ML18087A882
| ML18087A882 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/22/1983 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.F.2, TASK-TM GL-82-28, NUDOCS 8305050013 | |
| Download: ML18087A882 (27) | |
Text
PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department April 22, 1983 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing
Dear Mr. Varga:
REACTOR VESSEL LEVEL INSTRUMENTATION TMI ACTION ITEM II.F.2 SALEM GENERATING STATION UNITS NO. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 PSE&G hereby submits its response to Generic Letter 82-28 con-cerning Inadequate Core Cooling (ICC) Instrumentation System.
This transmittal also addresses items contained in your letter to Mr. R. A. Uderitz, dated April 4, 1982.
- 1.
PSE&G is using the Westinghouse Reactor Vessel Level Instrumentation System (RVLIS), described in our previous submittals of December 31, 1980, February 6, 1981, and December 7, 1981.
The RVLIS has been installed in Unit l; installation in Unit 2 is 85% complete and will be fin-ished by the end of the current outage. presents the information requested in Mr. Varga's letter of April 4, 1982.
This information follows the format listed on pages 113 and 114 of NUREG/CR-2628.
A proposed Technical Specification for the use and maintenance of the ICC equipment is being prepared for submittal to the NRC in the. near ~uture.
- 2.
The core-exit thermocouples were installed as described in our previous submittals. For subcooling margin monitoring, PSE&G is using reactor coolant differential pressure
( L'i.PSAT) and differential temperature (6 TSAT) instrumenta-
- /
t ion.
The pressure transmitters for @SAT have been A 0 '{ b changed to Rosemount 1153GD9's in Unit 1 and are being
~
changed in Unit *-2.
In addition the 6.TSAT-6.PSAT recorders are relocated to the control console and are no longer dedicated recorders.
The balance of the information is unchanged from our previous submittals.
___ Thi:> l=nt:lrf"I\\/ Pcl"\\Y'\\lc_.
8305050013 830422 PDR ADOCK 05000272 P
PDR 95-21 68 (80 M) 11-82
Mr. Steven A. Varga, Chief U.S. Nuclear Regulatory Commission 2 -
- 3.
All information currently unavailable requires Westinghouse input, which is still being developed.
4/22/83 Should you have any questions in this regard, we will be pleased to discuss them with you.
Very truly yours, I,..
/
/
/
--J E'. A. Liden
/Manager -
Nuclear
/
Licensing and Regulation Attachment CC:
Mr. Donald c. Fischer Licensing Project Manager Mr. Leif Norrholm Senior Resident Inspector
STATE OF NEW JERSEY
)
)
COUNTY OF SALEM SS.
COUNTY OF SALEM RICHARD A. UDERITZ, being duly sworn according to law deposes and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our response dated April 22, 1983, to the NRC's Generic Letter 82-28 concerning Inadequate Core Cooling (ICC) Instrumentation System, are true to the best of my knowledge, information and belief.
Subscribed and sworn to before me
, 1983 Nofary Public of New Jersey
ITEM II.F.2 INSTRUMENTATION FOR DETECTION OF INADEQUATE CORE COOLING
RESPONSE
The plant specific items which have been reviewed for Salem Generating Station are as follows:
- 1.
- 2.
Location of the Display System in the Control Room.
Display for the RVLIS is provided on Recorder Panel !RP! and the console Bez.a~ in the Control Room.
For Train A, Monitor LD-3375IB and Recorder LA-3376RB are located on lRPl.
For Train B, Monitor LD-3367IB is located on the control room console.
Also for Train &t wiring has been provided to the Recorder Panel lRPl should recorder selection be required for Train B.
- Also in the Control Room, the Auxiliary Annunciator* provides two alarms.
Point 752 is for the Reactor Level *Train A Failure Alarm, and Point 753 is for the Reactor Level Train. B Failure Alarm.
Integration of the ICC display into console or Rack.
The ICC *displays for Train B are located on the Control Room console at the location designated as lCCl position 2-10.
They are integrated with the controls for the reactor coolant pumps and for the pre~surizer overpressure protection system.
The ICC displays for Train A are located on 1(2)RP1 near Column CC-13.2 above the minimum line of ~ight approximately three feet fro~*the floor.
1 -
- 3.
- 4.
They are integrated with other recorders and displays.
Location of the differential pressure transducers outside containment.
The differential pressure transmitters are located in the electrical penetration area on Elevation 78' at Column CD-10.2.
