ML20133H738
| ML20133H738 | |
| Person / Time | |
|---|---|
| Issue date: | 07/31/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-1122, NUDOCS 8508090488 | |
| Download: ML20133H738 (400) | |
Text
- - - - --..
NUREG-1122 Knowledges and Abilities Catalog for Nuclear Power Plant Operators:
Pressurized Water Reactors j
,k a[eYuNsheduly Division of Human Factors Safety Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission O Washington, D.C. 20555
,p" m, t
[#
O x
191090V88
i O
i f
ABSTRACT This document catalogs roughly 5300 knowledges and abilities of reactor operators and senior reactor operators. It results from a reanalysis of much
. larger job-task analysis data base compiled by the Institute of Nuclear Power Operations (INP0). Knowledges and abilities are cataloged for 45 major power plant systems and 38 emer mental safety functions (gency evolutions, e.g., reactivity control grouped and reactor according to 11 coolant funda-system inventory control). With appropriate sampling from this catalog, operator licensing examinations having content validity can be developed. A struc-tured sampling procedure for this catalog is under development by the Nuclear l Regulatory Commission (NRC) and will be published as a companion document,
" Examiners' Handbook for Developing Operator Licensing Examinations" (NUREG-1121). The examinations developed by using the catalog and handbook will cover those topics listed under Title 10, Code of Federal Regulations, Part 55.
O d
4 O
K/A catalog ijj
0 (s
CONTENTS P_ age ABSTRACT............................................................. iii 1 ORGANIZATION OF THE CATAL0G.................................... 1-1 ..
1.1 Plant-Wide Generic Knowledges and Abilities. . . . . . . . . . . . . . . 1-1 1.2 Safety Function Groupings................................. 1-1 -
- 1. 3 Knowledge and Ability Categories ......................... 1-2
' 'g 1.4 Components ............................................... 1-3
- 1. 5 Knowledge Importance Ratings ............................. 1-3 ;
1.6 Additional Organizational Details ........................ 1-4 1.7 Acronymns and Terms ...................................... 1-4
- 1. 8 List of Systems by System Number ......................... 1-6 s 1.9 List of Emergency Plant Evolutions by EPE Mode Number ..... 1-8 2 SYSTEM-WIDE AND PLANT-WIDE GENERIC KNOWLEDGES AND ABILITIES ... 2-1 i
3 SYSTEM SAFETY FUNCTION GROUPS I
rs 3.1 Reactivity Control Systems and Malfunctions
\ <
\ 3.1.1 Plant Systems Control Rod Drive System (CRDS)................. 3.1-1 l Chemical and Volume Control System (CVCS)....... 3.1-15 Rod Position Indication System (RPIS)........... 3.1-31 3.1.2 Emergency Plant Evolutions Continuous Rod Withdrawal....................... 3.1-35 Dropped Control Rod............................. 3.1-38 Inoperable / Stuck Control Rod.................... 3.1-41 Reactor Trip.................................... 3.1-43 Emergency Boration.............................. 3.1-45 Anticipated Transient Without Scram (ATWS)...... 3.1-48 3.2 RCS Inventory Control Systems and Malfunctions 3.2.1 Plant Systems Reactor Coolant System (RCS).................... 3.2-1 Chemical and Volume Control System...............
- Emergency Core Cooling System (ECCS)............ 3.2-9 Pressurizer Level Control System (PZR LCS)...... 3.2-21 Engineered Safety Features Actuation System (ESFAS)......................................... 3.2-25
(
\~
- See Section 3.1.1.
K/A catalog v
CONTENTS (Continued)
Page 3.2.2 Emergency Plant Evolutions Loss of Reactor Coolant Makeup.................. 3.2-29 h Pressurizer Level Malfunction................... 3.2-31 1 3.3 RCS Pressure Control Systems and Malfunctions ;
3.3.1 Plant Systems -
Emergency Core Cooling System.................... ,
Pressurizer Pressure Control System (PZR PCS)... 3.3-1
- 3.3.2 Emergency Plant Evolutions
- Pressurizer Vapor Space Accident................ 3.3-5 Small Break L0CA................................ 3.3-8 "
Large Break L0CA................................ 3.3-12 )'
Pressurizer Pressure Control System Malfunction. 3.3-15 .
h Steam Generator Tube Leak....................... 3.3-17 m Steam Generator Tube Rupture.................... 3.3-20 i l N 3.4 RCS Heat Transport Systems and Malfunctions :<
3.4.1 Plant Systems . y Reactor Coolant System...........................
- Reactor Coolant Pump System (RCPS).............. 3.4-1 Residual Heat Removal System (RHRS)............. 3.4-7 h{
Steam Generator System (S/GS)................... 3.4-13 4 3.4.2 Emergency Plant Evolutions Reactor Coolant Pump Malfunctions............... 3.4-17 Loss of Residual Heat Removal System............ 3.4-20 Inadequate Core Cooling......................... 3.4-23 3.5 Secondary System Heat Transport Systems and Malfunctions 3.5.1 Plant Systems Steam Generator System........................... **
Main and Reheat Steam System (MRSS)............. 3.5-1 Steam Dump System (SDS)/ Turbine Bypass Control.. 3.5-5 Main Turbine Generator (MT/G) System ........... 3.5-9 Condenser Air Removal System (CARS)............. 3.5-21 Condensate System .............................. 3.5-25 Main Feedwater (MFW) System .................... 3.5-35 Auxiliary / Emergency Feedwater (AFW) System ..... 3.5-41 Service Water System (SWS)...................... 3.5-45
- See Section 3.2.1.
- See Section 3.4.1.
K/A catalog vi k__-- _______
CONTENTS (Continued)
Page 3.5.2 Emergency Plant Evolutions Steam Line Rupture.............................. 3.5-51 Loss of Condenser Vacuum........................ 3.5-54 Loss of Main Feedwater ......................... 3.5-56 3.6 Containment Integrity Systems and Malfunctions 3.6.1 Plant Systems _
l Pressurizer Relief Tank / Quench Tank System (PRTS) 3.6-1 Containment Cooling System (CCS)................ 3.6-5 Ice Condenser System............................ 3.6-9 Containment Spray System (CSS).................. 3.6-13 Containment Iodine Removal System (CIRS)........ 3.6-19 Hydrogen Recombiner and Purge Control System i (HRPS).......................................... 3.6-23 l Containment System ............................. 3.6-27 I 3.6.2- Emergency Plant Evolutions E Loss of Containment Integrity................... 3.6-31 s b p C 3.7 Electrical Systems and Malfunctions .,
} 3.7.1 -Plant Systems j
!5 AC Electrical Distribution System .............. 3.7-1 h j DC Electrical Distribution System .............. 3.7-7 y i Emergency Diesel Generator (ED/G) System ....... 3.7-11 g
[ 3.7.2 Emergency Plant Evolutions Loss of Offsite and Onsite
- Power................ 3.7-19 )
jE Loss of Offsite Power...........................
