ML20035G087
| ML20035G087 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 04/22/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9304260137 | |
| Download: ML20035G087 (19) | |
Text
_ _..
~*
GENuclear Energy
' GeremtElecmc Dunpany 175 neme. Aamue Sm km CA 95125 April 22,1993 Docket No. STN 52-001 i
i Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
. Submittal Supporting' Accelerated ABWR Review Schedule - DFSER Confirmatory Item 18A.3-1
Dear Chet:
Enclosed is a draft of the revised Appendix 18F addressing DFSER Confirmatory item 18A.3-1.
Tables 18F-1 through 18F-12.3 (origmally Tables 18F-1 through 18F-13.3) are not included in this transmittal and are subject to a small amount of revision.
With regard to Greg Galletti's February 16,1993 comments, we believe that the addition of the minimum inventory described in Section 18F.3 deprives the majority of those comments of significance and, therefore, we have not responded to them. Exceptions to this are those l
comments having to do with the PRA important operator actions. Modifications to Subsection 19D.7.6 will resolve those comments related to the PRA.
Please provide a copy of this transmittal to Clare Goodman.
Sincerely, Jack Fox Advanced Reactor Programs cc: Norman Fletcher (DOE)
Keith Gregoire (GE) t l
26008G g
g2 i
r 9304260137 930422 I
oDR ADOCK 05 1
ABWR 23A6100AR Standard Plant nev A APPENDIX 18F TABLE OF CONTENTS Section Title Page 18F.1 INTRODUCTION 18F-1 18F.2 TYPICAL INVENTORY OF CONTROLS, DISPLAYS AND 18F-1 ALARMS 18F.2.1 Task Analysis Structure 18F-1 18F.2.2 Guidelines For Selection 18F-3 18F.2.3 Presentation of Results 18F-3
)
18F.2.4 Important Operator Actions From the PRA 18F-5 18F.2.5 inventory Summaries 18F-6 18F.2.5.1 TypicalInventory of Controls 18F-6 18F.2.5.2 TypicalInventory of Displays 18F-6 18F.2.5.3 TypicalInventory of Alarms 18F-6 18F.3 MINIMUM INVENTORY OF CONTROLS, DISPLAYS AND 18F-7 ALARMS 18f.3.1 RPV Control EPG 18F-7 18F.3.2 Primary Containment Control EPG 18F-10 18F.3.3 Secondary Containment Control EPG 18F-12 i
18F.3.4 Radioactivity Release Control EPG 18F-13 l
18F.3.5 RPV Flooding Contingency 18F-14 18F.3.6 Primary Containment Flooding Contingency 18F-14
{
ABWR ux6icora Standard Plant arv. A 18F.1 INTRODUCTION This appendix contains the results of an analysis ofinformation and control needs of the main control room operators. The analysis is based upon the operation strategies given in the ABWR Emergency Procedure Guidelines (EPGs), as presented in Appendix 18A, and upon the significant operator acuons determined by the Probabilistic Risk Assessment (PRA), given in Subsection 18F.2.4, and is composed of two pans. The first pan of the analysis is presented in Section 18F.2 and suppons the development of a typical inventory of controls, displays and alarms which would be used by the main control room operators to implement the ABWR EPGs and to perform the significant operator actions determined by the PRA. The results of the analysis are summarized in Tables 18F-1 through 18F-12.3 of this appendix. The inventory of controls, displays and alarms generated through the analysis described in Section 18F.2 is presented for information only, as the actual full inventory of controls, displays and alarms to be provided in a panicular plant application will be developed through the human-system interface (HSI) design implementation process presented in Appendix 18E.
The second part of the analysis provides the basis for defining a minimum inventory of fixed-position controls, displays and alarms which can be used by the operators, executing the ABWR EPGs, to shut down the reactor, maintain adequate core cooling and remove core decay heat. The results of the second part of the analysis are presented in Section 18F.3 and Tables 18F-13 through 18F-24 of this appendix. This minimum inventory of fixed-position controls, displays and alarms, generated through the analysis described in Section 18F.3 and summarized in Tables 18F-22 through 18F-24, is considered to be part of the ABWR licensing basis and, therefore, as defined in Articles VI.2.c and VIII.2.h(i) of the Table 18E.2.1 definition of the HSI design implementation requirements, each ABWR design implementation will be confirmed to include that minimum set of fixed-position controls, displays and alarms.
The information and controls identified from this analysis do not necessarily include those derived from other design requirements.
