ML20079G506
| ML20079G506 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 01/13/1984 |
| From: | STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | |
| Shared Package | |
| ML20079G496 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8401200145 | |
| Download: ML20079G506 (31) | |
Text
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SNUPPS SAFETY ANALYSIS REPORT FOR SAFETY PARAMETER DISPLAY SYSTEM Revision 1 January 13, 1984 8401200145 840113 PDR ADOCK 05000482 F PDR
SAFETY ANALYSIS REPORT FOR SAFETY PARAMETEF[IISPLAY SYSTEM I. Introduction The safety Parameter Display' System (SPDS) conceptual design was previously described in References 1 and 2.
A broader Safety Assessment System (SAS) is being implemented for
~the SNUPPS plants based on a design developed jointly by a group of Westinghouse NSSS utilities of which the SNUPPS Utilities were members. SAS provides a centralized, flexible, computer based data and display system to assist control room personnel in evaluating the safety status of the plant. The highest level graphical displays contain a minimum set of key plant parameters representa-tive of ' the plant safety status and these constitute the SPDS.
There are three of these top level displays for different plant
' operating conditions: 1). Normal Operation, 2) Heatup and Cooldown, and 3) Cold Shutdown. In addition, there are seven Critical Safety Function (CSF) displays,14 trend graph displays, and four Accident Identification Display System (AIDS) displays which complete the
. Safety - Assessment System. All graphical displays are present-ed .to control room personnel on multiple color CRTs. One CRT is normally dedicated to the appropriate top level SPDS display.
All data displayed by the SAS is validated by comparing redundant sensors, checking.the value against reasonable limits, calculating rates of change, and/or checking temperature versus pressure curves. Invalid or suspect data is identified by consistent color and pattern.
All displays of the SAS have been carefully designed by persons with plant operating experience and evaluated against human f actors design criteria. Design and evaluation focused on the fundamental objective of aiding the control room operators in rapidly and reliably assessing the safety status of the plant. No control room displays were superseded by SAS and the Control Room Design Reviews verified suitability of the control room designs without SAS for all normal and accident conditions. Thus,SAS while useful as an operator aid, is never essential for plant operation. The concepts used in the SAS design have been verified using the Indian Point simulator. The intent of the SAS is to present to control room personnel a few easily understandable displays which use color coding and pattern recognition techniques to indicate off-normal values. These displays are updated and validated on an essentially real-time basis.
The SPDS will be operable during normal and abnormal plant operat-
-ing conditions and will operate during all modes of-plant operation.
SPDS maintenance and modifications- will take place as required and will be ' scheduled 'when .possible during .the cold shutdown mode of
. pl ant operation. The - nonnal operation mode will encompass all
. plant. conditions' at or above normal ' operating pressure and tempera-ture, including the initial stages of accidents initiated during nonnal operation. When the reactor coolant system is intentionally cooled below normal- operating _ values, the - operator selects the Heatup-Cooldown mode which alters the limit checking algorithm for the key parameters. An additional mode is also provided to address cold shutdown plant conditions.
II. Parameter' Selection
- The parameters used for SPDS were selected by consensus of member Utilities. A majority of the personnel have had direct operating experience at Westinghouse PWRs.
General constraints and considerations were:
SPDS may be-of use during routine plant operation, but the most benefit will be derived during off-normal or accident conditions to rapidly and reliably determine safety status.
The informatior, presented should provide information to plant operators on reactivity, core cooling, heat removal, reactor coolant -system integrity, radioactivity, coolant inventory, and containnent .
Wide range values should be used wherever possible.
Consideration must be given to both " event" and " function" approaches to procedural interfaces.
Although SPDS may provide information to many people in several locations, the SPDS is primarily for control room operator use.
. Regulatory requirements for the SPDS must be met.
~*
Other, i.e., EPRI/NSAC, Westinghouse, AIF, designs and experi-ence should be reviewed and considered for "do's" and " don'ts".
Human factors considerations must be embodied in the design.
As a result of this process, the key parameters for the top level
-SPDS displays were selected and are presented in Table I. Most are-conventional parameters, but a few are new summary parameters derived _for these displays. All of the parameters that are sent to
'SAS are presented in Table II. Further discussion of the use of these various parameters is presented below.
. .- __ _ _ _ - ~_
'III. Parameter Definition The SPDS database is made up of a number of different components -
direct sensor inputs, derived parameters, and display characteri-
'stics. In order to provide high quality data throughout the
. system, most-of the data used in the SPDS is derived from the sensor inputs. These derived ' data can be further categorized in the following manner:
Safety parameter display system (SPDS) parameters - parameters which define the minimum SPDS per NUREG-0696 (Reference 3).
Refer to note 2 in Table-I.
' *' key parameters - parameters displayed on any of the three top-level displays. Refer to Table I.
Most of the key parameters are directly related to the sensor inputs, however, a few are derived from multiple sensor inputs and defined off-normal'setpoints. Specifically:
containment environment: this is a key parameter chosen to detect changes in the containment based on a number of different sensors.