Transmitters LA-3617Z, LA3619Z, and* LA-3639Z, and tA-3666Z are located in Panel 840-1B(2B)
- Inclusion of hydraulic isolators and..e.ensors in the impulse lines.
The pressure sensing lines connect to six sealed capillary impulse lines (two at the reactor head, two at the seal table, and one at each hot leg) which transmits the pressure measurements to the d/p transmitters located outside the containment
- building.
The capillary impulse lines are sealed at the RCS end with a sensor bellows which serves as a hydraulic cou*pling for the pressure measurement.
The impulse lines extend from the sensor bellows through the containment wall to hydraulic isolators, which also provide. hydraulic coupling ~s well as a seal and isolation of the lines.
The capillary tubing extends from the hydraulic isolators to the d/p transmitters, where instrument valves are provided for isolation and by paSSe 2
ITEMS LISTED IN NUREG-0737, II.F.2 (APPENDIX A, NUREG/CR-2628) HAVE BEEN REVIEWED ON A PLANT SPECIFIC BASIS
RESPONSE
- 1.
l.a Description of display or deviations of instrumentation from generic descriptio~s. in this document.
The deviation of display from NUREG/CR-2628 Section II.C.2.a.4.a entitled:
"Plant operator interface and displays" is as -f01.lows:
There are three display sheets for reactor vessel level:
The first is a summary sheet, the second is a trending of the three**vessel level indications over a 1-hour period, and the third is a sensor status sheet which indicates which
. sensors are out of range or off scale
- The third display.sheet which is for sensor status is not identified in this NUREG Section.
The sensor status display for the vessel level monitor is shown in Figure 1-12.
Out of Range Inputs -
The control board display will indicate an out-of-range or limit of motion condition when the inputs reach the following setpoints:
Hydraulic Isolator (Limit of Motion) -
Later Impulse Line (out of range) 4SOO< T< 320F.
RCS THOT (out of range) 7000< TH< 500F RCS Pressure (out of range) 3000-psig < PWR < O
. psig Out of range inputs also were not identified in this NUREG Section.
l.b. Description of Existing Instrumentation Systems.
For a description of the subcooling meter, see the attached response to Section 2.1.3.b of NUREG 0578.
For a description of the in-core Thermocouple System, s"ee response to Attachment 1 of II.F.2.
These descriptions are part of a previous submattal.
3 -
. 2.
l.c. No modifications are planned for the
- instrumentation systems described in l.b.
A design analysis and evaluation of ICC detection instrumentation.
Any deviations from generic descriptions in this document, or from instruments tested by the Westinghouse testing program.
The design analysis for Salem Generating Station is in agreement with Section III of NUREG/CR-2628 entitled, "Description of Level Systems Tests and Analysis." The evaluation of ICC detection instrumentation is an agreemen~.with Section IV entitled:
"Evaluation of the ~ffferential Pr~ssure System."
Deviations of instrumentation - The only deviation from NUREG/CR-2628 is that.RTD sensors are not installed on every independently run vertical section of impulse line. Also, if the vertical
- section of impulse line runs through two compartments separated by a solid floor, an RTD sensor is not installed in each compartment.
The reason for this is that the microprocessing unit is c~pable of handling only 8 imputs per channel.
Location of the RTD sensors are shown on Figures 1-13 and 1-14 as per Westinghouse re.commendation.
See Tables 1-13 and 1-14 for RTD Elevations.
Additional indication for hydraulic isolator status is provided in Panels 841-lA and 841-lB.
Indication is as follows:
RX Head Low Fluid, RX Head High Fluid, RX Head Normal, Hot Leg Low Fluid, Hot Leg High Fluid, Hot Leg Normal, Seal Table Low Fluid, Seal Table High Fluid,. and Seal Table Normal.
Input is provided to the microprocessor unit for each high level condition.
This indication provides additional integrity to the RVLIS System.
- 3.
Additional Testing Programs, including qualification tests planned.
4 -
Testing programs, additional to those in Section III of NUREG/CR-2628 are not planned.
- 4.
Evaluation of conformance with NUREG-0737:II.F.2, and Appendix B.
For evaluation of conformance with Attachment 1, see response to NUREG-0737:IIF.2, Attachment 1.
For conformance to Appendix._ B, se*e Response to NUREG-0737.II.F.2, Appendix B.