18F.2 TYPICAL INVENTORY OF CONTROLS, DISPLAYS AND ALARMS A task analysis of the ABWR EPGs and PRA imponant operator actions was performed and is documented in Tables 18F-1 through 18F-11. The detailed analysis method employed is best presented by describing the structure of these tables.
18F.2.1 Task Analysis Structure In Tables 18F-1 through 18F-11, information and control needs for each operation instruction or action are presented in fourteen (14) columns of information. Information called for and presented in each of those columns in the tables is as follows:
1.
STEP REFERENCE Reference to either the EPGs or to the PRA as the basis of the panicular step addmssed by the associated set of table entries.
~
ABWR 23xamix Standard Plant nev. x 2.
STEP l
Specific step in the EPGs treferred to as the EPG step) or specific operator action referenced in the PRA (herein referred to as the PRA step) or item reference in the PRA.
1 3.
DESCRIPTION OF STEP A summary description of the step or operator action.
4.
INFORMATION TO PERFORM A STEP Information needed by the operator to perform the specific EPG step or PRA operator action.
5.
CONTROL FUNCTIONS TO PERFORM A STEP Control functions that the operators perform to execute the action (s) specified in the EPG step or PRA operator action.
6.
PARAMETER DISPLAYS TO EXECUTE STEP Plant process parameters the status of which the operator must be aware of for execution of the step given in the EPG step or PRA operator action.
7.
CONTROLS TO EXECUTE STEP Controls necessary for the execution of the step.
8.
ALARMS TO PERFORM STEP Annunciators necessary for the execution of the step.
9.
OPERATOR AIDS TO PERFORM STEP Operator aids such as supplementary procedures or other information necessary for the execution of the step.
l l
- 10. DISPLAYS TO JUDGE ACTION ACCOMPLISHMENT OR INITIATION Displays to provide feedback to the operators to confirm that the specific control functions have been initiated or completed.
l i
- 11. POSITION OF CONTROLS TO JUDGE ACTION ACCOMPLISHMENT OR INITIATION Position of control devices that provide feedback to the operators to confirm that proper control actions are initiated or completed.
j i
- 12. ALARMS TO JUDGE ACTION ACCOMPLISHMENT OR INITIATION Annunciators to provide feedback to the operators to confirm that proper conttul actions are initiated or completed.
- 13. OPERATOR AIDS TO JUDGE ACTION ACCOMPLISHMENT OR INITIATION i
Operator aids to provide feedback to the operators to confirm that proper control actions are initiated or accomplished.
18F.2 l
i ABWR 23^6ioora i
Standard Plant arv. 4 e
- 14. DISPLAY, CONTROL OR ALARM THAT IS CLASS lE OR REGULATORY GUIDE 1.97 INSTRUMENT Identification of those devices that are Class 1E or am provided by Class 1E or regulatory l
Guide 1.97 instruments.
l l
18F.2.2 Guidelines For Selection The following guidelines, developed from a research program on advanced control panel designs, were used to specify the candidate types of implementation devices for controls, displays and alarms.
l (a)
Fixed-Position Controls used for the following purposes shall be included in the inventory:
l Manual starting and resetting of safety systems.
Manual starting of emergency backups, Mode switches for initiation of automation sequences.
(b)
Divisional Visual Display Units (VDUs) used for the following purposes shall be included in the inventory:
Individual controls of safety system components.
Lineup displays of safety systems.
(c)
Non-Divisional VDUs used for the following purposes shall be included in the inventory:
Monitoring of non-safety systems aiid control of individual components of non-safety
- systems, Individual alarms (d)
Fixed-Position Alarms used for the following purposes shall be included in the inventory:
Imponant plant-level and system-level alarms (e)
Fixed-Position Displays used for the following purposes shall be included in the inventory:
Monitoring of important plant parameters 18F.2.3 Presentation of Results The results of the operational analysis of each step of the ABWR EPGs and PRA important operator actions are summarized in Tables 18F-12.1 through 18F-12.3.
In the ABWR man-machine interface design, control, display and alarm indication functions are implemented through the use of divisional VDUs (referred to as "Div. VDUs"), non-divisional VDUs (referred to as "VDUs") and/or through the use of dedicated and fixed-position display devices. Refer to Subsection 18.4.2 for a description of the man-machine interface 18F-3
ABWR 23^6>oorn Standard Plant urv. A standard design features. In Tables 18F-12.1 through 18F-12.3, as well as Tables 18F-1 through j
18F-ll, the particular candidate method of design implementation for each control, display and i
alarm function is indicated in brackets as part of each relevant table entry.
