ML20010J013
| ML20010J013 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 09/24/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM SLNRC-81-112, NUDOCS 8109290502 | |
| Download: ML20010J013 (22) | |
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SNUPPS Standardized Nuclear kJnit Power Nnt Systen 5 Choke Cherry Road Nicholas A. Petrick Rockville. Merviend 20850 Executive Director (301) 8694010 l September 24, 1981 SLNRC 81-112 FILE: 0541
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SUBJ: NUREG-0737 Item II.F.2
- r. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Docket Nos. STN 50-482, STN 50-483, and STN 50-486
Reference:
NRC (Youngblood) letter to UE (Bryan) and KGE (Koester),
dated September 1,1981, SNUPPS FSAR Request for Additional Information .
Dear Mr. Denton:
The referenced letter requested additional information on the subject TMI review item. The enclosure to this letter provides the requested information and will be incorporated in a future revision to the SNUPPS FSAR.
Very struly yours, e.h < w (
Nicholas A. Petrick RLS/mtk Enclosure p Cb cc: J. K. Bryan D. F. Schnell UE UE g IhN Ndd f h ('p G. L. Koester KGE ~
w ggp2 O I98I A - ___
D. T. McPhee KCPL W. A. Hansen NRC/ CAL k ""To,'jyp'on III N T. E. Vandel NRC/WC /.
Cf h ol M109290502 810924
p;hIl PDR ADOCK 05000482 A PDR.
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .J
s SLNRC 81-112 Enclosure SNUPPS Q492.9 The staff has reviewed the applicants' response to the requirement of Item II.F.2 of NUREG-07Tf and found that the applicants have not provided the ict.umentation 4 required by Item II.F.2. Therefore, the staff will require that the applicants provide the documentation required by Item II.F.2 of NUREG-0737.
RESPONSE See revised Section 18.2.13.
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SNUPPS 18.2.13 INSTRUMENTATION FOR DETECTION OF INADEQUATE CORE COOLING (II.F.2) i 18.2.13.i NRC Guidance Per NUREG-0737 Position Licensees shall provide a descriptien of any additional instru-mentation or controls (primary or backup) proposed for the plant to supplement existing instrumentation (including primary coolant saturation monitors) in order to provide an unambiguous, easy-to-interpret indication of inadequate core cooling (ICC).
A description of the functional design requirements for the system shall also be included. A description of the procedures to be used with the proposed equipment, the analysis used in developing these procedures, and a schedule for installing the equipment shall be provided.
Clarification (1) Design of new instrumentation should. provide an unambiguous indication of ICC. This may require new measurements or a synthesis of existing measurements which meet design criteria (item 7).
(2) The evaluation is to include reactor-water-level indication.
(3) Licensees and applicants are required to provide the necessary design analysis to support the proposed i
final instrumentation system for inadequate core i
cooling and to evaluate the merits of various instru-ments to monitor water level and to monitor other parameters indicative of core-cooling conditions.
(4) The indication of ICC must be unambiguous in that it should have the following properties:
I (a) It must indicate the existence of inadequate core cooling caused by various phenomena (i.e., high-void fraction-pumped flow as well as stagnant boil-off); and, t
18.2-57
8 SNUPPS (b) It must not erroneously indicate ICC because of the presence of an unrelated phenomeno;.. 1 (5) The indication must give advanced warning of ,the approach of ICC. ,
(6) The indication must cover the full range from normal '
operation to complete core uncovery. For example, water-level instrumentation may be chosen to provide advanced warning of two-phase level drop to the top of the core and could be supplemented by other indicators such as incore and core-exit thermocouples provided that the indicated temperatures can be correlated to provide indication of the existence of ICC and to infer the extent of core uncovery. Alternatively, full-range level instrumentation to the bottom of the core may be employed in conjunction with other diverse indicators such as core-exit thermocouples to preclude misinterpretation due to any inherent deficiencies or inaccuracies in the measurement system selected.
(7) All instrumentation in the final ICC system must be evaluated for conformance to Appendix 8 (to NUREG-0737), l
" Design and Qualification Criteria for Accident Monitoring Instrumentation," as clarified or modified '
by the provisions of items 8 and 9 that follow. This is a new requirement.