The components of the containment environment are containment temperature, containment pressure, containment sump level, and containment humidity. In an accident situation all of these parameters should. indicate the same behavior, however, due to instrument sensitivities, locations, inaccuracies, etc., they may not simultaneously indicate off-normal conditions. The combined
" target" parameter indicates off-normal when any one or more of the
. i ndividual parameters is off-normal . When the target indicates off-normal containment conditions, the operator may select the backup trend display or check the control board for further informa-tion.
secondary radiation: for the same reasons as described above, condenser air discharge radiation and steam generator blowdown radiation are conbined to produce this parameter which indicates the radiation " state" in the secondary system.
AIDS bars: the AIDS bars are weighted combinations of the corre-sponding primary AIDS parameters which summarize the degree to which multiple parameters consistantly indicate a particular event.
Other definitions for SAS or SPDS parameter subgroups include:
primary- AIDS parameters (PAPS) - parameters which are positive indicators of an accident and provide unambiguous infonnation that .an accident has occurred and in combination with other key paraneters, will differentiate between the four types of acci-dents. Refer to Table III.
secondary AIDS parameters (SAPS) - parameters which may antici-pate a possible condition, add confirmation to a key parameter's behavior, have low quality, or be a causal condition for a particular accident. In gener'al, this infomation needs to be provided to the operator for evaluation, but may not give (by itself) a clear indication of what is happening. Refer to Table IV.
modifier - a conditional event that alters or qualifies the use of a PAPS or SAPS before the parameter is valid as an accident indicator.
trend parameters - analog parameters whose value is plotted.
Refer to Table V.
critical safety function parameters - parameters used to define the CSF logic. Refer to Table VI.
IV. Comparison of SPDS Parameters With Other Sources
'The SPDS parameter suitability was assessed by reviewing the l
parameter list against other, broader accident parameter lists.
l The SPDS parameters were tested against the broader lists to verify that they were a complete, necessary parameter set for safety status assessment and control room operator integration of support-ing indications. Availability of all accident indications for use in conjunction with SPDS was also verified in these reviews. The i-
[ primary indication for all parameters is the control board and the SPDS is used as an operator aid. Each review is summarized below.
A. NUREG-0696 (Reference 3)
All NUREG-0696 parameters defined in Table I, note 2, are contained in the SPDS top level displays.
B. NSAC 8 (Reference 4)
All NSAC 8 parameters are contained in the SPDS top level displays, except those listed in Table VII. Each of-the exceptions was found to be ' supportive of parameters provided in the SPDS top level displays.
All parameters that are available at the SPDS console are also available through the B0P computer CRT display. A review of the above parameters not included in the top level SPDS displays shows that they are readily available at either the SPDS consoler the 80F computer CRT display, or the Post Accident Sampling System (PASS) printer. All parameters discussed above are also displayed on the control board, with the exception of RHR radioactivity which involves batch sampling.
C. .Westinghouse Owners Group (WOG) Revision 0 High Pressure Emergency Response Guidelines (ERG) (Reference 5)
All WOG ERG parameters are displayed on the top level SPDS
-displays except those listed in Table VIII.
All parameters that are available at the SPDS console are also available through the 80P computer CRT display. All parameters
. discussed above are also displayed on the control board, with the exception of the concainment recirculation sump sampling and the RCS sampling, which involve batch sampling.
' A review of the-above parame?.ers not included in the top level-SPOS shows that they are readily available at either the SPDS console, the 80P computer CRT display, the PASS printer, or the control board. Those parameters displayed only on the control board are:
Control Rod Bottom Lights - light indication is not available in this computer system Pressurizer Heaters - this paraneter indication is not criti-cal in assessing safety status High-Head SI Pump Discharge Pressure - safety injection flow rate is available on the 80P CRT display. Discharge pressure indication is not _ critical in assessing safety status BIT Temperature - the boron concentration is 2000 ppm, there-fore, the temperature is not critical in assessing safety status Boric Acid Tank Temperature - this parameter is not critical in assessing safety status Charging Line Flow Control Valve - not part of the safety injection flowpath and, therefore, not critical in assessing safety status Low Pressure Letdown Control Valve - not part of the safety injection flowpath and, therefore, not . critical in assessing safety status Hydrogen Recombiners - there is sufficient time available in an incident to determine the hydrogen recombiner status lurbine Stop Valves -there are other indicators that are sufficient to assess steam line flow and Lypass of the turbine.
This parameter, in itself, is not critical in assessing safety status Instrumentation for Turbine Runback - these parameters are not critical for assessing safety status L_ .
l As a result of _the above discussion, it is concluded that. parameters defined on the top level SPDS displays are sbfficient to define and assess the overall safety _ status of the plant. The B0P computer system CRT displays along with the PASS printer and SPDS console provide adequate = information -to investigate an incident in detail.
Those parameters found only on the control board have been reviewed I_
and have been ~found to be either not critical in assessing the safety L status, backed up by other parameters that can define the safety status, or not available in this computer based system (i.e., lights)
V. Human Factors Human-f actors engineering and industrial-design techniques have been effectively combined to establish man-machine interface design-requirements, maximize system effectiveness, reduce training and skill demands, and minimize operator error.
The color-graphic CRT formats and functional keyboard designs have
< been developed through an inter-disciplinary tean of senior operati-onal, human f actors, industrial design and computer-interf ace personnel.
Minimum use of color combined with simplified format for all of the CRT displays are key design features to aid both normal and off-normal pattern recognition. The operator, who is the end user, has been directly involved from the conception to ensure that man-machine interf ace goals of SAS have been satisfied. Human f actor engineering standards and testing verification have been used which are consistent with accepted practices.