In all of these tables, entries are identified by bold-face type and capital letters when they are first identified in the analysis as being the primary method of executing a particular control, display or alarm function. An example is the indication of RPV water level as a critical parameter displayed on the fixed-position display panel in the main control, mom.
i (A) RPV WATER LEVEL [ FIXED. POSITION)
Information given in the brackets indicates the type of implementing device. In order to minimize needless duplication of table entries, subsequent identification of the same design attribute is indicated in the tables with an underline and is not bold-faced nor capitalized. An example ofindication of RPV water level in subsequent steps is:
(a) RPV water level IFixed-Positionl Critical process parameters that are displayed on the fixed-position display panel are provided by Class IE instruments via a non-safety-related display controller. These parameters are also available in the divisional VDUs and the non-divisional VDUs. Therefore, when a monitoring function is specified (entry conditions and usually the conditional statements of each step of the EPGs) and the primary source of the monitored parameter is identified for the first time as a parameter displayed on the fixed-position display panel, the corresponding divisional VDUs and non-divisional VDUs are also listed. However, to minimize unnecessary duplication in the table entries, subsequent listings of the same primary monitoring source (fixed display) will not have their corresponding displays on divisional and non-divisional VDUs identified. As an example,if average drywell pressure display is identified for the first time as shown below:
(A) AVERAGE DRYWELL TEMPERATt?RE
[ FIXED. POSITION)
(b) Average drywell temperature [Div. VDU)
(c) Average drywell temperature [VDU) i Subsequent identification of average drywell temperature as a fixed-position display will be as follows:
(a) Average drywell tempemture IFixed-Position]
l To further reduce duplicate listings, table entries which are underlined will not have their instrumentation classification summarized in the Column 14 entries.
In certain columns of the tables, such as Column 7, " Controls to Execute Step", and Column 10, " Displays to Judge Action Accomplishment or Initiation", syucm controls or a system lineup display is specified as divisional VDUs or as non-divisional VDUs. In the case of Column 7, for 18F-4 I
I I
ABWR 23A61CDAR Standard Plant REv.A controls, all remote control equipment of a panicular system can be controlled from the VDU.
Also in Column 7, certain controls are specified as mode switches. An example is the RiiR(A)
Suppression Pool Cooling Mode Switch. Actuation of a system mode switch will initiate a predefined sequence of system level control, actions, such as aligning valves and starting pumps.
In Column 10, a system lineup display typically represents a graphical mimic of the system similar to that presenteu i'. a system P & ID, where the position of valves, operating status of pumps and status of other components of the system are indicated. Key system and process parameters are also indicated.
Certain displays in these tables are indicated as being fixed displays. Examples of this type of display are (i) switch position indication of a standby liquid control pump control switch and (ii) mode switch selection indication of RHR shutdown cooling mode. For these examples, process parameters such as standby liquid control pump discharge pressure and RHR flow, respectively, provide sufficient information fe.edback on actions initiated by the operator. In addition, certain fixed displays such as recirculation pump trip status indication, main turbine stop valve and control valve status indication are not considered to be absolutely required became fixe.d-position alarms are provided which will present the same status information to the operators. These types of fixed-position displays are not indicated by bold-faced type nor capitalized and, hence, will not be included as part of this representative inventory of displays.
Throughout Tables 18F-1 through 18F-11, numerical values used in the EPGs and in Column 3 represent typical values. These values will be confirmed as part of the established HSI design implementation process, as defined in Appendix 18E, through the execution of plant-specific calculations and analytical methods and updated as necessary for the particular application.
Other clarifications of the information presented in the tables are indicated by notes in the columns of the tables. Controis located outside of the main control room are indicated by an asterisk and a note at the end of Column 7.
18F.2.4 Important Operator Actions From the PRA The following operator actions are considered to be important operator actions in the ABWR PRA (see Section 19D.7):
(1) Backup manualinitiation of HPCF, (2) Recovery of feedwater following a scram, (3) Use of condensate injection following a scram with reactor depressurized, (4) Control of reactor water level in an ATWS, (5) Emergency Jepressurization of the reactor, (6) Alignment and initiation of firewater for RPV injection with ECCS failure, l
(7) Alignment and initiation of firewater for drywell spray, l
(8) Initiation of wetwell spray using RHR, (9) Isolation of water sources in an internal flooding, (10) Initiation of standby RHR in event of failure of operating RHR during shutdown operations.
18F-5 i
ABWR 2346ioora Standard Plant REv.A These actions have been determined to be a subset of the operator actions required to implement the EPGs and, themfore, no further analysis of them is required.