(8) If a computer is provided to process liquid-level signals for display, seismic qualification is not required for the computer and associated hardware beyond the isolator or input buffer at a location The accessible for maintenance following an accident.
single-failure criteria of item 2, Appendix Eb need l not apply to the channel beyond the isolation device if it is designed to provide 99 percent availability with respect to functional capability for liquid-level display. The display and associated hardware beyond the isolation device need not be Class 1E, but should be energized from a high-reliability power source which is battery backed. The quality assurance provisions cited in Appendix sh item 5, need not apply l to this portion of the instrumentation system. This is a new requirement.
(9) Incore thermocouples located at the core exit or a discrete axial levels of the ICC monitoring system and 5 which are part of the monitoring system should be evaluated for conformity with Attachment 1, " Design and Qualification Criteria for PWR Incore Thermo-couples," which is a new requirement.
18.2-58
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.. SNUPPS (10) The types and locations of displays and alarms should be deterrained by performing a human factors analysis taking into consideration:
(a) The use of this information by an operator.during '
both normal and abnormal plant conditions.
(b) Integratien into emergency procedures.
(c) Integration into operator training, (d) Other alarms during emergency and need for prioritiza-tion of alarms. l ATTACHMENT 1, DESIGN AND QUALIFICATION CRITERIA FOR PRES'SURIZED-WATER REACTOR INCORE THERMOCOUPLES (1) Thermocouples located at the core exit for each core quadrant, in conjunction with core inlet temperature data, shall be of sufficient number to provide indica-tion of radial distribution of the coolant enthalpy (temperature) rise across representative regions of the core. Power distribution symmetry should be considered when determining the specific number and location of thermocouples to be provided for diagnosis of local core problems.
(2) There should be a primary operator display (or displays) having the capabilities which follow:
(a) A spatially oriented core map available on demand indicating the temperature or temperature dif-ference across the core at each core exit ther-mocouple location. .
l (b) A selective reading of core exit temperature, continuous on demand, which is consistent with l
parameters pertinent to operator actions in connecting with plant-specific inadequate core cooling procedures. For example, the action requirement and the displayed temperature might be l
either the highest of all operable thermocouples or the average of five highest thermocouples.
(c) Direct readout and hard-copy capability should be available for all thermocouple temperatures. The 2
range should extend from 200 F (or less) to 1800 F (or more).
(d) Trend capability showing the temperature-time history of representative core exit temperature values should be available on demand.
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SNUPPS 9 9 (e) Appropriate alarm ~apability should be provided consistent with operator procedure requirements. t (f) The operator-display device interface shall be human-factor designed to provide rapid access to requested displays.
(3) A backup display (or displays) should be provided with the capability for selective reading of a minimum of 16 operable thermocouples, 4 from each core quadrant, all within a time interval no greater than 6 minutes.
The range should extend from 200 F (or leta) to 2300 F (or more).
(4) The types and locations of displays and alarms should be determined by performing a human-factors analysis taking into consideration:
(a) the use of this information by an operator during both normal and abnormal plant conditions, (b) integration into emergency procedures, (c) integration into operator training, and (d) other alarms during emergency and need for prioriti-zation of alarms.
(5) The instrumentation must be evaluated for conformance to Appendix B (to NUREG-0737), " Design and Qualifica-tion Criteria for Accident Monitoring Instrumenta-tion," as modified by the provisions of items 6 through 9 which follow.
(6) The primary and backup display channels should be electrically independent, energized from independent station Class lE power sources, and physically separated in accordance with Regulatory Guide 1.75 up to and including any isolation device. The primary display and associated hardware beyond the isolation device need not be class lE, but should be energized from a high-reliability power source, battery backed, where momentary interruption is not tolerable. The backup display and associated hardware should be Class 1E.
(7) The instrumentation should be environmentally qual-ified as described in Appendix B, Item 1, except that i seismic qualification is not required for the primary display and associated hardware beyond the isolater/
input buffer at a location accessible for maintenance following an accident.
18.2-60 Rev. 5 7/81
, SNUPPS (8) The primary and backup display channels should be designed to provide 99 percent availability for each
, channel with respect to functional capability to display a minimum of four thermocouples per core quadrant. The availability shall be eddressed in Technical Specifications.