Loss of Vital AC Electrical Instrument Bus......
3.7-21 3.7-26 '
l Loss of DC Power................................ 3.7-28 1
- 3.8 Control Air Systems and Malfunctions
! 3.8.1 Plant Systems i, Ins trument Ai r System (IAS). . . . . . . . . . . . . . . . . . . . . 3. 8-1 Station Air System 3.8-5 (SAS)........................
4 3.8.2 Emergency Plant Evolutions
- Loss of Instrument Air.......................... 3.8-9 l Control Room Evacuation......................... 3.8-11
! 3.9 Instrumentation Systems and Malfunctions j 3.9.1 Plant Systems y Reactor Protection System (RPS)................. 3.9-1 l Nuclear Instrumentation System (NIS)............ 3.9-5 4 Non-Nuclear Instrumentation System (NNIS)....... 3.9-11
! - In-Core Temperature Monitor (ITM) System........ 3.9-15 h K/A catalog vii 1
, , - - , ~, - .- . - - -, - - . . . ~ . - - ._ - . - - - - - - - . - - - - . - - . ,
CONTENTS (Continued)
Page Area Radiation Monitoring (ARM) System.......... 3.9-19 Process Radiation Monitoring (PRfl) System....... 3.9-23 3.9.2 Emergency Plant Evolutions Loss of Source-Range Nuclear Instrumentation.... 3.9-27 Loss of Intermediate-Range Instrumentation...... 3.9-29 (
Area Radiation Monitoring System Alarms......... 3.9-31 3.10 Auxiliary Thermal Systems and Malfunctions 3.10.1 Plant Systems Component Cooling Water System (CCWS)........... 3.10-1 Circulating Water System........................ 3.10-9 3.10.2 Emergency Plant Evolutions Loss of Component Cooling Water................. 3.10-19 Loss of Nuclear Service Water................... 3.10-19 3.11 Indirect Radioactivity Release Control Systems and Malfunctions (J
) 3.11.1 Plant Systems ,
2 Containmen+ Purge System (CPS).................. 3.11-1 Spent Fuel Pool Cooling System (SFPCS).......... 3.11-5 Fuel Handling Equipment System (FHES)........... 3.11-9 Liquid Radwaste System (LRS).................... 3.11-13 Waste Gas Disposal System (WGDS)................ 3.11-17 Fire Protection System (FPS).................... 3.11-23 3.11.2 Emergency Plant Evolutions Fuel Handling Incident.......................... 3.11-27 Accidental Liquid Radioactive Waste Release..... 3.11-29 Accidental Gaseous-Waste Release................ 3.11-31 Plant Fire On Site.............................. 3.11-33 High Reactor Coolant Activity........ .......... 3.11-35 APPENDIX A COMPONENT KNOWLEDGES O
K/A catalog viii
_,,,y2 , - - L a- - - 2 .-- --m. - - - . - - - - - ~ ~ ~ -
i k
8
.i
'9L l i
.n.
- v. 7
.o i
a 1
s i
ORGANIZATION OF THE CATALOG i
i t
l l
e'
p k
1 ORGANIZATION OF THE CATALOG The organization of the main body of the catalog parallels the organization of the Institute of Nuclear Power Operations' (INPO) job-task analysis (JTA) from
) which it is derived. Knowledges and abilities (K/As) are grouped according to the 9
system or emergency evolution to which they pertain. This organization is shown schematically below.
PLANT-WIDE GENERIC KNOWLEDGES AND ABILITIES (36)
SAFETY FUNCTIONS (11)
P' Plant Systems (45)
Task Mode Knowledge Categories (K1 - K6)
, Ability Categories (Al - A4) t Emergency Plant Evolutions (38)
Knowledge Categories (EK1 - EK3)
Ability Categories (EA1 - EA2)
COMPONENTS (Appendix A)
Component Categories (8)
Knowledges D Abilities
- 1.1 System-Wide and Plant-Wide Generic Knowledges and Abilities I(m) v A group of 36 knowledges and abilities has been identified as generic to all systems (e.g., knowledge of radiation control requirements). These are gener-ally administrative knowledges and abilities with broad applicability across systems. They are listed in Section 2 of the catalog. The twelve system-wide generic K/As are repeated at the end of each system and nine of them are re-peated for each emergency plant evolution (EPE) because these pr .icular generic K/As can reflect different meanings (and importance) depending on the system c-emergency evolution context.
1.2 Safety Function Groupings Eleven major functions must be accomplished to ensure safe power plant opera-
- tion. The nuclear power plant safety functions are as follows
^
(1) Reactivity Control (2) RCS Inventory Control l (3) RCS Pressure Control (4) RCS Heat Transport (5) Secondary System Heat Transport (6) Containment Integrity (7) Electrical Distribution (8) Control Air Supply (9) Instrumentation
[T (10) Auxiliary Thermal Transport (11) Indirect Radioactivity Release Control Q'
K/A catalog 1-1
l 1
1 Plant systems and emergency plant evolutions (EPEs) are organized in these safety functions. Selection of systems and evolutions for this catalog was based on the relationship and importance of system function or malfunction to the 11 safety functions. It should be noted that four systems (RCS, CVCS, ECCS, and S/GS) each contribute to two safety functions. Also, because EPEs are linked to more than one system, they have been listed separately under the appropriate, related safett function following the plant systems in that safety function.*
- 1. 3 Knowledge and Ability Categories k
F 7 The K/As are contained within six broad knowledge types and four broad ability
) types for systems, and three broad knowledge types and two broad ability types for emergency evolutions. If there are no knowledge or ability statements fol-lowing a broad category, it indicates that no statements were rated in that category. These broad categories of knowledges and abilities are listed below.
Knowledge and Ability Categories for Plant Systems and Emergency Evolutions:
3 Plant Systems b.
K1 - Knowledge of the physical connections and/or cause-effect relation-2 ships between the (system) and the following systems:
K2 - Knowledge of power supplies to the following:
? K3 - Knowledge of the effect that a loss of (system) will have on the following:
K4 - Knowledge of (system) design feature (s) and/or interlock (s) which provide for the following:
K5 - Knowledge of the following theoretical concepts as they apply to the (system):
K6 - Knowledge of the applicable performance and design attributes of the following (system) components:
Al - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the (system) controls including:
A2 - Ability to (a) predict the impacts of the following malfunctions or operations on the (system); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A3 - Ability to monitor operation of the (system), including:
A4 - Abi . .y in manually operata and/or monitor in the control room:
- Each system has a three-digit identifier (e.g., 001 = control rod drive system). These identifiers are the same as those used by INP0. Emergency evolutions always have the three-digit identifier of 000.