18F.2.5 Inventory Summaries As discussed above, Tables 18F-12.1,18F-12.2 and 18F-123 list typicalinventories of the controls, displays and fixed-position alarms necessary to implement each step of the ABWR EPGs and certain PRA important operator actions. These tables am discussed in more detail in the following paragraphs.
18F.2.5.1 Typical Inventory of Controls Table 18F-12.1 lists a typical inventory of controls used for execution of emergency operating procedures. These controls consist of fixed-position control devices and controls in divisional VDUs and non-divisional VDUs. In the anaiysis msults presented in Tables 18F-1 through 18F-11, control devices that am required for execution of a particular EPG step or an important operator action are given in Column 7 in bold-face type and capital letters. These devices are summarized in Table 18F-12.1. In Table 18F-12.1, fixed-position controls that are Class IE control devices are indicated by bold-face type and capitalletters. Non-safety-related fixed-position control devices are indicated by lower case letters followed by a star character
(*). All control devices located on divisional VDUs are provided by safety-related system controllers. Controls on the VDUs (driven by the process computer system) are provided by non-safety-mlated systems. In addition, non-safety-mlated control and display capability, as described in Subsection 18.4.2, are provided by VDUs that are independent of the process computer. These process computer-independent VDUs provide a backup control and display capability to the process computer-driven VDUs not specifically indicated in Tables 18F-1 through 18F-123.
18F.2.5.2 Typical Inventory of Displays Displays that are used for the implementation of the EPGs am identified in Tabler 18F-1 through 18F-11 by bold-face type and capital letters and are summarized in Table 18F-12.2. In l
Table 18F-12.2, fixed-position displays provided by Class 1E instruments are similarly indicated l
by bold-face type and capital letters. Those that are provided by non-safety-related instruments are indicated by lower case letters and by a star character (*). A display parameter that is a Regulatory Guide 1.97 parameter is indicated by a double star character (**) following the table entry.
18F.2.53 Typical Inventory of Alarms The fixed-position alarms identified in Tables 18F-1 through 18F-11 am summarized in Table 18F-12.3. Fixed-position alarms provided by Class 1E instruments are similarly indicated by bold-face type and capital letters. Those that are provided by non-safety-related instruments are indicated by lower case letters with a star character (*) following the table entry.
18F-6 1
~
23= =^a Standard Plant REV A l
18F.3 Minimum Inventory of Controls, Displays and Alarms i
Tables 18F-22,18F-23, and 18F-24 list the minimum inventories of cc.itrols, displays, and alarms, respectively, required to support operator actions to shut down the reactor, maintain adequate core cooling and remove core decay heat. These lists are based upon an analysis of the information and controls needed to satisfy the criteria that the main control room shall have l
sufficient fixed-position controls, displays and alarms during an emergency to achieve the successful completion of the above actions. In the remainder of this subsection, the specific rationale for defining the minimum sets listed in Tables 18F-22,23 and 24 are discussed in the context of the EPG entry conditions and success paths.
The EOP entry conditions for RPV Control Section of the ABWR EPGs are any of the following:
i i
(a) RPV water levellow, i
(b) RPV pressure high, (c) Drywell pmssure high.
(d) A condition which requires mactor scram and reactor power is above the APRM downscale 3
l trip value or cannot be determined.
l l
l The alanns and displays required for monitoring these conditions are summarized in Table 18F-i 13 and are considered a pan of the minimum inventory set.
t i
l Table 18F-13 l
RPV Control Entry Conditions Monitoring i
Entry Condition Alarms Displays j
RPV water levellow RPV Water Level 3 RPV water level RPV pressure high RPV Pressure High-High RPV pressure l
Drywell pressure high Drywell Pressure High-High Drywell pressure I
l A condition which requires reactor scram, and reactor power is above 5% or cannot be determined, including:
Neutron Flux high Neutron Flux High-High Reactor power (APRM)
Neutron monitoring system NMS System inop.
inoperative CRD charging water pressure low CRD Charging Pressure Low Rapid core flow decrease Rapid Core Flow Decrease i
Main turbine trip Main Turbine Trip Main generator trip Main Generator Trip Main steam line radiation high Main Steam Line Radiation High Main steam line radiation Reactor thermal power high Reactor thermal power 18F-7
s - a _.
-ua
---~2
- a r
~
ABWR meiman Standard Plant i
nrv 4 For reactor water level control, a success path for core cooling consists ofisolation of the reactor and systems connected to the RPV, initiation of standby AC power sources (the Class 1E diesel generators), and initiation of ECCS. The fixed-position controls, displays and alarms which l
provide for the initiation of control functions and confirmation that the actions taken were successful are summarized in Table 18F-14. These controls, displays and alarms are considered a part of the mimmum mventory set.
j i
Table 18F-14 RPV Water Level Control l
i EPG Controls Alarms Displays Success Path i
j RC-1 Manual Scram initiation Sc.;m Solenoids Power Status initiate manual Switches A and B, Ligts (8); Reactor Power i
scram Reactor Mode Switch (SRNM).