(9) The quality assurance provisions cited in Appendix B, item 5, should be applied except for the primary display and associated hardware beyond the isolation device.
18.2.13.1 SNUPPS Response T. N S Eli.T l
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18.2-61
INSERT Item II.F.2 of NUREG-0737 specifies the following as required documen-tation concerning instrumentation for detection of inadequate core cooling (ICC):
(1) A description of the proposed final system including:
(a) a final design description of additional instrumf.ntation and displays; (b) a detailed description of existing instrumentation systems (e.g., subcooling meters and incore thermocouples), including parameter ranges and displays, which provide operating infor-mation pertinent to ICC consideration; and (c) a description cf any planned modifications to the instrumen-tatfon systems Cescribd in item 1.b above.
(2) The necessary design analysis, including evaluation of various instruments to monitor water level, and available test data to support the design described in item I above.
(3) A description of additional test programs to be conducted for evaluation, qualification, and calibration of additional instru-mentation.
(4) An evaluation, including proposed actions, on the conformance of the ICC instrument system to this document, including Attachment 1 and Appendix B. Any deviations should be justified.
(5) A description of the computer functions ast,0ciated with IcC monitor-ing and functional specifications for relevant sof tware in the process computer and other pertinent calculators. The reliability of nonredundant computers used in the system should be addressed.
(6) A current schedule, including contingencies, for installation, testing and calibration, and implementation of any proposed new instrumentation or informative displays.
(7) Guidelines for use of the additional instrumentation, and analyses used to develop these procedures.
(8) A summary of key operator action instructions in the current emergency procedures for ICC and a description of how these proce-dures will be modified when the final monitoring system is imple-mented.
(9) A description and schedule commitment for any additional submittals which are needed to support the acceptability of the proposed final instrumentation system and emergency procedures for ICC.
Page Two ne following is a discussion of each of the above items as they relate to the SNUPPS instrumentation for detection of ICC: _
(1) The final system to be used at the SNUPPS units to detect'ICC consists of a reactor vessel level instrumentation system and a thermocouple / core cooling monitor system.
Reactor Vessel Level Ir.strumentation System The SNUPPS design provides redundant safety-grade (Class IE) reactor vessel water level instrumentation. The reactor vessel level instrumentation system (Figure 18.2-2) utilizes two sets of two d/p cells. These cells measure the pressure differential between the bottom of the reactor vessel and the top of the vessel.
This d/p me6suring system utilizes cells of differing ranges to cover different flow behavior with and without pump operation as discussed below:
(a) Reactor Vessel - Narrow Range (APh ) This measurement pro-vides an indication of reactor ve5sel level from the bottom of the reactor vessel to the top of the reactor during natural circulation conditions.
(b) Reactor Vessel - Wide Range (oPc )
This instrument provides an indication of reactor core and internals pressure drop for any combination of operating RCPs.
Comparison of the measured pressure drop with the normal, single-phase pressure drop will provide an approximate indi-cation of the relative void content or density of the circula-ting fluid. The indication of coolant density is significant only when the subcooling is r. car zero. This instrument will monitor coolant conditions on a continuing basis during forced flow conditions.
To provide the required accuracy for level measurements tempera-ture measurements of the impulse lines are provided. Til ese measurements, together with existing r eactor coolant tanperature measurements and wide range RCS pressure, are employed to compen-sate the d/p transmitter outputs Mr differences in system density and reference leg density, particularly during the change in the environment inside the containment structure following an accident.
Additional information (i.e., analyses, evaluations) concerning the Westinghouse generic reactor vessel level instrumentation system
. has been submitted to the NRC via Reft ence 7. The specific hard-ware for SNUPPS is not exactly as documented in Reference 7, since the SNUPPS design does not include a measurement of reactor vessel level above the hot legs. However, the analyses, evaluations, and coaclusions contained in Reference 7 are applicable to SNUPPS, since they are not sensitive to the above mentioned design difference.