K/A catalog 1-2
( Emergency Evolutions
() EK1 - Knowledge of the following theoretical concepts as they apply to the emergency task:
EK2 - Knowledge of the following components:
EK3 - Knowledge of the basis or reasons for the following:
EA1 - Ability to operate and monitor the following:
[ EA2 - Ability to determine and interpret:
More detailed or specific statements about components indicated under catego-ries K6 and EK2 are listed in Appendix A.
1.4 Components
- Basic components such as valves and pumps are found in many systems. The fol-lowing eight categories of components, for which additional K/As are presented, y are listed in Appendix A:
e i-(1) Valves (2) Sensors and Detectors (3) Controllers and Positioners (4) Pumps
,.l, b/
A) Centrifugal
{V Rotary Vane Positive Displacement Venturi (5) Motors (6) Heat Exchangers and Condensers (7) Demineralizers and Ion Exchangers (8) Breakers, Relays, and Disconnects These additional K/As are more detailed or specific than those appropriate for system listings, yet at the same time they are generic to the component types.
- 1. 5 Knowledge Importance Ratings Importance ratings of the K/As are given for R0s and for SR0s next to each knowledge and ability entry in the catalog. These ratings reflect the average ratings of individual NRC/ utility panel members. The rating scale is presented in Table 1.1.
Some importance ratings are followed by an asterisk or question mark. These l indicate variability in the rating responses. An asterisk indicates the rating f
spread was very broad. An asterisk can also signify that more than 15 percent l of the raters indicated that the knowledge or ability is not required for the l R0/SRO position at their plant, either because it refers to an inapplicable design feature or because it is the responsibility of someone else (e.g., SR0 (p) vs RO). A question mark indicates that more than 15 percent of the raters felt that they were not familiar with the knowledge or ebility as related to the par-(/ ,
ticular system or design feature. These marks indicate the need for examiners K/A catalog 1-3 1
to review plant-specific materials to determine whether or not that knowledge or ability is indeed appropriate for inclusion in any given examination.
Table 1.1 Importance* rating scale for R0/SR0 knowledges and abilities Rating Importance for Safe Operation 5 essential 4 very important 3 fairly important 2 of limited importance 1 insignificant importance
- /? indicates variability in the responses
- Importance includes direct and indirect impact of the K/A on safe plant operations in a manner ensur-ing personnel and public health and safety.
- 1. 6 Additional Organizational Details INP0 tasks are grouped into the following plant modes:
Generic (000)
Startup/ Shutdown (010)
Normal Operations (020)
Mode Change (030)
What If/ Abnormal (050)
The " generic" task mode groups K/As deemed appropriate to all tasks. In some cases, only a generic task mode appears. In other cases, where knowledges and their importance vary between task modes, several task modes appear. Tasks underlying each task mode are listed at the start of the mode.
The mode code also distinguishes emergency evolutions. For example, the first emergency plant evolution (EPE), " Continuous Rod Withdrawal," is given the EPE mode number 001.
Each knowledge listed in the catalog is identified by two characters (K1), which show the knowledge category, and the last two digits (01) show that this is the first knowledge within the K1 category. Similarly, the first ability category is identified as A1. To distinguish emergency plant evolution K/As from those for plant systems, an E has been placed before the knowledge (EK1) or ability (EA1) characters.
1.7 Acronyms and Terms AFAS auxiliary feed actuation signal AFW(S) auxiliary (/ emergency) feedwater (system)
ALARA as low as reasonably achievable A0V air operated valve ARM (S) area radiation monitor (monitoring) (system)
K/A catalog 1-4
- q. ATWS anticipated transient without scram I BIT boron injection tank V BWST borated water storage tank CARS condenser air removal system CAT chemical addition tank CCS containment cooling system CCW(S) component cooling water (system)
CEAC(S) control element assembly control (system)
CIRS containment iodine removal system COLSS core operating limit support system CPS containment purge system CRDM control rod drive mechanism CRDS control rod drive system CRT cathode-ray tube Crud corrosion product material floating in system CSAS containment spray actuation signal CSS containment spray system CVCS chemical and volume control system D/G diesel generator D/P differential pressure, or pressure difference, pressure drop DNB departure from nucleate boiling ECCS emergency core cooling system ECP estimated critical position (of control rods)
ED/G(S) emergency diesel generator (system)
EPE emergency plant evolution ESF engineered safety features p) CSFAS FHES FPS engineered safety features actuation system fuel handling equipment system fire protection system HPI/LPI high pressure or low pressure injection l HRPS hydrogen recombiner and purge control system j l
HVAC heating, ventilating and air conditioning l IAS instrument air system I&C instrumentation and controls i ICS integrated control system INPO Institute of Nuclear Power Operations ITM(S) in-core temperature monitor (system)
JTA job-task analysis K/As knowledges and abilities K-eff subcritical multiplication factor KSAs knowledges, skills, and abilities LOCA loss-of-coolant accident LRS liquid radwaste system LVDT linear variable differential transformer MFW(S) main feedwater (system)
M/G motor generator MOV motor-operated valve MRSS main and reheat steam system i MSIV main steam isolation valve I MTC moderator temperature coefficient l MT/G main turbine generator (system) nuclear instrumentation system l(A l
l V
)
NIS NNIS NPSH non-nuclear instrumentation system net positive suction head l NRC Nuclear Regulatory Commission l K/A catalog 1-5
P&ID piping (or process) and instrumentation diagram PDIL power dependent insertion limit PE0 plant equipment operator (auxiliary operator)
PORV power-operated relief valve PPDIL pre power dependent insertion limit Primary reference to reactor coolant system PRM(S) process radiation monitor (system)
PRT(S) pressurizer relief tank (system)
PTS pressurized thermal shock PWR pressurized water reactor PZR pressurizer PZR LCS pressurizer level control system PZR PCS pressurizer pressure control system Radwaste radioactive waste RCP(S) reactor coolant pump (system)
RCS reactor coolant system rem roentgen equivalent man, a measure of irradiation dose RHR(S) residual heat removal (system)
RMS radiation monitoring systems R0 reactor operator RPI(S) rod position indicator (or indication system)
RPS reactor protection system RWST refueling water storage tank SAS station air system SDS steam dump system Secondary reference to steam and feedwater system SFPCS spent fuel pool cooling system S/G(S) steam generator (system)
S/GB steam generator blowdown SCR silicon-controlled rectifier SDM shutdown margin SIS safety injection system SME subject matter expert 50P standard operating procedure SR0 senior reactor operator SS shift supervisor SUR startup rate SWS service water system T-ave. average reactor coolant temperature T-cold measured temperature of outlet T/G turbine generator T-ref. reference temperature for RCS Tech-Specs technical specifications UHI upper head injection VARS volt-amperes reactive VCT volume control tank WGDS waste gas disposal system 1.8 List of Systems by System Number The following list of systems by system number includes in parentheses the acronym for that system and the page number in this catalog where that system is addressed.