The ICC monitoring system conforms to Appendix A references, "NUREG 0578, Recommendation 2.1.3.b",
an_d the letter from H. R. Denton, NRC, to All Operation Power Plants, dated October 30, 1979, subject:
Discussion of Lessons Learned - Rhort Term Requirements" except that the in-core thermocouple temperature measurement system is not environmentally qualified and does not meet all
_the requirements of II.F.2 Attachment No. 1 (See
- 1. 1
- b above )
- No modifications are presently planned as indicated in 1.1.c above.
The justification for continued use of the in-core thermocouple are as follows:
- Current procedures instruct the operator to monitor the in-core thermocouples as a guide to determining the existence of adequate core cooling.
Westinghouse information and operating history of these devices indicate that they would fun~tion. If these devices were to fail, backup parameters, such as, RCS pressure and temperature, steam generator level, and auxiliary feedwater flow are available to enable determination of adequate core cooling.
These backup devices are qualified and are described in the procedure which also alerts the operator to potential errors in the in-core temperature readings
- 5
The existing procedure and availability of
- alternate indications is sufficient to ensure proper determination of core cooling adequacy.
- 5.
Description of computer, software and display function in plant.
The description of the RVLIS computer at Salem is an agreement with NUREG/CR-2628.
- See Westinghouse* instruction manual for the Vessel Level Monitoring System (Micro Processor) Manual
~
No. 9002-VLM-OOO.
Other specific information is as follows:
Hot Leg Temperature -
New wide range temperature sensors (qualified) will be used at Salem.
These Conax RTD's will be installed during 5th refueling on Unit 1 and 1st refueling on Unit 2.
Existing Rosemount RTD's have been replaced in each refueling outage *.
Wide Range Reactor.Coolant Pressure - Existing qualified pressure* sensors are used to measure reactor coolant pressure.
Alarms - Train A or Train B failure ala~ms on the Auxiliary Annunciator located in the control Room.
A general alarm is provided on the overhead annunciator.
Location -
The microprocessor unit is located in the adjacent relay.room in Panel 842-1.
A de~cription of the computer functions for in-core thermocouples and subcooling meters are described in II.F.2., and the attached response to Section 2.1.3.b of* NUREG 0578, respectively, which have been submitted previously.
- 6.
Schedule for installation, testing and calibration.
Installation, testing and calibration has been performed on Unit 1 during the 4th refueling 6 -
- 7.
outage ending 1/31/83.
On Unit 2, the 1st refueling is scheduled from January 22, 1983, to the end of May 1983, at which time the system will be installed, calibrated, and tested.
Guidelines for use of additional instrumentation, and analysis used to develop procedures.
Guidelines for use of additional instrumentation is in agreement with NUREG/CR-2628 Section II.C.2.d entitled:
"Operating Procedures."
Other guidelines can be found in the.following instruction manuals:
(1)
Post Accident Monitoring Recorder -
Manual No. I.B. 104-605 W (2)
Vessel Level Monitoring System (Microprocessor) -
Manual No. :
9002-VLM-000 (preliminary)* W (3)
Model 752 Differential Pressure Electronic Transmitter - Technical Manual (installation and operation) -
Manual No. 79C2 ITT Barton.
(4)
Model 581 Hydraulic Isolator. -
ITT Barton.
( 5.)
Model 353 High Valve Sensor -
ITT Barton.
(6)
Instrument Valves -- 1/4 x 281 - autoclave.
(7)
Test Equipment -
Autoclave.
(8)
Root Valves -- 3/4 T78 -
Rockwell -
Edwardo Analysis used to develop procedures is in agreement with NUREG/CR-2628,Section III.B., entitled: "Analysis of Performance."
It is also in agreement with Section IV.B., entitled1 "Application of Instrumentation Considerations."
For the open items in Section IV.B., Refer to the following items:
(1)
Normal maintenance and recalibration schedules - calibration checks are to be 7 -
performed monthly of the process electronics in accordance with the process. equipment instruction manual.
(2)
Interference with Refueling - Potential problems that might exist with respect to the disconnect and refilling the lines -
See Response to items required in NUREG-0737, Apendix B, Item No. 11 *. -
(3)
Sensor and transducer specific considerations Expected in-service life.
This is an agreement with Westinghouse*'"s response stated in Secti6n IV.D.36, entitled:
"Normal In-Service Life."
- 8.
Operator instructions in emergency operating procedures for lCC.
_The emergency oper.~ting procedures are being modified ba~ed upon input from the owner's group.
The operating department is in the process of updating the plant *specific Emergency Operating Procedures.
- 9.
Schedules for Additional Submittals Required.