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Page Three Thermocouple / Core Cooling Monitor System ;
The core cooling monitor system is a core exit thermocouple / core cooling detection system which provides presentation and display of the status of the core heat removal capability to both the plant operators and the technical support center. The system consists of redundant channels and output trains of thermocouple measurements, wide range hot and cold leg RTD temperatures and reactor pressure signals. These parameters are used by the system to display thermo-couple temperatures and to calculate saturation temperatures and margin of saturation (Tsat margin) which is often referred to as subcooling. The calculations are performed by the system which is based on microprocessor and data handling devices.
Thermocouple lionitgr The core exit thermocouple portion of the ICC system is arranged as follows:
(a) Primary system The primary system measures all the thermocoeples via isolators located in the qualified back-up system cabinet.
(b) Back-up system The back-up system consists of two channels each monitoring half of the 50 core outlet thermocouples. The system has separation and redundancy as well as qualification to comply with Appendix B of NUREG-0737 (see the discussion of item (4) below).
Core Cooling Manitor The core cooling monitor portion of ICC system compares core outlet thermocouple temperatures, hot and cold leg RTD temperatures with the saturation temperature based on the lowest of three pressure signals. This system has separation and redundancy as well as qualification to comply with Appendix B of NlREG-0737 (see the discussion of item (4) below).
The thermocouple / core cooling monitor is designed to give an early warning to the plant personnel that core conditions are approaching a saturation condition.
i The thermocouple / core cooling monitor combine s the functions of monitoring for excessive core exit thermocouple temperatures and monitoring both core exit thermocouple temperatures and hot and cold leg RTD temperatures for saturation margin (Tsat meter).
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.. Page Four The system consists of two redundant chan,els each monitoring hs1f of the < ! outlet thermocouples, and fou
- hot and cold leg RTDs.
Three t stor pressure input signals are Jsed with the auctioneered low pressura used by the microprocessor to perform the Tsat margin function. Tne thermocouple temperatures are corrected for reference jun' M on temperature with three reference junction temperature
,r.als input to each channel. (All of the thermocoupias connected to one channel are from one reference junction unit).
The systems two redundant trains utilize the following safaty-grade equipment:
(a)Thermocouples (b) Reference junctiri boxes (c) RTDs (d) Termination board assemblies (e) Microprocessor assemblies (f) Remote displays (g) Analog meters (h) Recorders (i) Power supplies (j) Connections and cabling The equipment listed abcve and shown in Figure 18.2-3 has been designed to satisfy the requirements of IEEE Standard 279. This safety-grade system is isolated from the non-Class lE plant com-puter, technical support center, and data links by qualified isolation devices.
The system can display individual thermocouple temperatures and provides two levels of alarm when preset temperatures are exceeded.
The display is a alphanumeric panel digital display with eight lines of thirty-two characters each located at the processing cabinets, behind the main control board.
The thermocouple monitor can calculate and display core outlet tem-perature quadrant tilts based on thermocouple temperatures. The tilts calculated by each unit are based on half the total number of core thermocouples. This information is also availab?e to the gerator at the main control board via the plant computer.
Page Five The core cooling monitor compares core outlet thermocouple tempera-tures, hot leg, and cold leg RTD temperatures with the saturation temperature based on the lowest of three pressure signals. Two levels of alarm are provided for the core cooling (Tsat) monitor function. The margin to saturation is displayed on two redundant analog meters on the vertical section of the main control board and are visible to an operator at the control console.
The thermocouple / core ccoling monitor provides information to the operator that assists in the perfor#cce of the required manual safety furci .ons following a Condition II, III or IV event. This includes information relative to maintaining the plant in a safe shutdown condition or to proceed to a cold shutdown condition consistent with the Technical Specification limits.
Addit . anal information concerning the thermocouple / core cooling monitor system is provided in Table 18.b3.
(2) Reference 7 provides a design analysis and evaluation of the instrumentation for detection of inadequate core cooling (ICC).
(3) Additiond Msting of the equipment described above is currently in progress in order to est/ Pish and upgrade qualification of the equipment to comply with NlRtu-0737 The test programs are:
(a) Qualification tests of core exit thermocouples (b) Qualification tests of temperature compensat*- hnction boxes (c) Qualification tests of electronics to add t( system computer and technical support center isolak as F . processors (d) Any analysis and/or tests needed to justi>y qualification of modif'ed equipment (such as seismic ano.ysis of cabinets used to housa electronics).