K/A catalog 1-6
Number System V 001 Control Rod Drive System (CROS) (3.1-1) 002 Reactor Coolant System (RCS) (3.2-1) 003 Reactor Coolant Pump System (RCPS) (3.4-1) 004 Chemical and Volume Control System (CVCS) (3.1-15) 005 Residual Heat Removal System (RHRS) (3.4-7) 006 Emergency Core Cooling System (ECCS) (3.2-9) 007 Pressurizer Relief Tank / Quench Tank System (PRTS) (3.6-1) 008 Component Cooling Water System (CCWS) (3.10-1) 010 Pressurizer Pressure Control System (PZR PCS) (3.3-1) 011 Pressurizer Level Control System (PZR LCS) (3.2-21) 012 Reactor Protection System (RPS) (3.9-1) 013 Engineered Safety Features Actuation System (ESFAS) (3.2-25) 014 Rod Position Indication System (RPIS) (3.1-31) 015 Nuclear Instrumentation System (NIS) 3.9-5) 016 Non-Nuclear Instrumentation System (NNIS) (3.9-11) 017 In-Core Temperature Monitor (ITM) System (3.9-15) 022 Containment Cooling System (CCS) (3.6-5)
?
(, 025 Ice Condenser System (3.6-9) 026 Containment Spray System (CSS) (3.6-13) 027 Containment Iodine Removal System (CIRS) (3.6-19) 028 Hydrogen Recombiner and Purge Control System (HRPS) (3.6-23) 029 Containment Purge System (CPS) (3.11-1) 033 Spent Fuel Pool Cooling System (SFPCS) (3.11-5) 034 Fuel Handling Equipment System (FHES) (3.11-9) 035 Steam Generator System (S/GS) (3.4-13) 039 Main and Reheat Steam System (MRSS) (3.5-1) 041 Steam Dump System (SDS)/ Turbine Bypass Control (3.5-5) 045 Main Turbine Generator (MT/G) System (3.5-9) 055 Condenser Air Removal System (CARS) (3.5-21) 056 Condensate System (3.5-25) 059 Main Feedwater (MFW) System (3.5-35) 061 Auxiliary / Emergency Feedwater (AFW) System (3.5-41) 062 AC Electrical Distribution System (3.7-1) 063 DC Electrical Distribution System (3.7-7)
( 064 Emergency Diesel Generator (ED/G) System (3.7-11)
K/A catalog 1-7
068 Liquid Radwaste System (LRS) (3.11-13) 071 Waste Gas Disposal System (WGDS) (3.11-17) 072 Area Radiation Monitoring (ARM) System (3.9-19) 073 Process Radiation Monitoring (PRM) System (3.9-23) 075 Circulating Water System (3.10-9) 076 Service Water System (SWS) (3.5-45) 078 Instrument Air System (IAS) (3.8-1) 079 Station Air System (SAS) (3.8-5) 086 Fire Protection System (FPS) (3.11-23) 103 Containment System (3.6-27)
- 1. 9 List of Emergency Plant Evolutions by EPE Mode Number The following list of emergency plant evolutions (EPE) by EPE mode number includes in parentheses some of the commonly used acronyms and the page number in this catalog where that emergency evolution is addressed.
Number EPE Mode 001 Continuous Rod Withdrawal (3.1-35) 003 Dropped Control Rod (3.1-38) 005 Inoperable / Stuck Control Rod (3.1-41) 007 Reactor Trip (3.1-43) 008 Pressurizer Vapor Space Accident (Relief Valve Stuck Open) (3.3-5) 009 Small Break LOCA (3.3-8) 011 Large Break LOCA (3.3-12) 015 RCP Motor Malfunction (3.4-17) 017 Partial Loss of Reactor Coolant Flow (3.4-17) 022 Loss of Reactor Coolant Makeup (3.2-29) 024 Emergency Boration (3.1-45) 025 Loss of Residual Heat Removal System (RHRS) (3.4-20) 02o Loss of Component Cooling Water (CCW) (3.10-19) 027 Pressurizer Pressure Control System (PZR PCS) Malfunction (3.3-15) 028 Pressurizer (PZR) Level Malfunction (3.2-31) 029 Anticipated Transient Without Scram (ATWS) (3.1-48) 032 Loss of Source-Range Nuclear Instrumentation (3.9-27) 033 Loss of Intermediate-Range Instrumentation (3.9-29) 036 Fuel Handling Incident (3.11-27) 037 Steam Generator (S/G) Tube Leak (3.3-17) 038 Steam Generator Tube Rupture (3.3-20)
K/A catalog 1-8
_ = - . - .
040. Steam Line Rupture (3.5-51) 051 Loss of Condenser Vacuum (3.5-54) 054 Loss of Main Feedwater (MFW) (3.5-56) 055 Loss of Offsite and Onsite Power (Station Blackout) (3.7-19) 056 Loss of Offsite Power (3.7-21) 057 Loss of Vital AC Electrical Instrument Bus (3.7-26) 058 Loss of DC Power (3.7-28) 059 Accidental Liquid Radioactive-Waste Release (3.11-29) 060 Accidental Gaseous-Waste Release (3.11-31) 061 Area Radiation Monitoring (ARM) System Alarms (3.9-31) 062 Loss of Nuclear Service Water (3.10-19) 065 Loss of Instrument Air (3.8-9) 067 Plant Fire On Site (3.11-33) 068 Control Room Evacuation (3.8-11) 069 Loss of Containment Integrity (3.6-31) 074 Inadequate Core Cooling (3.4-23) 076 High Reactor Coolant Activity (3.11-35) i i
K/A catalog 1-9
a O
bi 5l f
SYSTEM-WIDE AND PLANT-WIDE GENERIC KNOWLEDGES AND ABILITIES O
/% l (G
2 SYSTEM-WIDE AND PLANT-WIDE GENERIC KNOWLEDGES AND ABILITIES The system-wide and plant-wide generic K/As, listed below, are primarily adtrinistrative-type job requiremnts that are independent of individual systems. They can apply across all plant systems and emergency evolutions.
IMPORTANCE System-Wide Generic K/As R0 SR0
- 1. Knowledge of operator responsibilities during maintenance, 3.5 3.9 test, and surveillance activities.
- 2. Knowledge of system status criteria which require the 2.7 3.8 notification of plant supervisors or off plant personnel.
- 3. Knowledge of which events related to system operation / status 2.8 3.8 should be reported.