VI. Summary The -top - level SPDS displays have been reviewed and it has been determined that:
The general constraints for parameter selection have been met.
A comparison with other sources of parameters useful for safety assessment has shown that the SPDS parameters sel-ected are sufficient The SPDS was evaluated at the Indian Point simulator and it was shown that:
The SPDS is a valid tool for operator use Operators use the SPDS differently depending upon their levels of operating experience.
Operators use SPDS differently depending on the event or malfunction in progress Use of the SPDS did not degrade the operators response to transien.ts or incidents
Based on the above conclusions regarding SPDS parameter selection,
, Lcomparison with other sources of parameters, and the Indian Point
- simulator evaluation,'it is concluded that:
The SPDS does not involve an unreviewed safety question
- There is ^ no ' change in the Technical Specifications required
~
' to impicment SPDS,- since the SPDS is only an aid to the control room operator VII. References
- 1. SLNRC 81-042, dated 6/4/81 c2. LSLNRC 83-0019, dated 4/15/83
- 3. NUREG-0696, Functional Criteria'for Emergency Response Facilities
- 4. NSAC-8, Nuclear Plant Safety Parameter Evaluation by Event Tree
. Analysis,.0ctober, 1980 5..
W0G-83-239, Westinghouse Owners Group Procedure Related Submittals to NRC, dated 9/12/83 S 4 n
I' ,
.i: #
TABLE I ,
KEY PARAMETERS AIDS bars l
AIDS targets l 2
RCS pressure Pressurizer level 2 Cold leg temperature (each l'oop)2 Stean generator level (each loop)2 Steam generator pressure (each loop)2 Secondary radiation-(target)I Containment environment (target)l,2 Containment radiation2 2
Reactor vess'el' level ,
- Subcooling 2 I
Core' exit temperature2 ,
Intermediate range startup rate Power' level (source,. intermediate2, and power range2 )
RCS average temperature Residual heat removal system flow (each loop)
Residual heat removal system heat exchanger inlet temperature (each ' loop)
Residual heat removal system heat exchanger outlet temperature (each loop) 1 Message area Date'and time Key events (e.g. time of reactor trip, time of feed' water isolation, time of safety injection actuation, time of steamline isolation) "
Name of plant '.
Operational mode
- 1. -Noted bars and targets are derived parameters, defined in Section III-
- 2. . Minimum parameter set required by NUREG-696 T
'^
TABLE II' SAS DATA LINK PARAMETERS LIST (includes SPDS)
DATA POINT NSSS BOP VALUE ENGR
-VALUE DESCRIPTION INSTRUMENT POINT ID RANGE UNITS 001 PRESSURIZER RC-PD/455A REP 0480A 1700 to 2500 PSIG 002 PRESSURE RC-PD/456 REP 0481A ,-
003 RC-PD/457 REP 0482A 004 RC-PD/458 REP 0483A ,
005 RCS PRESSURE RC-PD/405(WR) REP 0498A 0 to 3000. PSIG 006 RC-PD/403(WR) REP 0499A 007 PRESSURIZER RC-LD/459 RELO480A 0 to 100 PERCENT
! 008 WATER LEVEL RC-LD/460 RELO481A 009 RC-LD/461 RELO482A l
1 ,
l' 010 CORE EXIT LATER RET 0001A 0 to 2300 DEG. F THRU THRU 059 THERMOCOUPLES RET 0050A 060 REACTOR RC-LD/13128 RELO503A 0 to 120 PERCENT 061 VESSEL LEVEL RC-LD/13228 REL0523A 062 CONTAINMENT NONE GNT0060 0 to 400 DEG. F 063 TEMPERATURE GNT0061 064 GNT0062 065 GNT0063 066 CONTAINMENT VS-PD/936 REP 1000A 0 to 69 PSIG 067 PRESSURE VS-PD/935 REP 1001A 068 VS-PD/934 REP 1002A 069 CTMT SUMP A NONE EJLOOO7 0 to 156 INCHES 070 CTMT SUMP B EJL0008
TABLE II (CONTD)
DATA. P0 INT NSSS B0P VALUE ENGR VALUE DESCRIPTION INSTRUMENT POINT ID RANGE UNITS 071 CONTAINMENT. NONE GNA0027 10 to 98 PERCENT 072 HUMIDITY GNA0028 073 CONTAINMENT NONE GSA0010 0 to 10 PERCENT 074 HYDR 0 GEN GSA0019 CONCENTRATION 075 S/G A SG-FD/512 REF0405A C to 5000 KLB/HR 076 STEAM / FLOW SG-FD/513 REF0406A 077 S/G B SG-FD/522 'REF0425A 0 to 5000 KLB/HR
, 078 STEMA FLOW SG-FD/523 REF0426A
?
079 S/G C SG-FD/532 REF0445A 0 to 5000 KLB/HR 080 STEAM FLOW SG-FD/533 REF0446A 081 S/G D SG-FD/542 REF0465A 0 to 5000 KLB/HR 082 STEAM FLOW SG-FD/543 REF0466A 083 5/G A SG-LD/517 RELO400A 0 to 100 PEP, CENT 084 WATER LEVEL SG-LD/518 RELO401A 085 SG-LD/519 REL0402A 086 S/G B SG-LD/527 RELO420A 0 to 100 PERCENT 087 WATER LEVEL SG-LD/528 RELO421A 088 SG-LD/529 RELO422A m.____._____
TABLE II (CONTD) .