(4) An evaluation of the conformance of the reactor vessel level instru-mentation system to NLREG-0737 is provided in Reference 7.
An evaluation of the conformMce of the thermocouple / core cooling monitor system to NUREG-0737 (Attachment 1 and Appendix B) is as follows:
(a) Attachment 1, Item (1)
- The core exit thermocouples are being qualified so as to comply with the recommendations of Regulatory Guides 1.89 and 1.100. The thermocouples are located at the core exit and in an arrangement
- Page Six such that each of the redundant microprocessor systems has core exit temperatures distributed over the entire core, in sufficient number to determine the radial power distribution and so located as to verify power distribution symmetry among core quadrants.
(b) Attachment 1, Item (2)
The primary operator display is a computer based display and calculation system. It provides information as required by
) subitems (a) through (f).
(c) Attachment 1, Item (3)
The back-up system to display thermocouple readings is located in a cabinet which also houses the core cooling monitor. This system has a 40-character (alphanumeric) display line located on the front of each of the microprocessor drawers. This back-up system can display all of the 50 individual thermocouple temperatyreswithfn6 minutes. The range extends from less than 200 to 2300 F.
(d) Attachment 1, Item (4)
Human-factors consideration of the types and locations of dis-plays and alarms is discussed in Sections 18.1.16 and 18.3.2.
The ICC instrumentation will be considered in the overall human factors evaluation.
(e) Attachment 1, Item (5)
Conformance to the specific items of Appendix B to NUREG-0737 is as follows:
(1) Appendix B, Item (1)
The thermocouple / core cooling monitor instrumentation is currently being tested to establish environmental qualifica-tion in accordance with Regulatory Guide 1.89 (NUREG-0588).
This qualification requirement applies to the complete instrumentation chanr.el from thermocouple to display where display indicates the remote display, analog meter, and recorder. Qualified channel isolation devices isolate this qualified instrumentation from the data links, technical support center display, c9d plant computer display.
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The seismic portion of the environmental qualification test-ing is being performed to comply with Regulatory Guide 1.100.
This seismic qualification will provide assurance that the instrumentation will continue to read within the required accuracy following, but not necessarily during, a safe shut-down earthquake.
- Page Seven Instrumentation, whose ranges are required to extend beyond those ranges calculated in the most severe design basis accident eveat for a given variable, will be qualified using the following criteria.
The qualification environment will be based on the design basis accident events, except the assumed maximum of the value of the monitored variable will be the value equal to the maximum range for the variable. The monitored variable will be assumed to approach this peak by extrapolating the most severe initial ramp associated with the design basis accident events. The decay for this variable will be con-sidered proportional to the decay for tr.is variable assoc-iated with the design basis accident events. No additional qualification margin needs to be added to the extended range variable. All environmental envelopes except that pertain-ing to the variable measured by the information display channel will be those associated with the design basis accident events.
The abave environmental qualification requirement does not account for steady-state elevated levels that may occur in other environmental parameters associated with the extended range variables. For example, a sensor measuring contain-ment pressure must be qualified for the measured process variable range, but the corresponding ambient temperature is not mechanistically . linked to that pressure. Rather, the ambient temperature value is the bounding value for design basis accident events analyzed in Chapter 15.0. The extended range requirement is to ensure that the equipment will con-tinue to provide information should conditions degrade beyond those postulated in the safety analysis. Since variable ranges are nonmechanistically determined, extension of assoc-iated parameter levels is not justifiable and has, therefore, not been required.
(2) Appendix B, item (2) l The purpose for qualifying the thermocouple / core cooling l
monitoring system is to generate evidence that the equip-ment will maintain and perform its functions during a design basis event. It is of special concern during the qualifica-tion effort to uncover common mode failures.
l The single-failure criteria for the computer and information beyond the isolator does not apply to this data based infor-l mation device as referred to in NUREG-0737 (clarification
! item (8)). In relation to diversification, the use of reactor vessel level instrumentation adds diversification to the ICC instrumentat ion. Inclusion of the core cooling (Tsat margin) monitoring functions enhances even further the capability of the SNUPPS ICC instrumentation.