- 4. Knowledge of system purpose and/or function. 3.7* 4.0
- 5. Knowledge of the technical specification bases and definitions 2.9 3.9 related to limiting conditions for operations and safety limits.
ON 6. Ability to locate and operate components, using local controls 3.7 3.8 (outside the control room).
- 7. Ability to locate, explain, and apply all limits and 3.5 4.0 precautions.
- 8. Ability to recognize indications for system operating 3.5 4.5 parameters, which are entry level conditions for technical specifications.
- 9. Ability to verify system alarm setpoints and operate controls 3.8 4.0 identified in the alarm response manual.
- 10. Ability to recognize abnormal indications for system operating 4.1 4.5 parameters, which are entry-level conditions for emergency and abnormal operating procedures.
- 11. Ability to perform those actions, without reference to 4.3 4.4 procedure, for all casualties which require immediate operation of system components or controls.
- 12. Ability to perform specific system and integrated plant 3.7 4.0 operations during:
Controlled plant load change.................................. 3.4 3.3 Normal plant operations....................................... 3.5 3.3 Plant heatup and startup...................................... 3.5 3.4 Plant shutdown and cooldown................................... 3.5 3.4 K/A catalog 2-1
IMPORTANCE Plant-Wide Generic K/As R0 SRO
- 13. Knowledge of how to conduct and verify valve lineups. 3.7 4.0
- 14. Knowledge of tagging and clearance procedures. 3.6* 4.0
- 15. Knowledge of 10 CFR 20 and related facility radiation control 3.4 3.9 requirements.
- 16. Knowledge of facility ALARA program. 3.4 3.7
- 17. Knowledge of facility requirements for controlling access to 2.9* 3.5*
vital / control areas.
- 18. Knowledge of safety procedures related to:
Rotating equipment.......... ................... .. ... ...... 2.8 2.9 Electrical equipment............ ...................... ...... 3.0* 3.2*
High temperature....................... .... . ....... ....... 2.9 3.1 High pressure.......................... .. .......... ....... 3.1 3.3 Caustic solutions...... ..... ............................... 3.0 3.1*
Chlorine... ............................ ............. ....... 3.0* 3.2*
Noise.... ...................... .. ............. .. ...... . 2.3 2.6*
0xygen-deficient environment.................................. 3.0* 3.1*
Confined spaces............................................... 3.0 3.2 Hydrogen...... ............... ............................... 3.3 3.4
- 19. Knowledge of facility fire protection requirements, including 3.4 4.2 fire brigade and portable fire-fighting equipment usage.
- 20. Knowledge of the equipment rotation schedules and the 2.1 2.4 reasoning behind the rotation procedure.
- 21. Ability to obtain and verify control procedure copy. 3.8 4.1
- 22. Ability to execute procedural steps. 4.3 4.3
- 23. Ability to locate and use procedures and station directives 2.8 3. 5 related to shift staffing and activities.
- 24. Ability to operate the plant phone, paging system, and two-way 3.1 3.3 radio.
- 25. Ability to make accurate, clear, and concise verbal reports. 3.3 3. 7
- 26. Ability to maintain accurate, clear and concise logs, records, 3.3 3.6 status boards and reports.
- 27. Ability to obtain and interpret station electrical and 2.9 3.5 mechanical drawings.
- 28. Ability to obtain and interpret station reference material 2.9 3.5 such as graphs, nomographs, and tables which contain system performance data.
K/A catalog 2-2 I
IMPORTANCE O)
(s_, Plant-Wide Generic K/As R0 SRO
- 29. Ability to coordinate personnel activities inside the control 3.1 4.7 room.
- 30. Ability to coordinate personnel activities outside the control 3.5 4.5 room.
l 31. Ability to direct personnel activities inside the control room. 3.1 4.7
- 32. Ability to direct personnel activities outside the control 3.5* 4.5 room.
1
- 33. Ability to locate control room switches, controls, and 4.3 4.3
' indications, and to determine that they are correctly reflecting the desired plant lineup.
- 34. Ability to maintain primary and secondary plant chemistry 2.8* 3.3*
within allowable limits.
j 35. Ability to use plant computer or available calculator to 3.2 3.6 obtain and evaluate parametric information on system and component status.
- 36. Ability to take actions called for in the Facility Emergency 2.9* 4.7 Plan, including (if required) supporting or acting as the
!' Emergency Coordinator.
1 i
I t
\
i s
i i
d
)
i I
l 1
i K/A catalog 2-3
l O evere saeerv eu~crio~ oaoues se
?
i b
3 SYSTEM SAFETY FUNCTION GROUPS l :
1 l I l i i
.)
l 1 :
I f
t i ;
t 1 :
i
,1
)
i i
} ,
4 1
l
.a K/A catalog 3-1 ;
i i_ _
t . . . . . .