Additional submittals will be made when the additional information is developed.
8 -
VESSEL LEVEL SENSOR Off SCALE DP No.
DP 1
RTD 7
1 STATUS DISABLED DP No.
RTD4 I
I..
1 I
Figure 1-12 Typical Vessel Level Sensor Status Display
, I I '.
,1
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10 -
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- 12.
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- TRA\\N B-CHAN* D 13 -
IIF.2, Attachment 1 This is an evaluation of conformance of the ICC instrument system to "II.F.2 Attachment l" entitled, "Design and Qualification Criteria for Pressurized-Water Reactor Incore Thermocouples."
This item has been responded to previously.
The following paragraph numbers correspond to the paragraph numbers of 'Attachment 1:
- 1.
There are 65 in-core thermocouples, with a minimum of eleven in each quadrant and an adgitional.eight thermocouples shared with the two adjoining quadrant, to provide indication of radial distribution of temperature
~
rise across representative regions of the core.
See FSAR, Section 7.6.
- 2.
Primary Operator displays A.
A core map for each quarter of the core is available to the operator on demand on the computer output CRT.
The core map gives the
_temperature at eac.h core exit thermocouple location in.that quarter of the core.
B.
The core map will give the location of the hottest in-core thermocouple.
This hottest in-core thermocouple reading is the basis for the subcooling calculations and procedures *.
- c.
There is direct read-out and hard copy capability for all thermocouple temperatures.
The range extends from JOOF to 22000F.
D.
Trend capability f.or the thermocouples is available on demand on the Trend Typewriter located on the operator's console.
E.
Alarm capability is provided consistent with operator procedure requirements:
When-~eactor power <0.25% alarm at 120F~ when reactor power>.025% alarm at 6300F.
F.
The operator-display device is human-factor designed as noted in Essex Corp. Review of February, 1980.
- 3.
A backup display is available, but it does not meet the stated requirements as follows:
14 -
All thermocouples may be read, but only one at a time.
The range is 370-4000 or 6700-7000F and not required 2QQOF to 23QOOF.
The read-out meter on the flux mapping panel is located in a room adjacent to the control room and may not allow the operator to read 16 thermocouples within a time interval of less than 6 minutes.
The backup display is not referenced in the emergency procedures.
- 4.
A primary display CRT is located on the control console.
The hard copy and trend displays are located on the operator's computer console which is located directly behind the operator.
5 *
- 6.
The instrumentation does not meet Appendix B, "Design and Qualification Criteria for Accident Monitoring Instrumentation." See Item 6-9 below* *. ***
The primary display channel utilizes the station computer which is energized from an uninterruptible power supply.
The primary CRT display and operators console which supplies direct digital readout and trend capability are also energized from the same power supply.
The primary display channel and associated hardware are not Class lE.
The backup display is supplied from redundant station power sources.
The backup display and hardware are not Class lE.
The reference junction heater power is derived from the same ~ource as the backup display.
- 7.
The in-core thermocouples, their electrical connectors and reference junction boxes are not environmentally qualified as required in Apendix B, Item 1.
The computer ~nd display have not been environmentally qualified or seismically qualified.
- 8.
The primary display channel uses a computer ~ith an estimated reliability of 98 -
99%.
The overall primary display channel reliability is 90 -
95%.
There is no reliability figure available for the backup display.
- 9.
The in-core thermocouples are not purchased to the stated Q.A. requirements.
JEF:dh 15 -
ALL ITEMS REQUIRED IN NUREG-0737, APPENDIX B, HAVE BEEN REVIEWED ON A PLANT SPECIFIC BASIS AS FOLLOWS:
- 1.
- 2.
ENVIRONMENTAL QUALIFICATION All equipment specified by Westinghouse for the RVLIS
- System has been used for the Salem Plant.
- It is environmentally qualified in agreement with the codes and standards listed in Section IV, A.l of NUREG/CR-2628.
SINGLE FAILURE ANALYSIS Redundancy is provided by dual instrument trains in the system in agreement with Section IV A.2. of NUREG/CR-2628
- 3.
CLASS lE POWER SOURCE Class lE Power Source is provided.
- 4.
AVAILABILITY PRIOR TO AN ACCIDENT The RVLIS System has readouts during normal operation.
- 5.
QUALITY ASSURANCE PROCEDURES Information is not available at this time.
- 6.
CONTINUOUS INDICATIONS Continuous indication is provided.
16 -
- 7.
