Evaluation of the upper vessel to downcomer leakage effect on X
e Downcomer-lower plenum interface considerations
- elevations
- volume
- mixing / stratification
- core inlet flow distribution e
Upper plenum design; plenum-nozzle interface; plenum-RVVV interface upper plenum restriction (location and size), RV-HPV location.
Design of Downcomer The following effects shall be considered in the downcomer design:
e RVVV-cold leg mixing e
condensation of RVVV steam in downcomer including plume and droplet effects Page No. 6-7
e inter-cold leg mixing e
fluid volume, elevations, and surface-to-volume ratios e
metal-to-fluid volume ratios e
lateral and axial irrecoverable loss coefficients e
pressurized thermal shock Pump Design Criteria Scale four identical model Reactor Coolant Pumps (RCP's) to provide plant-similar performance in single-phase flow, coastdown, and model mechanical criteria (pump orientation). Also two-phase flow scaling shall be considered.
The following shall be considered:
e Single-Phase Flow:
Obtain plant-typical head versus scaled flow at the full-flow design point, and at off-nominal conditions (viz, operation of less than all the RCP's).
Consider violating specific-speed scaling to improve the model pump similarity in multiphase flow.
e Coastdown:
Obtain plant-typical head-flow response versus coastdown time by controlling pump speed versus time, maintaining typicality until single-phase flowrate is less than 10% of full flow.
l Consider modifying the model coastdown to match coastdown progress to the evolution of plant conditions during the transient (i.e., if model system voiding is delayed, consider prolonging the RCP coastdown).
j Consider modifying coastdown control in events encountering two-phase flow, to adjust model flow degradation to that of the plant.
i Page No. 6-8
e Two-Phase Flow:
Determine the current estimates of prototype RCP degradation and degraded-flow performance.
Consider abandoning specific-speed scaling in favor of a pump design better preserving multiphase characteristics, e.g., sonic velocity within the pump, the ratio of impeller fluid flow area to surface area, the ratio of velocities of liquid and vapor, etc.
~
Consider controlling model pump speed to simulate flow degradation.
Consider combining two cold legs to permit pump scaling.
e Mechanical Criteria: Minimize leakage and heat loss. Consider canned-rotor pumps. Consider isolating and bypassing the pumps after coastdown.
e Pump Energy: The pump energy addition to the loop shall be considered.
e Maintain Prototypical Mechanical Performance:
Install counterrotation devices.
Estimate locked-rotor resistance to forward or reversed flow (single-phase or multiphase), consider installing flow orifices at the low point of each cold leg (suction) to augment model pump resistance.
Install the model_ : pumps in-the same orientation and with the same axis.
o,
-m ofrotation,andwiththesamepipingconfigurationasir. the plant.
X e
Consider standard pump design.
Reactor Vessel Vent Valve Design Scaling and design of RVVV are required to provide the proper flowrate and entrainment characteristics. The flow mixing with the downcomer shall also be considered under natural circulation or two-phase conditions.
2 Page No. 6-9
The following characteristics shall be considered:
e Definition of the model RVVV characteristics; flow rate and valve actuation versus driving pressure difference.
e Determination of RVVV entrainment characteristics.
e Evaluation the feasibility of several partial area / sequential opening RVVV lines.
X e
Pressurizer Design X
The following shall be considered in the design of the pressurizer.
X fluid entrainment during PORY venting X
surge line fluid inertia, flooding, and countercurrent flow X
surge line to pressurizer fluid mixing X
spray effect on condensation
._e. sign Investigations D
X Use codes to check the prototypicality of the scaled system components.
4is.. _
2._.
m, Develop a preliminary RELAP model of MIST conceptual design.
Perform i
limited transient analysis for design investigation.
Construct a SAVER code model for the primary coolant system conceptual design. Calculate the irrecoverable momentum and head losses under specified flows for forced natural circulation conditions. Compare predicted pressure loss characteristics of MIST to the prototypical values.
Technical Interface Coordinate technical schedules and outputs with ARC.
Schedule and integrate the UPGD scaling and design efforts for the input to the facility specification.
Page No. 6-10
' Design Requirements Document Assemble outputs from the design effort, integrate them, and produce design requirements section of the facility specification.
6.2.2 Task 2 - Loop Functional Specification The Loop Functional Specification shall use the design requirements as input to conceptually design the MIST loop and to identify and select key loop components and instrumentation.
All subsystems, major hardware, and instrumentation shall be identified.
In addition, mechanical dimensions will be provided for the preparation of fabrication and erection drawings.
This effort shall specifically address:
Functional and Structural Core and Vessel Design X
The core and reactor vessel (including the downcomer) design will require compromises between the optimally scaled arrangement and the feasible /ASME Code acceptable arrangement.
As part of the facility specification effort, a conceptual design shall be defined to best satisfy both constraints.