RC/L-1, Main Steam Line Manual RPV Level Reactor isolation Status: MSIV l
Initiate isolation Switches 1.5/Drywell Position Status j
isolation (4,1 per division)
Pressure High, Isolation incomplete RC/L-1 Diesel Generator Start Emergency Diesel Generator l
Initiate diesels Switches Operating Status (3,1 per (3,1 per division) division)
RC/L-1, Primary Containment RPV Level 3 Reactor isolation Status.
Initiate Manual isolation Switches isolation l
isolation (3,1 per division)
Incomplete, RPV Level 2 isolation incomplete I
RC/L-2 RCIC System initiation RPV Level 2, RCIC Flow, HPCF(B) Flow, l
Initiate ECCS Switch, HPCF(B) System RPV Level 1.5, HPCF(C) Flow, RHR(A) Flow, initiation Switch, HPCF(C)
RPV Level 1 RHR(B) Flow, RHR(C) Flow.
System initiation Switch, l
RHR(A) System initiation l
Switch, RHR(B) System i
Initiation Switch, RHR(C)
System initiation Switch, l
l 18F-8
ABWR m84 =^n Standard Plant REV.A For reactor power control, the success path is to initiate a manual scram. For reactor pressure control, successful pressure control is achieved by depressurizing the reactor. The fixed-position controls, displays and alarms requimd for manual scram and reactor depmssurization are summarized in Table 18F-14 and are considered a part of the minimum inventory set.
Table 18F-15 RPV Power and Pressure Control EPG Controls Alarms Displays Success Path RC-1 Manual Scram Initiation Scram Solenoids Power Status initiate manual Switches A and B, Reactor Lights (8);
scram Mode Switch Reactor Power (SRNM).
C2-1.3, Div. I Manual ADS Channel RPV pressure j
Emergency RPV 1 Initiation Switch, depressurization Div. I Manual ADS Channel by ADS 2 Initiation Switch, i
Div. Il Manual ADS Channel 1 Initiation Switch, j
Div.11 Manual ADS Channel 2 initiation Switch, 18F-9
.'ABWR amma Standard Plant nyva 18F.3.2 Primary Containment Control EPG The EOP entry conditions for Primary Containment Contml Section of the ABWR EPGs are any of the following:
(a) Suppression pool temperature high, (b) Drywell temperature high, (c) Drywell pmssum high, (d) Suppression pool waterlevel high, (e) Suppression pool waterlevel low, (f)
Primary containment hydrogen concentration high.
The alarms and displays required for monitoring these conditions are summarized in Table 18F-15 and are considered a pan of the minimum inventory set.
Table 18F-16 Primary Containment Control Entry Conditions Monitoring Entry Condrtion Alarms Displays l
Suppression pool average temperature Suppression Pool Average Suppression pool Temperature High average temperature 1
Drywell average temperature Drywell Average Temperature Drywell average 1
High temperature Drywell pressure Drywell Pressure High Drywell pressure Suppression poolwater level Suppression Pool Water Level Suppression poolwater High/ Low level Drywell hydrogen concentration Drywell Hydrogen Concentration Drywell bydrogen High concentration (when monitors are in operation)
Wetwell hydrogen concentration Wetwell Hydrogen Wetwell hydrogen Concentration High concentration (when monitors are in operation)
)
i l
{
ABWR meiwia Standard Plant nev x For primary containment control, the success path consists of depressurizing the reactor and terminating injection flow into the containment when certain conditions exist as defined in the EPGs The ultimate overpressure protection of the containment is provided by the rupture disks.
The controls for depressurizing the reactor are given in Table 18F-15. The fixed displays for determining whether emergency reactor depressurization is requimd, and the fixed-position controls and displays required for terminating injection into the primary conteinment are j
summarized in Table 18F-17 and are considered a part of the minimum inventory set.
Table 18F-17 Primary Containment Control EPG Controls Alarms Displays Success Path SP/T-3, (Refer to Table Suppression pool average emergency 18F-15) temperature, RPV pressure.
depressunzation when pool temperature exceed limit.
i DW/T-3, emergency (Refer to Table Drywell average temperature.
depressurization when 18F-15) drywell average temperature exceeds limit.