RECORDING OF INSTRUMENT OUTPUTS
- 8.
- 9.
A recorder is provided for logging on one Train (which may be selected) in agreement with Section IV A.7.of NUREG/CR-2628 IDENTIFICATION OF INSTRUMENTS Displays are provided for each train.
ISOLATION Isolation of signal channels is provided.
- 10. IN-LINE CHECKING Information is not available at this time.
- 11. SERVICING, TESTING, AND CALIBRATION PROCEDURES Information is not available at this time.
Ii. ADMINISTRATOR CONTROL OF REMOVAL FROM SERVICE Information is not available at this time.
- 13. ADMINISTRATIVE CONTROL OF ACCESS TO SET POINT, CALIBRATION ADJUSTMENTS.
Transmitters are located outside the containment.
Check and test points are readily accessible
- 17 -
- 14. UNAMBIGUOUS INDICATIONS
. This is an agreement with Section IV A.14.
- 15. IDENTIFICATION OF MALFUNCTIONING COMPONENTS OR MODULES Information is not available at this time.
- 16. DIRECT MEASUREMENT OF PLANT VARIABLES.
This is in agreement with Section IV A.16.
17 SAME INSTRUMENTS USED FOR ACCIDENT MONITORING AS FOR NORMAL OPERATION (TO THE EXTENT PRACTICAL)
Information is not available at this time.
- 18. PERIODIC TESTING.
Information is not available at this time
- 18
ATTACHMENT 1 Page 1 of 6 Instrumentation for Detection of Inadequate Core Cooling in PWRs and BWRs (Section 2.1.3.b)
NRC Position
- 1.
Licensees shall develop procedures to be used by the operator to recognize inadequate core cooling with cur-rently available instrumentation.
The licensee shall provide a description of the existing instrumentation for the operators to use to recognize these conditions.
A detailed description of the analyses needed to form the basis for operator training and procedure develop-ment shall be provided pursuant to another short-term requirement, "Analysis of Off-Normal Conditions, Includ-ing Natural Circulation" (see Section 2.l.9)o In addition, each PWR shall install a primary coolant saturation meter to provide on-line indication of cool-ant saturation and condition. **operator instruction as to use of this meter shall include consideration that is not to be used exclusive of other related plant para-
- meters.
- 2.
Licensees shall provi~e a description of any additional instrumentation or controls (primary or backup) proposed for the plant to supplement those devices cited in the
- preceding section giving an unambiguous, easy-to-inter-pret indication of inadequate core cooling. *A descrip-tion 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.
- Response The existing instrumentation available.in the Control Room is sufficient to recognize inadequate core co6ling. The*
indications available for determination of core heat removal are:
- a.
RCS delta T less than full load delta T.
- b.
RCS or core exit thermocouple temperatures constant or decreasing.
ATTACHMENT 1 Page 2 of 6
- c.
Stearn generator press~re constant or decreasing at a rate equivalent to the rate of decrease of RCS tempera-
.tures while maintaining steam generator level with
- continuous auxiliary feedwater.
A further guide for recognition of inadequate core cooling is the recent addition *of a computer/CRT display for sub-
~ooling.
The significant parameters which are continuously displayed are reactor coolant differential pressure (P act-ual ~ P saturated) and differential temperature (T saturated
- Tactual).
Alarms are set for pressure differential less than 200.psi and temperatur~ differential less than SQOF.
The computer program is pred~cated on the hottest in-core thermocouple reading.
The CRT matrix of in-core thermo-
- couples will display the location of the hottest in-core thermocouple.
A recorder has been provided at the control console to record differential pressure and temperature.
Additional information is provided in Table 2.1.3.b-l.
Emergency Procedures, EI 4.4, "LOCA", and EI 4.6, "loss of Secondary Coolant," have been revised to ~ddress the use of this computer program to monitor the margin of subcooling in the Reactor Coolant System.
PSE&G is a member of the Westinghouse Operating Plant Owners' Group~
Westinghouse, under the direction of the Westinghouse Owners Group, is. performing further analyses to aid in selection of more direct indicators of inadequate
ATTACHMENT 1 Page 3 of 6 core cooling, and to serve as a basis for augmented emer-gency procedures.
A preliminary report on inadequate core cooling was sub-mitted to the NRC on October 30, 1979 by the Owners' Group..
The Salem 2 Emergency Procedures will be revised on an interim basis to specify precautions and operator actions to "tecover from a condition in which the core has experienced inadequate cooling.