Specific
~
considerations shall include:
4 n,.
o-
.1 3
e Core heater design, single-ended or double-ended rods.
~
e Bundle arrangement, CHF evaluation (heater design), and CHF instrumentation (if needed).
e Sealing of vessel penetrations and electrical isolation for core heaters.
Cooling and moisture barrier for core heater electrical termination.
e e
Use of DC or AC power for heaters.
Page No. 6-11
e Core heater configuration for desired heat flux profile.
e Rod bow.
e Evaluation of core heaters for a 10% versus 100% scaled power core.
e Safety (trip) instrumentation.
e Capability of core heaters to operate in steam environment, maximum permissible heat flux. Tine duration for use in uncovered condition and energy storage in uncovered condition.
e Reactor vessel arrangement for desired scaling, particular emphasis on bottom - vessel entrance for downcomer flow, core heater to vessel wall gap, core heater removal and replacement.
e Lower plenum / core inlet flow distribution (definition of possible bench scale test).
X e
Upper plenum and upper head geometry, arrangement, mechanical constraints.
e Instrumentation in downcomer for loop-to-loop and fluid stratification, o
Mechanical arrangement of the downcomer for scaling considerations versus minimization of heat loss and code fabrication requirements.
Functional and Structural loop Layout X
The scaling requirements defined in Task 1 prescribe a desired configuration of the primary coolant system. Analyses shall be performed to determine the required structural and mechanical constraints and to define the required functional performance of key equipment.
Page No. 6-12
i
= The specific items listed belov shall be evaluated as part of this task.
Define the conceptual primary loop arrangement with specific emphasis e
on component and piping supports.
Thermal growth and pipe stresses shall be calculated. Materials' will be selected and support locations shall be defined.
The capability for' isolating and bypassing the RCP's during testing e
shall be considered. Conceptual layouts shall be prepared, required components defined and availability of components determined.
The advantages and/or disadvantages of this approach shall be determined for consideration and comparison to possible pump leakage and heat loss difficulties.
e Location of the primary coolant system in the building shall be defined to allow proper interfaces to existing boundary systems.
The boundary systems that shall be considered are the condenser, steam lines, secondary forced circulation system, feed lines, the single-and two-phase leak systems and the HPI system.
e Location of the conceptual loop arrangement in the building envelope i shall be reviewed to insure that.adeq'uate space shall be. avail,able. i,
u. n e
Loop heat. losses of the primary coolant system and the steam generator shall be estimated.
Special consid'eration shall given to both water and steam phase effects.
This information shall be used to define guard heater capacity and control zone lengths.
l e
Determine under what conditions the existing OTSG "A" shall be structurally adequate for the planned tests in the MIST facility.
I Page No. 6-13 l
o Evaluate the influence of the number and location of tube support plates in the steam generator. Determine if the number and locations in the new steam generator should match OTSG "A" or the plant.
(OTSG "A" has 16 tube support plates compared to 15 in the plant steam generators).
e Evaluate possible thermocouple and pressure tap penetrations with the intent to minimize heat losses.
e Determine the adequacy and/or define the modifications required to the existing heat exchangers steam condenser secondary circulation pump, heat removal single-phase leak two-phase leak (HPV and PORY locations) e Define the adequacy of existing or define the requirements for the following valves feedwater steam pressure control simulation of steam dump valves pressurizer isolation valves leak isolation
- forced circulation systein valves needed for AFW head / flow control
- HPI system (forward and bypass feed)
- Code required primary loop valves e
Establish the required pipe and/or tube sizes and layouts (thermal / hydraulic and code) for the feedwater, steam, HPI, LPI, core flood, and leak systems Page No. 6-14
j
~
X a
Determine the adequacy of existing code safety valves or define new specifications e
Establish the conceptual layout of the LPI and core flood system o
Identify the need for and define benchscale qualification or evaluation tests.
Reactor Coolant Pump Design and Vendor Identification Scaling and design of the reactor coolant pumps will require a significant degree of interaction between 'the scalers, designers, and potential pump vendors.
The purpose of this effort will be to determine the conceptual pump design and to identify the pump vendor to satisfy the scaling constraints, minimize heat loss, end minimize inventory leakage. Specific efforts shall include:
X e
Specification of head / flow coastdown and degraded performance.
e Interact with possible vendors to identify achievable pump characteristics.
e Identify requirements for pump motor starter, safety interlocks, and cooling requirements.
e bevelop conceptual layout and pump supports in cold legs.
e Evaluate bearing, seals, and general pump arrangement.
Functional and Structural Design of Reactor Yessel Vent Yalve X
The vent valve characteristics in OTIS are modeled by a line between the reactor vessel plenum and the downcomer with a restrictor in the line that simulates the full open vent valve resistance. The opening and closing of the X
OTIS vent line is controlled by an automatically controlled isolation valve located in the plenum-downcomer cross-over line.