PC/P-3, (Refer to Table Wetwell pressure, suppression emergency 16F-15) pool water level.
depressurization when wetwell pressure exceed limit.
SP/L-2, SP/L-3, (Refer to Table Suppression pool water level, emergency 18F-15) suppression pool average depressurization when temperature, RPV pressure.
suppression poolwater level exceed limit.
SP/L-3.3, terminate Condensate pump Primary containment water I
injection flow into the standby mode level, wetwell pressure.
containment when initiation switches (3),
containment water level reactor feedpump cannot be maintained standby mode below limit.
initiation switches (3)
PC/H, PC/H-4, emergency (Refer to Table Wetwell hydrogen depressurization when 18F-15) concentration, drywell drywell or wetwell hydrogen concentration.
hydrogen concentration cannot be controlled below limits.
The high pressure ECCS (RCIC,IIPCFtB), liPCF(C)) have their suction valves automatically aligned to the suppression pool on high suppe:,3 ion pool water level. RHR can take suction only from the suppmssion pool. For these systems, no fixed-position controls for terminating injection flows into the containment are necessary.
ABWR 23^siooxa Standard Plant nry a 18F.3.3 Secondary Containment Control EPG The EOP entry conditions for Secondary Containment Contml Section of the ABWR EPGs are any of the following:
(a) Reactor building differential pressure low, (b) An area temperature above maximum normal temperature, (c) A HVAC cooler differential temperature above the maximum differential temperature, (d) A HVAC exhaust radiation level above the maximum normal radiation level, (e) An area radiation above the maximum normal radiation level, (f)
A floor drain sump water level above the maximum normal water level.
The alarms required for monitoring these conditions are summarized in Table 18F-18 and are considered a part of the minimum inventory set.
Table 18F-18 Secondary Containment Control Entry Conditions Monitoring Entry Condition Alarms Reactor building differential pressure low Reactor Building AP Low Area temperature above maximum normal temperature Area Temperature High
+
HVAC cooler differential temperature above the maximum Area HVAC AT High differentialtemperature HVAC exhaust radiation level above the maximum normal RB/HVAC Exhaust Radiation High l
radiation level j
Area radiation above the maximum normal radiation level Reactor Building Area Radiation f
High Floor drain sump water level above the maximum normal water Reactor Building Floor Drain Sump i
level Water Level High-High I
i ABWR
~
ms, min Standard Plant i
~
nev. A l
For secondary containment control, the success path consists of depressurizing the reactor when cenain conditions exist as defined in the EPGs. The controls for depressurizing the reactor are given in Table 18F-15. The displays for determining whether emergency reactor 1
depressurization is requimd are summarized in Table 18F-17 and are considered a pan of the l
minimum inventory set.
Table 18F-19 Secondary Containment Control EPG Controls Alarms Displays l
Success Path SC/T-4.2, emergency (Refer to Table Area Temperature i
depressurization when an 18F-15)
High-High area temperature exceeds l
its maximum safe operating temperature in more than i
one area.
SC/R-2.2, emergency (Refer to Table Reactor Building Area depressurization when 18F-15)
Radiation High-High area radiation level exceeds its maximum safe operating levelin more than one area.
l 5
18F.3.4 Radioactivity Release Control EPG 3
t The EOP entry conditions for Secondary Containment Control Section of the ABWR EPGs is offsite radioactivity release rate above the offsite release rate which requires a declaration of an Alen status. The offsite release rate will be based upon calculations in accordance with the Offsite Dose Calculation Manual, results of sampling analysis, or ponable survey instruments.
j No specific fixed-position alarms and displays will directly indicate the entry condition.
However, fixed-position alatms Stack Radioactivity High and RCW Radioactivity High will prompt the operator to initiate action for sampling analysis and dispatch survey team to the plant l
boundary. These two fixed-position alarms are considered a part of the minimum inventory set.
l l
Table 18F-20 I
Radioactivity Release Control Entry Conditions Monitoring Entry Condition Alarms Offsite release rate above level for Alert status.
Stack Radioactivity High, RCW Radioactivity High The success path for radioactivity release control is to isolate primary systems and depn ssurize the mactor. The fixed-position devices to achieve these actions are given in Table 181L15.