D E
o j Reactivity Control Systems and Malfunctions O
I lu u
t
\s /
SYSTEM: 001 Control Rod Drive System (CRDS)
TASK MODE: 000 Generic TASK: Perform full-length control rod assembly drop time test Disconnect and connect control rod drive shaft from control rod Perform safety group transfer operations between the dc hold and auxiliary power supplies Operate control rods to shape axial power Perform individual rod transfer operations between the normal and auxiliary power supplies Perform regulating group transfer operations between the normal and auxiliary power supplies De-energize a CRDM Operate control rods manually while the reactor is at power (Mode 1)
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the CRDS and the follow-ing systems:
[ \
K1.01 CCW..................................................... 3.0* 3.2*
\s_ l Kl.02 CVCS.................................................... 3.6* 3.7*
Kl.03 CRDM.................................................... 3.4 3.6 K1 04 RCS..................................................... 3.2* 3.A*
Kl.05 NISandRPS.............................................4.5 4.4 K2 Knowledge of bus power supplies to the following: ;
K2.01 One-line diagram of power supply to M/G sets............ 3.5 3.6 K2.02 One-line diagram of power supply to trip breakers. . . . . . . 3.6 3.7 K2.03 One-line diagram of power supplies to logic circuits.... 2.7* 3.1 K3 Knowledge of the effect that a loss of the CROS will have on the following-1 1
K3.01 CVCS.................................................... 2.9* 3.0*
i K3.02 RCS..................................................... 3.4* 3.5 3
K3.03 CCW..................................................... 2.2* 2.4*
I K4 Knowledge of CRDS design feature (s) and/or interlock (s)
! which provide for the following:
K4.01 Rod position indication................................. 3.5 3.8 K4.02 Control rod mode select control (movement control)...... 3.8 3.8 K4.03 Rod control 1ogic....................................... 3.5 3.8
/'~ K4.04 Circuitry and principle of operation for LVDT or reed
\ switch............................ ..................... 2.5 2.8 K/A catalog 3.1-1 1
SYSTEM: 001 Control Rod Drive System (CRDS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K4.05 Boration and dilution................................... 3.9* 3.9*
K4.06 Indication of what caused reactor trip (first-out panel)............ ..................................... 3.7 4.2 K4.07 Rod stops........ .... ................................ 3.7 3.8 K4.08 Prevention of excessive rod movement......... .......... 3.2^ 3.4 K4.09 Recovery of dropped rod................................. 3.9 4.1 K4.10 Trip signals that would prevent reset of reactor trip signals................................................. 3.6 3.8 K5 Knowledge of the following theoretical concepts as they apply to the CRDS:
K5.01 Understanding and app, station of individual and over-lapped rod bank curve' ............... . ............... 3.3 3.7 K5.02 Definitions of differt...tial rod worth and integral rod worth; their applicatior................................ 2.9 3.4 K5.03 Principles of operation of rod drive motor (magnetic jack or roller nut)..................................... 2.1 2.4 K5.04 Rod insertion limits... ................................ 4.3 4.7 K5.05 Interpretation of rod worth curves, including proper curve to use: all rods in (ARI), all rods out (AR0),
hot zero power (HZP), hot full power (HFP)......... . . . . 3. 5 3.9 K5.06 Effects of control rod motion on axial offset. ......... 3.8 4.1 K5.07 Effects of an asymmetric rod configuration on power distribution. ..........................................3.3 4.0 K5.08 Reasons for rod insertion limits and their effect on shutdown margin......................................... 3.9 4.4 K5.09 Relationships between reactivity due to boron and reactivity due to control rods.......................... 3.5 3. 7 K5.10 Effect of rod motion on core power distribution and RCS temperatures..................................... .. 3.9 4.1 K5.11 Relationship between reactivity worth of power-shaping control rod group and other control rod groups (power-shaping, or part-length, rods have much less reactivity than full-length control rods).......................... 3.1 3.6*
KS.12 Effects on power of inserting axial shaping rods........ 3.4* 4.1*
K5.13 Effects of past power history on xenon concentration and samarium concentratien.............................. 3.7 4.0 KS.14 Interpretation of isothermal temperature coefficient; ability to apply it with respect to isothermal tempera-ture defect............................................. 2.3 2.8 K5.15 Relationship between RCS temperature and MTC............ 3.4 3.7 K5.16 Relationship between RCS temperature and NDT of vessel.. 3.4 4.0 K5.17 Sources for adding positive reactivity.................. 4.2 4.2 K5.18 Anticipation of criticality at any time when adding positive reactivity during startup...................... 4.2 4.3 K/A catalog 3.1-2
- SYSTEM
- 001 Control Rod Drive System (CRDS)
(V TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.19 Reasons for using boron in the reactor.................. 3.1 3.4 K5.20 Effects of RCS temperature on boron reactivity worth.... 2.8 3.2 K5.21 Unit of measure of RCS boron concentration.............. 2.2 2.5 K5.22 Reason for use of peak samarium instead of equilibrium samarium in shutdown margin calculations................ 2.2 2.5 K5.23 Definition and effects of xenon absorption cross section. 2.2 2. 6 K5.24 Definition and effects of moderator absorption cross section................................................. 2 .1 2.4 K5.25 Definition and effects of moderator scattering cross section................................................. 1.8 2.1 K5.26 Definition of moderator temperature coefficient; appli-cation to reactor contro1............................... 3.3 3.6 K5.27 Interpretation of isothermal temperature coefficient; ability to apply it with respect to the isothermal temperature defect...................................... 2.4* 2.8*
K5.28 Boron reactivity worth vs. boron concentration, i.e.,
amount of boron needed (ppm) to change core reactivity n)
- V K5.29 K5.30 to desired amount.......................................
Effect on reactivity of changes in Effects of fuel burnout on reactivity in the core.......
T-ave................
3.5 3.7 2.9
- 3. 8 3.9 3.1 K5.31 Concept of equilibrium with respect to isotope produc-tion and decay.......................................... 2.6 3.0 KS.32 Fission process......................................... 2.5 2.8 K5.33 Xenon production and removal processes. . . . . . . . . . . . . . . . . . 3.2 3.5 K5.34 Effects of power level on peak samarium................. 2.1 2.2 K5.35 Methods of samarium production and removal.............. 2.1 2.3 KS.36 Significance of sign (always minus) of a calculated power defect............................................ 3.1 3. 4 K5.37 Sources of decay heat and ef fects on RCS. . . . . . . . . . . . . . . . 3.6 4.1 K5.38 Definition of xenon transient; causes; effects on r e a c t i v i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5 4.1 K5.39 Defini tion and uni ts of reactivity. . . . . . . . . . . . . . . . . . . . . . 2. 7 2. 9 K5.40 Definition of ppm....................................... 2.0 2.2 K5.41 Theory of radioactive decay of reactor poisons such as 13 8 1, t a n X e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4 2.8
, K5.42 Definitions of T-ave. and no-load T-ave................. 2.9 3.0 l K5.43 Definition of T-ref..................................... 3.2 3.4 K5.44 Definition of isothermal temperature defect............. 2.2 2.6 K5.45 Heat transfer formulas for primary and secondary coolant. 2.4 2.9 K5.46 Hot channel factors..................................... 2.3 3.6 K5.47 Factors af fecting SUR: p- e f f , A , p . . . . . . . . . . . . . . . . . . . . . 2. 9 3.4 K5.48 Definition of fuel temperature (Doppler) effect......... 3.3 3.5 i K5.49 Definitions and effects of factors affecting power defect:
( ) moderator temperature defect, fuel temperature defect, i ("j moderator vold defect, redistribution, individual contribution effects (the summation of all defects)..... 3.4 3.7 K/A catalog 3.1-3 l
L
SYSTEM: 001 Control Rod Drive System (CRDS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.50 Definition of moderator void defect..................... 2.2 2.5 K5.51 Defini tion of xenon oscillation. . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.7 j KS.52 Definition and purpose of axial of fset. . . . . . . . . . . . . . . . . . 3.0 3.6 K5.53 Definition of delta flux and its relationship to axial offset..................................................2.8 3.4 K5.54 Definition and units of reactivity...................... 2.8 3.1 K5.55 Definition and function of moderator.................... 3.0 3.2 K5.56 Determination of degrees of subcooling, using tempera-ture and pressure indications for primary coolant....... 4.2 4. 6 K5.57 Interpretation of rod drop test data.................... 2.2* 2.5 K5.58 Reason for overlap of control banks..................... 2.7 3.2 K6 Knowledge of the applicable performance and design attributes of the following CROS components:
K6.01 Control rod configuration and construction material..... 2.2 2. 5 K6.02 Purpose and operation of sensors feeding into the CROS.. 2.8 3. 3 K6.03 Reactor trip breakers, including controls............... 3.7 4.2 K6.04 Breakers, relays, and disconnects....................... 2.4 2.8 K6.05 Sensors and detectors................................... 2.4 2.7 K6.06 Motors..................................................2.1 2.1 K6.07 Transformers and voltage regulators..................... 1.8 2.0 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CROS controls including:
A1.01 T-ave. and no-load T-ave................................ 3.8 4.2 A1.02 T-ref...................................................3.1 3.4 A1.03 S/G level and pressure.................................. 3.6 3. 7 A1.04 PZR level and pressures................................. 3.7 3. 9 Effect on T-ave. of dilution without rod motion A1.05 compensation............................................ 3.4 3.9 A1.06 R e a c t o r p owe r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 .1 4.4 A2 Ability to (a) predict the impacts of the following mal-functions or operations on the CRDS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Loss of CCW or fan cooling.............................. 3.1 3.7 A2.02 Loss of power source to reactor trip breakers........... 3.8 /.3 K/A catalog 3.1-4
4:
CN SYSTEM: 001 Control Rod Drive System (CRDS)
(
v
) TASK MODE: 000 Generic Tasks as noted previously.