1 Paga Eight (3) Appendix B, Item (3)
The instrumentation is energized from Class lE power sources.
(4) Appendix B, Item (4)
All of the ICC instrumentation complies with IEEE Stand.'r0 279. The systems utilize two trains, therefore, the
" Exemption" as defined in Paragraph 4.11 of IEEE Standard 279 is applicable here.
(5) Appendix B, Item (5)
The ICC equipment falls under the quality assurance require-ments applicable to Class IE equipment. Refer to Appendix 3A for a discussion of the quality assurance regulatory guides.
(6) Appendix B, Item (6)
A digital (40-character) line display is provided for the thermocouple readings in the back-up system. The computer based (primary) thermocouple indication system has contin-uous (recording) displays.
(7) Appendix B, Item (7)
The back-up Class Ir. system (which is on demand) includes redundant recorders. The computer based (primary) inaication system has continuous (recording) displays.
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! (8) Appendix B, Item (8) i The instruments are specifically identified on the control l
panels so that the operator can easily discern that they are intended for use under accident conditions.
l (9) Appendix B, Item (9) l l The SNUPPS ICC instrumentation complies with isolation j requirements.
(10) Appendix B, Item (10)
The SNUPPS ICC instrumentation is testable as required.
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(11) Appendix B, Item (11)
Servicing, testing, and calibrating programs are specified l
to maintain the capability of the monitoring instrumentation.
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- Page Nine (12) Appendix B, Item (12)
The access to the thermocouple / core cooling monitor permits removing channels for service (location is a main. control room). The testing and/or maintenance is facilitated by this system location.
(13) Appendix B. Item (13)
The design facilitates administrative control of tha access to all setpoint adjustments, module calibration adjustments, and test points.
l (14) Appendix 3, Item (14) 8 The monitoring instrumentation design, mir:imizes the dev-elopment cf canditions that would cause meters, annunciators, i rec.arders, alarms, etc., to give snomalous indicatiori potentially confusir.g to the operator.
(15) Appendix 3, Item (15)
The instrumentation is designed to f acilitate the recognition, location, replacement, repair, or adjustment of malfunction-ing components or modules.
(16) Appendix B, Item (16)
The instrumentation used in both the reactor vessel level instrumentation system and thermocouple monitoring receives input signals directly from the sensors that measure the para-meters. The core cooling monitor also derives most of the j signals directly from the sensors except in the case where l
Tsat, pressures and others are obtained from the protection set.
(17) Appendix B, Item (17)
The instruments used for ICC instrumentation are aho used, with the exception of the reactor vessel level indication, for monitoring normal operation of the plant to the extent i that it is practical. No loss of sensitivity is expected due to this use.
(18) Appendix B, Item (18)
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Periodic testing is in accordance with the applicable portions of Regulatory Guide 1.118.
! (f) Attachment 1, Item (6)
The instrumentation system power supplies, separation, etc.,
are in conformance with this requirement.
. Page Ten (g) Attachment 1, Item (7)
The instrumentation qualification is discussed in item (4), e.1 above. -
(h) Attachment 1, Itea (8)
The instrumentation system is in conformance with this require-ment.
(1) Attachment 1, Item (9)
Quality assurance is discussed in item (4).e.5 above.
(5) The ICC instrumentation can perform its functions independent of
- the plant computer.
(6) The ICC instrumentation will be installed by fuel load.
(7) and (8) The Westinghouse Owners Group has developed ICC operating guidelines. These guidelir.cs were developed using the generic ICC analyses discussed in Section 18.1.8. These ganeric guidelines will be considered, as appropriate, by the SNUPPS utilities in s developing plant specific operating procedures.
(9) No additional submittals are required with the exception of emer-gency operating procedures discussed in Sections 18.1.8 and 18.1.15.