NSSS 80P 'VALUti ENGR DATA POINT' INSTRUMENT POINT ID RANGE- UNITS ,
.VALUE- DESCRIPTION.-
S/G C -SG-LD/537' RELO440A 0 to 100 ~ PERCENT-089 WATER LEVEL . SG-LD/538- RELO441A 090.
SG-LD/539 RELO442A
-091 092 S/G D. SG-LD/547 RELO460A 0 to 100 PERCENT
. WATER LEVEL SG-LD/548 RELO461A 093 SG-LD/549 RELO462A .
094 095 S/G A SG-PD/514 REP 0400A 0'to 1300 PSIG SG-PD/515- REPO401A 096 PRESSURE SG-PD/516_ REP 0402A 097 l
098 S/G B SG-PD/524 . REP 0420A 0 to 1300 PSIG SG-PD/525 REP 0421A
- . 099 PRESSURE
~ SG-PD/526- REPO422A
~ 100 I
101 'S/G C SG-PD/534 . REP 0440A 0 to 1300 PSIG PRESSURE SG-PD/535 REP 0441A 102 SG-PD/536 REPO442A 103 104 S/G D SG-PD/544 REP 0460A 0 to 1300 PSIG PRESSURE SG-PD/545 REP 0461A 105 SG-PD/546 REP 0462A 106 107 S/G A SG-FD/510 REF0403A 0 to 5000 KLB/HR 108 FEEDWTR FLOW SG-FD/511 REF0404A 109 S/G B SG-FD/520 REF0423A 0'to 5000 KLB/HR 110 FEEDWTR FLOW .SG-FD/521 REF0424A
.. o
' TABLE II'(CONTD)
~ DATA; POINT NSSS - BOP VALUE- ENGR:
VALUE DESCRIPTION INSTRUMENT POINT ID RANGE. UNITS 111 ~S/G ' C . SG-FD/530 REF0443A' 0 to 5000 ,KLB/HRL 112 FEEDWTR FLOWc SG-FD/531 REF0444A 113 S/G D .SG-F0/540 REF0463A 0 to 5000 - KLB/HR 114 FEEDWTR FLOW- SG-FD/541 .REF0464A 115 S/G'A AUX FLOW -NONE ALF0702 0 to 200 KLB/HR 116 S/G B AUX FLOW 'ALF0703
. -117' S/G C AUX FLOW ALF0704 118 S/G D AUX FLOW' ALF0701 o l 119 PZR RELIEF RC-PD/469 REP 0485A 0 to 120 PSIG
- g TANK PRESSURE
, 120 PWR RANGE CH.1 RE-NM/41F REN0049A 0 to 120 PERCENT 121- PWR RANGE CH 2. RE-NM/42F REN0050A 122 PWR RANGE CH 3 RE-NM/43F REN0051A 123- PWR RANGE'CH 4 RE-NM/44F REN0052A 124 HOT LEG TEMP RC-TB/413A RET 0419A 0 to 700 DEG. F LOOP 1 1
125 HOT LEG TEMP RC-TB/423A RET 0439A 0 to 700 DEG. F LOOP.2 -
126 H0T LEG TEMP RC-TB/433A RET 0459A 0 to 700 DEG. F j LOOP 3 i
j 127 HOT LEG TEMP RC-TB/443A RET 0479A 0 to 700 DEG. F
, LOOP 4
TABLE II (CONTD)
DATA POINT NSSS B0P VALUE ENGR VALUE DESCRIPTION INSTRUMENT POINT ID RANGE UNITS 128 COLD LEG TEMP RC-TB/4138 RET 0406A 0 to 700 DEG. F LOOP 1 129 COLD LEG TEMP RC-TB/4238 RET 0426A 0 to 700 DEG. F LOOP 2 130 COLD LEG TEMP RC-TB/4338 RET 0446A 0 to 700 DEG. F-LOOP 3 131 COLD LEG TEFP RC-TB/443B RET 0466A 0 to 700 DEG. F 8.00P 4 i 132 SOURCE RNG CH 1 RE-NM/31F REN0031A 10-I to 10 5 DKCS qi 133 SOURCE RNG CH 7 RE-NM/32F REN0032A 134 INT. RANGE CH 1 RE-NM/35B REN0035A 10-5 to 10 3 MCAMP 135 INT. RANGE CH 2 RE-NM/36B REN0036A 136 RWST LEVEL SI-LD/930 RELO930A 0 to 100 PERCENT 137 SI-LD/933 RELO933A 138 CST LEVEL NONE APL0004 0 to 100 PERCENT 139 REACTOR RC-LD/1311B REL0501A 0 to 120 PERCENT 140 VESSEL LEVEL RC-LD/13218 RELOS21A 141 CONDENSER NONE ACP0204 0 to 40 IN. HG 142 PRESSURE ACP0211 143 ACP0218
TABLE II (CONTD)