The isolation valve is Page No. 6-15
X programned to open and close based on predetermined AP values.
Simulation of the vent valve in this manner will not provide characteristics experienced when the vent valve is partially opened.
Partially open vent valve characteristics shall be considered.
Specific consideration shall include:
e RVVV configuration and valve type (single or multiple lines).
e RVVV opening and closing speed.
e RVVV partial open resistance.
e Measurement or control of RYVV position.
e Investigation of the feasibility of metering RVVV flowrate in single and/or two-phase flow.
Specification of hardware required for vent valve simulation.
e Building and Supporting Facilities The detail requirements for the building modifications and expansion shall be defined. This effort will be coordinated with the loop layout to ensure that adequate space shall be available for the MIST Facility. Overall building height requirements shall be set based on the elevations compiled as part of Task 1, Phase II.
Requirements for utilities, such as electricity, tower water, city water, high-purity water, compressed air, lighting and heating shall be specified. For example, the electrical demands associated with the loop components and general uses (RCP, core, pressurizer heaters, guard heaters, HPI pump, secondary pumps, controls and general lighting) shall be compiled to insure that the electrical demands are met.
Page No. 6-16 l
Data Acquisition System X
The DAS equipment and software used for OTIS will require modification and expansion. Hardware needed to satisfy the specified requirements shall be identified.
Existing hardware will be integrated into the 2 x 4 system to the maximum extent possible. The conceptual arrangement or specification for the DAS software shall be prepared.
The specification shall provide sufficient detail to guide software development.
The specific activities shall include:
e The requirements for the new analog to digital conversion equipment shall be specified and the equipment shall be selected.
Included shall be considerations of:
- accuracy
- resolution speed required for data acquisition
- noise rejection characteristics
- interface (to computer)
- expansion capabilities
-- - compatibility with existing hardware.
The requirements of the data acquisition computer and peripherals shall e
be defined and the hardware identified.
X The following features shall be evaluated:
Processing speed. The processing speed shall have to be sufficient to acquire and store data at the defined rate (to be determined during the facility specification task) and to support the operator / loop interface.
Particular emphasis shall be placed on evaluating the requirements for conductivity probes.
Page No. 6-17
f 8
Terminals. Terminals should be available for operator /
loop interface, monitoring of specific loop instrumentation /
parameters, trend plotting, software preparation and revision, and hardcopy listings.
Data Storage.
Acquired data shall be either stored on-site and/or transferred to an off-line machine for data storage. The approach and the hardware to be used shall be identified.
Communications.
Hardware requirements for interfacing computers for data transfers shall be defined.
Computer Processing Capacity. The trade-off between increased on-site computer capacity and off-site processing costs shall be evaluated.
The conceptual structure for the data acquisition software shall be e
defined.
Included shall be considerations of:
- data ocquisition speed reduction to engineering units
- data analysis
- data transmittal
- archival
- sorting and plotting (on-line and off-line)
- operator / loop interface (color graphics)
- replay (to color graphics)
- video recording of color graphics
- processing of conductivity probe information
- data format for transmittal and archival
- sequential versus random access data files
- data file security Page No. 6-18
transmittal of sorted data files and data tapes to the NRC/DAE data base application of NRC Automated Data Qualification Program (NRC to provide the program)
Instrumentation and Controls Instrumentation requirements for the MIST Facility shall be compiled and provided for review by the PMG.
Special emphasis shall be placed on:
o Instrument type, location, accuracy, response, noise sensitivity, and signal conditioning.
e The structural integrity (i.e., dynamic load, vortex shedding, etc.) of intrusive instruments in the primary circulation loop shall be evaluated and satisfactory arrangements defined:
~
flush mounting of viewports
- identification of vendors identification of special calibration or qualification tests.
e Control concepts for the following shall be defined
- core power (steady and ramp)
- pressurizer pressure
- pressurizer level
- LPI head / flow HPI head / flow
- steam pressure (steady and ramp)
- AFW head / flow steam generator level (constant, modulated, and feedup)
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Guard heater zone lengths shall be evaluated and the control scheme defined.
Loop Functional Specification Section of the Facility Specification The Loop Functional Specification section of the Facility Specification shall document the efforts performed to conceptually design the loop components, piping, auxiliary subsystems, instrumentation, controls, DAS, RCP's, and the building and supporting facilities.
6.2.3 Task 3 - Test Specification A Test spacification section shall be prepared. This document shall X
identify the tasts to be performed, background discussion of each test, objective of the tests, ind a general description of test procedures.
6.3 PHASE II MIST FUNCTIONAL SPECIFICATION SCHEDULE Tas,k completion is scheduled for September 30, 1983 with PMG review and approval-by October 31, 1983.
B&W shall provide a reference design for review by the PMG before the ACRS Meeting scheduled in July.
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