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Add to Reference section i-
) 7. Letter NS-TMA-2357, dated December 23, 1980, T. M. Anderson ,
, (Westinghouse) to D. G. Eisenhut (NRC). j i
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SNUPPS TABLE 18.2-3 DETAILS FOR THE THEPF.0 COUPLE /00RE 000LIlC l0;;ITOR SYSTEM Display Information Displayed (T-Tsat, Tsat, P-Psat subcooled-Press, etc.) T-T sat - superheated Display Type (analog, digital, CRT) Analog (control board) and digital (electronics package)
Continuous or on Demand Continuous (control board) and on demand (electronics package)
Single or Redundant Display Redundant Location of Display Control board and control room Alarms (include set points) Caution: 25 F subcooled for RTD 15 F subcooled for T/C Alarm: of subcooled for RTD and T/C Overall uncertainty (F, psi) Digital: 4 F for T/C, 3F for RTD Analog: 5 F for T/C, 5F for RTD Range of Display Calibrated: 1000 psi subcooled to 2000 F super-heat overall: Never off scale Qualifications (seismic, environ-- Seismic and environmental mental, IEEE 323)
Calculator i.
Type (process computer, dedicated Dedicated digital digital or analog calc.)
If process computer is used specify NA availability (percent of time)
Single or redundant calculators Redundant
_____- ___ ___ _ _ _ _ ______ _ _ _ _ _ J
- SNUPPS 9
TABLE 18.2-3 (Sheet 2)
Selection Logic (highest T., Auctioneered at high hot lowest press) leg RTD or average incore thermocouple. -Auctioneered low reactor coolant pre?sure Qualifications (seismic, environ- Seismic and environmental mental, IEEE 323)
Calculational Technical (steam Functional fit - ambient to tables, functional fit, ranges) critical point Input Temperature (RTDs or T/Cs) RTDs, T/Cs, and Tref RTDs - 2 hot leg and 2 cold Temperature (number of sensors and locations) leg / channel T/Cs - 25 per channel Range of temperature sensors RTDs 700 F T/cs 1650 F Calibration unit ran;e 2300 F Uncertainty
- of temperature sensors See WCAP 8587 (F at 1)
Qualifications (seismic, environ-- . Seismic and environmental menta'. IEEE 323)
Pressure (specify instrument used) Barton DP Cell 2 wide range - RCS loop Pressure (number of sensors and 1 narrow range - pressurizer i locations)
Range of pressure sensors Wide range 0-3000 psi narrow range 1700-2500 psi Uncertainty
- of pressure sensors See WCAP 8587 (psi at 1)
Qualifications (seismic, environ- Seismic and environmental mental, IEEE 323)
- Uncertainties must address conditions of forced flow and natural circulation.
Rev. 5 7/81
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< l SPARE HEAD PENETRATION i
OUTLET - m OUTLET x w *y WIDE RANGE P OP b A P, N CORE 7 MOVABLE DETECTOR CONDUlT TRAIN A TRAIN 8 s Rev. 6 S/B1 SNUPPS FIGURE 18.2 2 REACTOR VESSEL LEVEL INSTRUMENTATION SYSTEM l _ _.. _ -. . _ _ _ ___ . _ _ - _ __ -- . . - . _ _. - - -_
a e
annuncij, tor outputs TECHNICAL SUPPORT E DEM CENTER
, REFERENCE ED sioA -
TERMINATION
/C 1/C Siena11 BOARD ASSEE LY ~
E DEM PLANT COMPUTER two T-hot temp signals - : ,
two T-cold tem sigul: -
P1 & P2 -
RENTE DISPLAY P3 ,
I 120 vac ANALOG METER MICRO-PROCESSOR ASSEMBLY 120 vac j -
RECORDER
- 120 vac TMI:: A -
TRAIN B annuncij, tor outputs TECHNICAL SUPPORT REFERENCE E D Si""*lh -
TERMINATION
/C BO T/C 51ona11 BOARD ASSEMBLY ~
E DEM PLANT COMPUTER two T-hot temp signals -
two T-cold temp signal: -
P1 & P2 REMOTE DISPLAY P3 I
120 vac
. ANALOG METER MICRO-PROCESSOR ASSEMBLY RECORDER 1
s tes.
5 120 vac - j 120 vac
- 1. P1 and P2 are wide range loop pressures
- 2. P3 is a narrow rance pressurizer pressure
- 3. Material type for T/C is shown below. Type K extension wire size is 22 awg chrome 1/alumel wire.
SNUPPS
& chromel FIGURE 18.2-3 T/C) a alinel
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