DATA POINT NSSS BO? VALUE ENGR VALUE DESCRIPTION . INSTRUMENT POINT ID RANGE UNITS 144 RHR FLOW AC-FD/618(A) REF0626A 0 to 5500 GPfl 145 RHR FLOW AC-FD/619(B) REF0627A 146 RHR HX AC-TD/612(A) RET 0630A 50 to 400 DEG. F 147 TEMP IN AC-TD/613(B) RET 0631A 148 RHR HX AC-TD/604(A) RET 0627A 50 to 400 DEG. F 149 TEMP OUT AC-TD/605(B) RET 0628A 150 PRESSURIZER NONE BBZ0455AA 0 or 1 N/A 151 PORV POSITION BBZO455AB 0 or 1 L
i 152 LATER SPARE LATER LATER SUBC00 LING (P.TD) 153 SUBC00 LING (TC) LATER SPARE LATER LATER 154 PRESSURIZER NONE BBZ8010A 0 or 1 N/A 155 SAFETY VALVE BBZ8010B 0 or 1 156 POSITION BBZ8010C 0 or 1 157 REACTOR TRIP N/A REY 0006D 0 or 1 N/A 158 SIGNAL REY 0007D 0 or 1 159 STEAM LINE NONE ABZ0011 0 or 1 N/A 160 ISOLATION ABZ0014 0 or 1 161 VALUE ABZ0017 0 or 1 162 POSITIONS ABZ0020 0 or 1
TABLE'II-(CONTC)
> DATA POINT NSSS B0P VALUE- ENGR VALUE' DESCRIPTION INSTRUMENT POINT ID RANGE UNITS 163 SAFETY INJECT NONE- SAQ0010A 0 or 1 N/A 154 ACTUATION SIGNAL SAQ0010B 0 or 1 165 FEEDWATER NONF AEZ0039 0 or.1 N/A ~
166 ISOLATION AEZ0040 0 or- 1 167 VALUE AEZ0041. O or 1 168 POSITIONS AEZ0042- 0 or 1 169 RCP A STATUS NONE BBQ0001 0 or i N/A 170 RCP B STATUS BBQ0002 0 or 1 171 RCP C STATUS BBQ0003 0 or'.1 172' RCP D STATUS BBQ0004 0 or.1
.i 173 SOURCE RANGE NONE SEN0033' 0 or 1 N/A y 174 HI VOLTAGE STATUS SEN0033A 0 or 1 N/A ]
175 ERFIS EVENT NONE RTQ0002 0 or 1 N/A TERMINATION SIGNAL 176 ERFIS EVENT NONE RTQ0001 0 or 1 N/A INITIATION SIGNAL 177 S/G A PORY NONE ABZ0001 0 or 1 N/A POSITION 178 S/G B PORV NONE ABZ0002 0 or 1 N/A POSITION
TABLE II (CONTD) ,
DATA POINT NSSS BOP VALUE ENGR VALUE DESCRIPTION INSTRUMENT POINT ID RANGE UNITS 179 S/G C PORV NONE ABZ0003 0 or 1 N/A POSITION 180 S/G D PORV NONE ABZ0004 0 or 1 N/A POSITION 181 AFPT STEAM NONE ABZ0005 0 or 1 N/A 182 SUPPLY ABZ0006 VALVE POSITION 183 S/G A FMIN NONE ABZ0014 0 or 1 N/A L STEAM 150. VALVE i
184 S/G B MAIN NONE ABZ0017 0 or 1 N/A STEAM 150. VALVE 185 S/G C MAIN NONE AB?.0021 0 or 1 N/A STEAM ISO. VALVE 186 S/G D MAIN NONE ABZ0012 0 or 1 N/A STEAM 150. VALVE 187 TURBINE BYPASS NONE ABZ0035 0 or 1 N/A 188 VALVES POSITION ABZ0039 189 ABZ0042 190 ABZ0045
TABLE II (CONTD) ,
DATA POINT .NSSS BOP VALUE ENGR ~
~VALUE DESCRIPTION INSTRUMEN1 POINT ID RANGE . UNITS 191 S/G BLOWDOWN NONE BMF0705 0 to 150 KLB/HR EFFLUENT FLOW 192 -
RHR PUMP.A STATUS NONE ~EJQ0001 0 or 1 N/A 193 RHR PUMP B STATUS EJQ0002-194 S/G A WR WTR LVL SG'LD/501 RELO404A 0 to 100 -%
195 S/GBWRWTRLVL- SG LD 502 -RELO424A 0 to 100 %
l L 196 S/G C WR WTR LVL SG LD 503 RELO444A 0 to 100 %
197. S/G D WR WTR LVL SG LD 504. RELO464A 0 to 100 %
198 AIR SUPPLY PRESS NONE KAP 0010 0 to 200 PSIG 199 ACC PRESS TX 2 NONE KAP 0108 0 to 800 PSIG 200 ACC PRESS TK 3 KAP 0110 201 ACC PRESS TK 4 KAP 0112 202 ACC PRESS TK 5 KAP 0ll4 203 T LOOP 1 NONE RET 0400A 0 to 700 DEG. F ave RET 0420A 204 T LOOP 2 ave RET 0440A 205 T LOOP 3-a 206 T LOOP 4 RET 0460A
. TABLE II (CONTD) .