18F-13 I
-Wr P m m
7 1--'
l i
.'ABWR 23^sioorn Standard Plant nev 4 18F.3.5 RPV Flooding Contingency l
When RPV waterlevel cannot be determined or when water level instruments cannot be relied upon to provide indication of adequate core cooling, RPV flooding is required, as specified in the I
ABWR EPGs. The RPV Flooding Contingency provides strategies for flooding the RPV. RPV water level must be continuously monitored. The EOPs provide specific criteria for determination of validity ofindicated water level instruments. A fixed-position alarm, Indicated i
RPV Water Level Abnormal, will alert the operator when conditions exist which indicates that the displayed RPV water level was not reliable. This alarm is considered pan of the minimum set of fixed-position alarms.
i A success path for RPV flooding is for the operator to initiate flooding using HPCF(B) or
[
HPCF(C), bypassing the Level 8 HPCF shutoffinterlock so that HPCF can continued to be used j
for flooding the RPV above level 8. The fixed-position contmls and displays necessary for
(
flooding the RPV with the reactor shutdown am given in Table 18F-21 and are included as part l
of the minimum inventory set.
l Table 18F-21 RPV Flooding Contingency EPG Controls Alarms Displays Success Path C4-3.1: Initiate HPCF to inject HPCF(B) System Indicated RPV RPV pressure, l
into the RPV untilat least 6 SRVs initiation Switch, Water Level Wetwell pressure, j
are open, RPV pressure is not HPCF(C) System Abnormal SRV position i
increasing and is 3.27 kg!cm2 g initiation Switch, indication.
or more above wetwell pressure, Level 8 HPCF(B) logic
{
bypassing Level 8 interlock.
bypass (in system cabinet),
i Level 8 HPCF(C) logic l
bypass (in system j
j cabinet),
18F.3.6.
Primary Containment Flooding Contingency For certain postulated LOCAs, adequate core cooling can only be maintained when the primary containment is flooded to an elevation above the top of the active fuel. The minimum controls, displays, and alarms necessary for flooding the containment, and terminating injection flow into the containment, are included in Table 18F-14 and Table 18F--17, respectively.
18F.3.7 Regulatory Guide 1.97 Parameters Fixed-position displays that are not specifically required by the above analysis of minimum inventory based on defined success paths, but are quired by Regulatory Guide 1.97, are included as part of the minimum displays. These au Condensate Storage Tank Water Level and SLC Pump Discharge Pressure. All parameters in the minimum display inventory (Table 18F-
- 23) are Regulatory Guide 1.97 parameters except the SRV Position Status indications and Scram Solenoids Power Status indications. One Regulatory Guide 1.97 requirement for reactor scram status indication is provided by an alarm, Contml Rod Not Insened To/Beyond MSBWP.
l 1
"ABWR nA6imAn Standard Plant arv. 4 TABLE 18F-22 511NI51051 INVENTORY OF CONTROLS I
NO.
FIXED POSITION N O.
FIXED POSITION 1
MANUAL SCRAM INITIATION SW(A),
22 DIV 1 MANUAL ADS CHANNEL 1 INITIATION S W, j
2 MANUAL SCRAM INITIATION SW(B),
23 DIV I MANUAL ADS CHANNEL 2 INITtATION S W, 3
REACTOR MODE SW 24 Div 11 MANUAL ADS CHANNEL 1 INITIATION S W, 4
DIV. I MAIN STE AM LINE MANUAL 25 DIV 11 ADS MANUAL ADS CHANNEL 2 ISOLATION SW INITIATION S W,
(
5 DIV. It M A N STEAM LINE MANUAL 26 CONDENSATE PUMP (A) STANDBY MODE ISOLATION SW INITIATION SWITCH j
6 DrV. til MAIN STEAM LINE MANUAL 26 CONDENSATE PUMP (B) STANDEY MODE I
ISOLATION SW INITIATION SWITCH i
7 Div. IV MAIN STEAM LINE MANUAL 27 CONDENSATE PUMP (C) STANDBY MODE ISOLATION SW INIT,ATION SWITCH 8
PRIM ARY CONT AtNM ENT 28 REACTOR FEEDPUMP (A) STANDBY DIV. I MANUAL ISOLATION SW, MODE INITIATION SWlTCH i
1 9
PRIM ARY CONT AINM ENT 29 REACTOR FEEDPUMP (B STANDBY SwiTC)r4 DIV, il M ANUAL ISOLATION SW, MODE INITIATION l
a 10 PRIM ARY CONT AINM ENT T)
REACTOR FEEDPUMP (C) STANDBY
(
DIV. lll WANUAL ISOLATION SW, MODE INITIATION SWITCH 11 RCic INITIATION SW 12 HPCF (B) INITIATION SW r
i 13 HPCF (C) INITIATION SW t
)
l l
17 DG(A) START SW, 18 DG(B) START SW, 19 DG(C) START 3W, 20 LEVEL 8 HPCF(B) SHUTOFF LOGIC BYPASS (SYSTEM CABINET IN BACK PANEL) 21 LEVEL 8 HPCF(C) ( SHUTOFF LOGIC BYPASS (SYSTEM CABINET IN BACK PANEL) l Amendmr:nt ??