These interim revisions will be avail-able for NRC review prior to power testing.
The station procedures will be further updated after completion of the final *Owners* Group report *..
It is our intent to install a device to indicate reactor vessel water level on Salem 2.
This device will be similar to the proposed Westinghouse design for VEPCO's North Anna plant.
Installation of this device will be accomplished during the first refueling outage subject to equipment availability ~nd acceptability of the design to provide an unambiguous indication of inadequate cor*e cooling.
~*.
ATTACHMENT 1 TABLE 2. 1. 3
- b-1
.SUBccx::>LING METER INFORMATION Display Information Displayed (T-Tsat, Tsat, Press, etc.)
Display Type (Analog, Digital, CR!')
- Continu6us or on Demand Single or Redundant Display er.
location of Display Ala:ans (include set:p::>ints)
Overall uncertainty ( °F, PSI)
Range of Display Qualifications (seismic, enyironmantal, IEEE323)
Calculator
!YPe (process ccmputer, dedicated digital or analog calc. )
If process canputer is used specify avail ability. (% of time)
Single or redundant calculators Selection Logic (highest T., lowest press)
Qualifications (seismic, environmental, IEEE323)
Calculational Technique (Steam Tables, Functional Fit, ranges)
Input Temperature (RTD's or T/C's)
Temperature (number of sensors and location$)
Range of temperature sensors Page 4 of 6 Note 1 CRT and Analog Pen Recorder Note 1 Note 2 Note 3 Note 4 Note 5 Note 6 None Process eanputer (Note 8) 90%-95% (Estimated)
Single Note 7 None Steam Tables (Note 9) 32<°F<705 12_g>sia<3204 Chranel/Alumel T/C 65 Incore T/C's 3Q-2200°F
ATTACHMENT 1 TABLE 2.1. 3.b-1 (CONTINUED)
Uncertainty* of temperature sensors (°F at 1)
Qualifications (seismic, environmental, IEEE323)
Pressure (specify instrument used).
Pressure (number of sensors and locations)
Range of Pressure sensors.
Page 5 of 6
~ 5op None Rosemount 1153GD9 2-#11 Hot leg 0-3000 psig
+130 psi (Small
-::uncertainty* of pressure sensors (PSI at 1)
-. ~
- Break Conditions)
Qualifications (seismic, environmental, IEEE323)
Backup capability Availability of Temp & Press Availability of Steam Tables etc.
Training of c:perators.
Procedures Qualified, Safety Grade Main Console Indica-tion
.conversion Curves Ccmpleted Ccmpleted
- Uncertainties are not affected by differences in RCS flCM conditions.
The:rrnocouples are located in hottest regions and pressure neasurement is independent of flCM conditionso Notes
- 1. Continuous information displayed on analog pen recorder:
(Tsat-Tact>r (Pact-Psat>*
Infonnation available on demand:
(Tsat-Tact>, (Pact-Psat), Psatr Pressure.
Temperature and location of hottest in-core T/C.
- 2.
The information available on demand can be displayed on the CRT or trend typewriter.
L*.
Notes ATTACHMENT 1 TABLE 2. 1. 3
- b-1 (CONTINUED)
Page 6 of 6
- 3.
The CRT is located on the center-left portion of the main control
- console.
The other displays are available at the operator's can-puter console.
4 *. Alarms:
(Tsat-Tact) - less than 50°F subcooling (P-Psat) - less than 200 psi Temp. - any T/C greater than 630°F t
If these alanns occur, they will be displayed even if the subcooling
- calculation program has not been requested by*. the operator.
- 5.
Overall uncertainty is a factor of the uncertainty in the tempera-ture and pressure neasurements and the resulting potential error when using the steam tables. The uncertainties of these devices are listed separately on the table.
- 6. Analog.Ranges:
(Tsat-Tact) ~lectable to 150°F Diff:
(P-Psat) Selectable to 1500 psi Diff:.
CRT Range:
N(A
- 7.
The selection logic used is:
highest in-core T/C reading
- average of two reactor coolant pressures.
The operator is provided with the capability to reject the selected T/C: the next highest reading T/C will then be autanatically se-lected for the calculation.
A reasonability check of the two pressure readings is perfonned by the cx::mputer.
If the readings indicate that one of the :rceasurements is invalid, the canputer will reject the invalid reading.
- 8. The process ccmputer is powered fran a vital bus throogh an inverter with battery backup.
- 9. The subcooling calculations are perfonned on an 8-10 second basis.
' *