-DATA POINT' NSSS B0P VALUE ENGR VALUE. DESCRIPTION INSTRUMENT- POINT ID- RANGE UNITS 207 SEP' GRP 1 STATUS NONE NNE0002 0 or i N/A 208 SEP GRP 2 STATUS NNE0004
.209; SEP GRP 3 STATUS. NNE0006 210 SEP GRP 4 STATUS NNE0008 211 SEP GRP 5 STATUS' PNE0001 212~ SEP GRP 6 STATUS PNE0002 213 . AUX TURB ESW VLV NONE ALZ0032 0 or 1 N/A 214 ALZ0033
, 215 AUX TURB CST VLV NONE ALZ0036 0 or 1 N/A RMS-1 RADWASTE BLDG NONE C.I.103 10-7 to 108 1 GASE0US RADIATION /C I/cc MONITOR 4
RMS-2 UNIT VENT GASEOUS NONE C.I.213 10-7 to 108 (/(Cif cc RADIATION MONITOR 0
RMS-3 CONTAINMENT HIGH- NONE C.I.591 10 to 10 8 R/HR RANGE AREA RADIATION C.I.601 10 to 10 MONITOR RMS-4 S/G LIQUID RADIO- NONE C.I.026 10-7 to 10-2 dCjIcc ACTIVITY RADIATION MONITOR RMS-5 CON' "AIRblS- NONE C.I.925 10-7 to 10-2 dC'/ccl
- CHAhot RADIATION MONITOR 8
4 . ,_ ._ . . ,. ~ _ _ . . . _ _ . . ._- __ - .
ts t
2 TABLE III PRIMARY AIDS PARAMETERS Ioss.of Coolant 1 Steam Generator Ioss of Inadequate Accident' 'Ibbe Rupture Secondary Core -
Cooling Cooling (IDCA) (SGTR) . (IOSC) . (IOCO) '
DERIVED PARAMEIER NAME _NOR HU/CD'_ ' NOR HU/CD NOR HU/CD NOR HU/CD RG Pressure -X .X X X '
l l
1b I Pressurizer level X ib.
X X" l 1 l 2 !
. Containment environment X X X l l
. Containment radiation X. X. j l l \
, Secondary radiation X X 3 4 q S.G. level X X l l
. l .
4~
S.G., pressure' X Core exit.tenperature -X X l
_ 9eactor vessel level X X
-l t -
'MMifiers:
'(1): RCS average temperature is crmputed as a volune weighted average of the cold
> ' ' leg.: temperatures and the hot = leg' tenperatures. ' An average density is then-couputed _which is used to adjust the observed pressurizer level for change due
< i to temperature. If' the _ change. in pressurizer level is due to a corresponding
[ ; temperature change, then this parameter is enabled for LOSC (la) . If the V: pressurizer. level ~ decrease is due to mass loss (i.e., greater decrease than
~
can be explained by the temperature change), then this parameter is enaoled
' for a IOCA and SGTR (lb) . .
If the pressurizer level is decreasing due to a mass loss (see modifier 1
~
I -(2) aoove)', then a lack of. abnormal contairment environment conditions is enabled ,
, for SGTR.-
(3) :If there is-no auxiliary feedwater flow to a stean generator, then steam.
~
generator level is enabled for SGrR. -Uso highest S.G. level to determine setpoint violation.-
! ~(4)~ For IOSC use' lowest S.G. level and pressure to determine setpoint violation.
NOR . Normal -
HU/CD .Heatup/Cooldown I
- p-
- - , .. n . __-,-x-_._;n..-a_...-_.-,--- _ . - _ . _ _. _ ,__.
'D e
TABLE IV SECONDARY AIDS PARAMETERS Ioss of Coolant Ste m Generator! Ioss of Inadequate
~ Accident Tube Rupture Secondary Core Cooling j Goolim 1
(LOCA) .
(SGIR) (14SC) (ICCD)
DERIVED !ARAMETIER NAME NOR HU/CD NOR HU/CD NOR HU/CD Pressurimr power operated relief valves position X X (none) ,
1 1 Pressurim r safety valves position - X X I
i I Pressurimr relief tank pressure X- X i l l Contairrent environment X X
-Ste m generator steam flow / feed flow misnatch X X Subcoolin9 l J X X 1 l ll _
lI Ste m generator level (lowest) ,
X 1
Source range power level
- X v
- Enabled only if the reactor is tripped and the source range high voltage is on.
NOR - Normal '
HU/CD - Heatup/Cooldown
TABLE V
. TREND PARAMETERS Cold leg. temperature
. Condensate storage tank level 1 Condenser air discharge ra'diation Containment humidity l
Containment hydrogen' concentration Containment pressure Containment radiation-Containment sump level Core-exit tenperature Containment temperature s Hot leg tenperature
- ICC AIDS bar height Intermediate range power level
- LOCA AIDS bar height
- LOCA AIDS bar height Power range power level Pressurizer level Reactor coolant system average temperature
- Reactor coolant system pressure Reactor vessel level Refueling water storage tank level Residual heat removal system flow Residual-heat removal system heat exchanger inlet tenperature Residual heat removal system heat exchanger outlet temperature Source range porar level Unit vent radiation l
Stesi, generator auxiliary feed flow Steam generator blowdown radiation
TABLE V (CONT)
TREND PARAMETERS (continued)
Steam generator level Steam generator pressure Steam generator steam flow
- SGTR AIDS bar height Subcooling
- NOTE: A trend plot of the ba, height for the NORMAL OPERATION and HEATUP/C00LDOWN AIDS algorithms is available.