1 W ??
l
ABWR 23^6ito^n Standard Plant nuv. x F
TABLE 18F-23 j
511NI51U51 INVENTORY OF DISPLAYS POSITION N O.
FIXED POSITION N O.
$}ED 1
1 22 PRIM A N s LJNTAINMENT WATER LEVEL RPV WATER LEVEL
- f 2
WETWELL PRESSURE * *,
2)
CONDENSATE STORAGE TANK WATER LEVEL * *,
3 SUPPRESSION FOOL ~ BULK 24 SLC PUM P( A) DISCHARGE AVERAGE TEMPERATURE * *,
PRESSURE **
4 HPCF(B) FLOW * *,
25 SLC PUMP (E) DISCH A RGE PRESSURE * *
)
5 HPCF(C) FLOW * *,
26 SUPPRESSION POOL LEVEL **,
6 RPV PRES 5URE * *,
27 AVERAGE DMWELL TEMPERATURE **,
7 DRYWELL PRESSURE * *,
28 WETWEt L HYDROGEN CONCENTRATION LEVEL * *,
8 REACTOR POWER LEVEL, 3
DRYWELL HYDROGEN (NEUTRON FLUX, APRM) * *,
CONCENT R ATION LEVEL * *,
^
\\
9 REACTOR POWER LEVEL (SRNM) 3()
DRYWELL OXYGEN CONCENTRATION **
l 10 RE ACTOR THERMAL POWER **,
31 WETWELL OXYGEN CONCENTRATION **
l 11 MSIV POSITION STATUF (INBOARD 32 Main Stack radiation level **,
AND OUTBOARD VALMS) *
- l l
12 MAIN STEAM LINE RADIATION **,
33 DRYWELL RADIATION LEVEL *
- 13 SCRAM SOLENOIDS POWER STATUS 31 WETWELL RADIATION LEVEL **
LIGHTS (8) 14 RPV ISOLATION STATUS *
16 RHR( A) FLOW *-*,
17 RHR(B) FLOW **,
18 RHR(C) FLOW * *,
19 EMERGENCY DIESEL GENERATOR PERATING STATUS * *,
2)
EMERGENCY DIESEL GENERATOR (B)
OPERATING STATUS
- 4, 21 EMERGENCY DIESEL GENERATOR P RATING ST ATUS * *,
1
- denotes Regulatory Guide 1.97 parameters.
Amendment 77 ISIL77
.'ABWR 23AsionAn Standard Plant REV.A 1
TABLE 18F-24 51INI51U51 INVENTORY OF ALAR 51S NO.
FIXED POSITION N O.
FIXED POSITION I
INDICATED RPV WATER LEVEL 21 SUPPRESSION POOL WATER ABNORMAL LEVEL HIGH/ LOW, 2
RPV WATER LEVEL 3, 2
CAMS H2/02 LEVEL HIGH, 3
RPV PRESSURE HIGH-HIGH 3
DRYWELL PRESSURE HIGH.
24 AREA TEMPERATURE HIGH HIGH 5
25 AREA HVAC AT HIGH NEUTRON FLUX HIGH-HIGH 6
NEUTRON MONITORING SYSTEM INOP 26 RBHVAC EXHAUST RADIATION HIGH 7
CRD CHARGING WATER PRESSURE 27 REACTOR BUILDING AREA RADIATION
- LOW, HIGH 8
RAPID CORE FLOW DECREASE, 3
REACTOR BUILDING FLOOR 1
DRAIN SUMP WATER LEVEL HIGH-HIGH 9
MAIN TURBINE Trip 3
STACK RADIOACTIVITY HIGH 10 MAIN GENERATOR TRIP 30 RCW RADIOACTIVITY HIGH Il MAIN STEAM CNE RADIATION
INCOMPLETE, 14 RPV LEVEL 1.5 'D RY WE L L PRESSURE HIGH ISOLATION INCOMPLETE, 15 RPV WATER LEVEL 2, 16 RPV WATER LEVEL 1.5, 17 RT V WATER LEVEL 1, a
l 18 CONTROL ROD SCRAM STATUS 19 SUPPRESSION POOL BULK AVERAGE TEMPERATURE HIGH, 3
DRYWELL AVERAGE TEMPERATURE HIGH, Amendment 77
]g}:_??
. -, - -