,.~
- l.
".. TABLE VI CRITICAL SAFETY FUNCTION PARAMETERS Average RCS temperature ,
Atmospheric dump valve switch position Class lE power Cold leg temperature
. Condensate storage tank level Condenser pressure Containment pressure Containment radiation Containment sump level 1-Core exit temperature l Instrument air Intermediate range startup rate Power range power level Pressurizer-level Rate of change of steam generator pressure Reactor coolant pumps status Reactor coolant system pressure Reactor trip signal Reactor vessel level (wide range and narrow range)
Residual heat removal' system status Source range high voltage status Source range startup rate Steam dump valve accumulators Steam generator feed flow to intact steam generators Steam generator narrow range-level Steam generator pressure Subcooling
- L TABLE VII NSAC-8 PARAMETERS NOT CONTAINED IN THE SPDS TOP LEVEL DISPLAYS Hot Leg Temperature - displayed on a trend graph at the SPDS console (Table V)
Primary RCS Flow - status of RCPs is displayed on the Critical Safety Function (CSF) trees at the SPDS console (Table VI)
RHR Flow - displayed on a trend graph at the SPDS console (Table V)
Main and Auxiliary Feedwater Flow - auxiliary feedwater flow rate is displayed on a trend graph at the SPDS console (Table V). Main feedwater flow rate is used as input to the CSF trees at the SPDS console '(Table VI)
~
Boron Concentration - available through the 80P computer CRT display in the control room Control Rod Position - available through the 80P computer CRT display in the control room Liquid Volume Control Tank Level - available through the 80P computer CRT display in the control room Letdown Flow - available through the 80P computer CRT display in the control room Pump Seal Return Flow - available through the 80P computer CRT display in the control room 1
- ' PRT Level - available through the 80P computer CRT display in the control room PORV Flowrate - valve position available via the AIDS display at the SPDS console (Table IV). Temperature measurement -of the '
fluid downstream of the PORV available through the BOP computer CRT display in the control room Pressurizer Pressure - displayed on the CSF trees at the SPDS console (Table VI)
RHR Radioactivity - available from the Post Accident Sampling Computer System (PASS) printer in the control room Containment Radioactivity - available % CSF trees at the SPDS console (Table VI)
Containment Hydrogen Concentration - displayed on a trend graph at the SPDS console (Table V)
s' e .
TABLE VIII WOG REVISION 0 HIGH PRESSURE ERG PARAMETERS NOT CONTAINED IN THE SPDS TOP LEVEL DISPLAYS Containment Isolation Phase A - available through the B0P computer CRT display in the control room Containment Isolation Phase B - available through the B0P computer CRT display in the control room Intermediate Range Startup Rate - dispiryed on the CSF trees at the SPDS console (Table VI)
Source Range Startup Rate - displayed on the CSF trees at the SFDS console (Table VI)
Control Rod Position - available through the BOP computer CRT display in the control room Control Rod Bottom Lights - available on the digital rod position indication system on the control board. In addi-tion, a signal indicating that control rod is at the bottom is available through the 80P computer CRT display in the control room.
Auxiliary Building Rcdiation - available through the BOP computer CRT display in the control room Containment Ventilation Isolation Dampers - Available through the B0P computer CRT display in the control room
. Pressurizer PORV Block Valves - available through the BOP computer CRT display in the control room Pressurizer Spray Valves e available through the 80P computer CRT display in the control room Reactor Vessel Vent Valves - available through the 80P computer CRT display in the control room Pressurizer Heaters - available on the control board High-Head Safety Injection (SI) Pump Discharge Pressure -
available on the control board Boron Injection Tank (BIT) Temperature - available on the control board Charging /SI flow - available through the B0P computer CRT display in the control room I
".-_.--__--_-__.__._____._m
TABLE VIII (contd)
High-Head SI Flow - available through the 80P computer CRT display in the control room High-Head SI Pumps - available through the 30P computer CRT display in the control room High-Head SI Pump Cold Leg Header Isolation Valve - available through the B0P computer CRT display in the control room High-Head 51 Pump Cold Leg Injection Isolatior. Valves -
available through the 80P computer CRT display in the control room High-Head SI Pump Hot Leg Injection Isolation Valves -
available through the BOP computer CRT display in the control room RWST to High-Head SI Pump Isolation Valves - available through the B0P computer CRT display in the control room High-Head SI Pump Miniflow Isolation Valves - available through the BOP computer CRT display in the control room Low-Head SI Pump Cold Leg Injection Isolation Valves -
available through the 80P computer CRT display in the control room Low-Head SI Pump Hot Leg Injection Isolation Valves - avail-able through the B0P computer CRT display in the control room Recirculation Sump Isolation Valves - available through the B0P computer CRT display in the control room RWST to Low-Head SI Pump Isolation Valves - available through the 80P computer CRT display in the control room Low-Head SI Pump Discharge to Charging /SI Pump and High-Head SI Pump Suction Isolation Valves - available through the BOP computer CRT display in the control room Charging /SI Pump and High-Head SI Pump Suction Connection Isolation Valves - available through the BOP computer CRT display in the control room Accumulator Isolation Valves - available through the 80P computer.CRT display in the control room Accumulator Vent Valves - available through the 80P computer CRT display in the control room
TABLE VIII (contd)
' BIT inlet and10utlet Isolation Valves - available through the 80P computer CRT display in the control room Low Head SI Pump Discharge Crossover Isolation Valves -
available through the 80P computer CRT display in the control room Charging /SI Pump Discharge Pressure - available through the 80P computer CRT display in the control room
- - Boric Acid Tank Temperature - available on the control board.
~*
Charging Flow - availabie through the BOP computer CRT display in.the control room RCP Seal Injection Flow - available through the 80P computer CRT display in the control room Charging /SI Pumps - available through the 80P computer CRT display in the control room Charging /SI Pump Miniflow Isolation Valves - available through the 80P computer CRT display in the control room RWST to Charging /SI Pump Isolation Valves - available through the 80P computer CRT display-in the control room VCI' Outlet Isolation Valves - available through the 80P computer CRT display in the control room Charging Line Isolation Valves - available throught the 80P computer CRT display in the control room Charging Line Flow Control Valve - available on the control
, board
'* Pressurizer Auxiliary Spray Valve - available through the B0P computer CRT-display in the control room RCP ' Seal Injection Outside Containment Isolation Valves -
.available through the 80P. computer CRT display in the control room RCP Seal Return Outside Containment Isolation Valve'- avail-able through the 80P computer CRT display in the control room l
L '.
TABLE VIII (contd)
Letdown Isolation Valves 'available through the' B0P computer CRT display in the control room
. Letdown Orifice Isolation Valves - available through the B0P computer CRT display in the control room i
Letdown Line Containment Isolation Valves - available through the 80P computer CRT display in the control room Low Pressure Letdown Control. Valve - pressure indication available through the B0P computer CRT display in the control room. Valve position available on the control board Excess Letdown Isolation Valves - available through the B0P computer CRT display in the control room
- Charging Flow - available through the B0P computer CRT display in the control room Letdown Flow - available through the B0P computer CRT display in the control room
- ' Excess Letdown Flow - available through the 80P computer CRT display in the control room CCW Pumps status available through the B0P computer CRT display in the control room
'* CCW Valves - available through the B0P computer CRT display in the control room RCP Thermal Barrier CCW Return Inside Containnent Isolation Valve - available through the B0P computer CRT display in the control room-RCP . Thermal Barrier CCW Return Outside Containment Isolation Valve - available through the B0P'ccmputer CRT display in the control room Seal. Water Heat Exchanger Flow - status available through the B0P computer CRT display in the control room
. Containment Fan Cooler Flow - available through the B0P computer CRI display in the control room Service Water Pumps - status available -through the BCP computer CRT display in the control room
TABLE VIII (contd)
Service Water Valves - available through the 80P computer CRT display in the control room Containment Spray Pumps - status available through the 80P computer CRT display in the control room Containment Spray Valves - available through the 80P computer CRT display in the control room Containment Ventilation Isolation Dampers - available through the 80P computer CRT display in the control room Containment Fan Coolers - available through the 80P computer CRT display in the control rcom Hydrogen Recombiners - available on the control board Containment Air Circulation Fans - status available through the 80P computer CRT display in the control room Steam Generator Wide Range Level - available through the 80P computer CRT display in the control room Steam Generator PORVs -'available through the 80P computer CRT display-in the control room Main Steamline Isolation Bypass Valves - available through the 80P computer CRT display in the control room
- Steam Supply Valves to Turbine-Driven AFW Pump - available through the 80P computer CRT display in the control room Turbine Stop Valves - available on the control board Condenser Steam Sump Valves - available through the 80P computer CRT display in the control room Feedwater Flow Control Valves - available through the 80P computer CRT display in the control room Feedwater Flow Control Bypass Valves - available through the B0P computer CRT display in the control room Main Feedwater Flow Rate - available as input to the CSF trees at the SPDS console (Table VI)
Condensate Flow - available through the 80P computer CRT display in the control room Emergency Service Water - status available through the BOP
. computer CRT display in the control room
TABLE VIII (contd)
Motor-Driven AFW Pumps - status available through the B0P computer CRT display in the control room Auxiliary Feedwater Valves - available through the BOP computer CRT display in the control room Condensate Storage Tank to Hotwell Isolation Valves - avail-able through the 80P computer CRT display in the control room Auxiliary Feedwater Flow Rate - displayed on a trend graph at the SPDS console (Table V)
Steam Generator Olowdown Isolation Valves - available through the 80P computer CRT display in the control room Steam Generator Blowdown Flow - available through the B0P computer CRT display in the control room DC Busses - available through the BOD computer CRT display in the control room.
Diesel Generators - available through the 80P computer CRT display in the control room AC Emergency Busses - available through the 80P computer CRT display in the control room Offsite Power - available through the B0P computer CRT display in the control room Air Supply for Pneumatic System - available through the BOP computer CRT display in the control room Control Rod Drive Mechanism Fan Status - available through the B0P computer CRT display in the control room Spent Fuel Pit Level - available through the B0P computer CRT display in the control room Containment Recirculation Sump Sampling - available from the Post Accident Sampling Computer System (PASS) printer in the control room RCS Sampling - available from the Post Accident Sampling Computer System (PASS) printer in the control room Instrumentation for Turbine Runback - available on the control board
.. _ _ _ _ _ _