IMP 9RTANCE K/A NO. ABILITY R0 SRO A2.03 Effect of stuck rod or misaligned rod................... 3.5 4.2 A2.04 Positioning of axial shaping rods and their effect on SDM..................................................... 3.2* 3.8*
A2.05 Fractured split pins.................................... 1.9? 1.9?
A3 Ability to monitor automatic operation of the CRDS, including:
A3.01 Reactor power........................................... 4.1 4.0 A3.02 Rod height.............................................. 3.7 3.6 A3.03 Axial imbalance......................................... 3.6 3.8 A3.04 Radial imbalance........................................ 3.5 3.8 A3.05 Individual vs. group rod position....................... 3.5 3.5 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Controls for CCWS....................................... 3.1 2.9 A4.02 Boration/ dilution....................................... 4.1 3.9 h'qj A4.03 CRDS mode control....................................... 4.0 3.7 A4.04 Part-length rod position................................ 3.9* 3.6*
A4.05 Determination of the amount of boron needed to back the rods out of the core, including xenon effects if equi-l ibrium i s not yet achieved. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7 3.7 A4.06 Control rod drive disconnect / connect.................... 2.9 3.2 A4.07 Power source transfer check............................. 3.3? 3.3?
(O) v K/A catalog 3.1-5 -
)
SYSTEM: 001 Control Rod Drive System (CRDS)
TASK MODE: 010 Startup/ Shutdown TASK: Establish initial conditions for reactor startup Perform estimated critical position calculations Perform control rod programming verification Start up the CRDS Perform rod group latching and position indication alignment Manually trip the reactor Adjust overlap between sequential rods Perform a shutdown group withdrawal Operate the CRDS to bring the reactor critical Shift the control rod drive mode of control from manus 1 sequential to automatic sequential Shift the control rod drive mode between automatic and manual group or manual individual Shif t the control rod drive mode between manual group or manual individual and manual sequential Operate the CRDS to shut down the reactor Secure rod drive M/G sets Shut down the CRDS Start up rod drive M/G sets Perform SDM calculations IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the CRDS and the follow-ing systems:
Kl.01 WGDS.................................................... 1.7* 2.0*
Kl.02 Quench tank............................................. 1.7* 2.1*
K1.03 CCWS: must be shut down to prevent condensation on CRDM stators............................................ 2.2* 2.4*
K1.04 CCWS must be cut in before energizing CRDS.............. 2.8* 3.1*
K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the CROS will have on the following:
K4 Knowledge of CRDS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Resetting of CRDM circuit breakers...................... 2.7 2.9 K4.02 Rezeroing rod demand position counters.................. 2.5 2.6 K4.03 Operation of CRDS controls for withdrawing lingering rods and transferring rods and rod groups............... 3.4 3.4 K4.04 Operation parameters, including proper rod speed........ 2.6 2.8 K4.05 Operation of latching controls for groups and individ-ual rods................................................ 2.7 3.0 K4.06 Synchronization of power supplies to CRDS. . . . . . . . . . . . . . . 2. 2 2.4 K/A catalog 3.1-6
( SYSTEM: 001 Control Rod Drive System (CROS)
\s_, TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K4.07 Override (bypass) for rod bank motion when one rod is b o t t ome d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9* 3.1*
K4.08 Configuration of control / shutdown rods in core.......... 2.'1 2.5 K4.09 How contactors absorb arcing where used in conjunction with circuit breakers................................... 1.4 1.5 K4.10 The permissives and interlocks associated with increase from zero power......................................... 3.2 3.4 K4.11 Prevention of adverse chemical conditions............... 1.9 2.3 K4.12 Seismic considerations.................................. 1.4 1. 8 K5 Knowledge of the following theoretical concepts as they apply to the CRDS:
K5.01 Reasons for overlap of control rod banks for withdrawal and insertion........................................... 2.7 3.4 K5.02 Reason for using M/G sets to power rod control system... 1.9 2.4 K5.03 Operational theory for M/G sets......................... 1.5 1. 7 K5.04 Effects of RCS temperature on rod worth................. 2.2 2.8 K5.05 Meaning of zero SUR; reactor just critical or completely Ns- shutdown...............................................3.3* 3.4
- K5.06 Reason for withdrawing shutdown group
- to provide
! adequate shutdown margin................................ 3.3 3.8 l K5.07 CROS circuitry, including effects of primary / secondary powe r mi smatch on rod moti on. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2 3.6 l K5.08 Nucleonics associated with startup...................... 2.9 3.2 l K5.09 Understanding of " cold-water" (startup) accidents....... 3.4 3.8 K5.10 Purpose of overlap between source and intermediate range instrumentation......................................... 2.9 3.6 K5.11 Method used to parallel the rod control M/G sets........ 2.1 2.6 K5.12 Reason for maintaining cross-tie breaker between rod drive M/G sets; reliability of control rod drive trip
- breakers during operation of one M/G set................ 2.4 2.9 K5.13 Reactivity balance (shutdown withdrawal precedes dilution)...............................................3.1 3.6 K5.14 Need for maintenance of stable plant conditions during rod exercising.......................................... 2.7 3.1 K5.15 Reactor may not go critical upon withdrawal of a shut-down group.............................................. 3.7 4.0 l K5.16 Definition, uses, and calculation of 1/m plot........... 2.9 3. 5 l K5.17 Effects on power of inserting axial shaping rods........ 3.3* 3.7*
KS.18 Determination of the amount of boron needed to back out rods from the core, including effects of xenon.......... 3.2 3.6 K5.19 Response effects on T-ave, of dilution without rod
, motion..................................................3.3 3.5 K5.20 Effects of positioning of axial shape rods on 50M....... 3.0* 3.6*
K/A catalog 3.1-7 i
SYSTEM: 001 Control Rod Drive System (CRDS)
TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K5.21 Prediction of changes in boron concentration due to power operation, dilution, or boration.................. 3.4 3.9 K5.22 Determination (using plant curve book) of reactivity change associated with the difference in boron concentration........................................... 3.2 3.6 K5.23 Interpretion of differential and integral boron worth curves.................................................. 2.7 3.1 K5.24 Approximation of change in reactivity due to change in boron concentration (using differential boron thumb rule).................. ................................ 3.4 3.5 K5.25 Significance of sign change (plus or minus) in reactiv-ity due to change in boron concentration................ 3.3 3.5 K5.26 Estimation of xenon reactivity based on time to reach peak xenon after trip / shutdown, approximate peak xenon reactivities after shutdown from various power levels, approximate xenon worth during the decay process follow-ing peak worth.......................................... 3.5 3.7 K5.27 Significance of sign change (plus or minus) in reactiv-ity due to change in samarium level..................... 2.3 2.7 K5.28 Magnitude of heat decay as a function of time after shutdown................................................ 3.2 3. 5 K5.29 Effects of boron on temperature coefficient............. 2.9 3.4 K5.30 Relationships of axial offset to ECP: method of recov-ery from high power trip, allowing for xenon transient, with minimum boron movement............................. 2.3 3.2 K5.31 Estimation of core life based on RCS boron concentra-tion (correlation of estimated critical boron concen-tration with time in core life)......................... 2.3* 3.1*
K5.32 Estimation of samarium reactivity based on time to reach peak samarium after trip / shutdown, and on approx-imate peak samarium reactivities after shutdown from v a r i o u s p owe r l e v e l s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.4 K5.33 Comparison of actual data with historical data to deter-mine whether a trend exists............................. 2.1 3.1 K5.34 Axial offset problems caused by xenon oscillations (and their application to Tech-Spec power limitations)....... 3.2 41 K5.35 Definition of shutdown margin........................... 3.3 3.6 KS.36 Effect of reactor power changes on RCS temperature. .. ... 3.4 3.7 K5.37 Sign changes (plus or minus) in reactivity, cbtained when positive reactivities are added to negative reactivities............................................ 3.2 3.4 K6 Knowledge of the applicable performance and design attributes of the following CRDS components:
K6.01 Purpose and position switch of alarm for high flux at shutdown................................................ 2.98 3.2*
K/A catalog 3.1-8
p SYSTEM: 001 Control Rod Drive System (CRDS)
TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE ,
R0 SR0 K6.02 Purpose and operation of neutron flux recorder at high speed concentration..................................... 2.9* 2.9*
K6.03 Location and operation of rod control M/G sets and con-trol panel, including trips............................. 3.1* 3.3 K6.04 Location and operation of CRDS fault detection (trouble alarms) and reset system, including rod control annun-ciator.................................................. 2.9 3.2 K6.05 Location and interpretation of CRDS ac/dc status alarms. 2.9* 3.2*
K6.06 ' Lecation and operation of RPIS. . . . . . . . . . . . . . . . . . . . . . . . . . 3. 6 3.7 K6.07 Location and interpretation of reactor trip breaker..... 4.0 4.1 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CRDS controls including:
A1.01 RCS average temperature indications (T-ave.)............ 3.7 4.0 A1.02 Verification that CRDS temperatures are within limits y A1.03 before starting.........................................
Location and interpretation of RCS ter.iperature and 2.6 3.0 pressure indications.................................... 4.2 4.4 A1.04 Location and operation of controls and indications for CRDS component cooling water............................ 2.9 2.7 A1.05 Required primary system subcooling during shutdown; location of indication.................................. 3.7 3.9 A1.06 Estimation of decay heat load, in order to control RCS temperature with proper amount of heat removal.......... 2.9 3.4 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CRDS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunctions or operations:
A2.01 Effects of transient xenon on reactivity................ 3.4 3.7 A2.02 Effect of reactor trip on primary and secondary param-eters and systems....................................... 4.1 4.4 A2.03 Loss of CCW to CRDS..................................... 2.9 3.3 A2.04 Station blackout........................................ 3.8* 4.0 A2.05 Loss of power to one or more M/G sets................... 3.4 3.9 A2.06 Situations requiring a reactor trip..................... 4.4 4.7 A2.07 Erroneous ECP calculation............................... 3.6 4.2 p A2.08 ATWS.................................................... 4.4 4.6 V
K/A catalog 3.1-9
SYSTEM: 001 Control Rod Drive System (CRDS)
TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A3 Ability to monitor automatic operation of the CRDS, including:
A3.01 RCS temperature and pressure............................ 3.9 3.9 A3.02 Boration/ dilution....................................... 4.1 3.7 A3.03 Anticipation of criticality at any time when adding pos i ti ve reacti v i ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 9 4.0 A4 Ability to manually operate and/or monitor in the control room:
A4.01 Mode select for CRDS; operation of rod control M/G sets and control panel....................................... 3.7 3.4 A4.02 CCWS.................................................... 2.8 3.1 A4.03 De termi nati o n o f an ECP. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5 3.9 A4.04 Determination of S0M.................................... 3.5 4.1 O
O K/A catalog 3.1-10
/ T SYSTEM: 001 Control Rod Drive System (CRDS)
!j TASK MODE: 050 What If/ Abnormal TASK: Recover from a sequence inhibit situation Level a control rod while in the automatic mode of control IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the CRDS and the following systems:
K2 Knowledge of bus power supplies to the following:
K2.01 Control rod l i f t co i l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1* 2.7*
K2.02 M/Gsets................................................3.1* 3.5 K2.03 Circuit breakers........................................ 2.4 2.8 K2.04 Sensors and detectors................................... 2.1 2.4 K2.05 Motors.................................................. 1.7 2.1 K3 Knowledge of the effect that a loss of the CRDS will have on the following:
K4 Knowledge of CRDS design feature (s) and interlock (s) which provide for the following:
K4.01 Rod motion inhibit...................................... 3.4 3.8
'(
K5 Knowledge of the following theoretical concepts as they apply to the CRDS:
KS.01 Relationship of T-ave. to T-ref......................... 3.3 3.6 K5.02 Effect of adding high or low boron concentration to maintain T-ave, equal to T-ref.......................... 3.4 3.8 K6 Knowledge of the applicable performance and design attributes of the following CRDS components:
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CRDS controls including:
A1.01 "Prepower dependent insertion limit" and power dependent insertion limit, determined with metroscope............. 4.07 4.27 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CRDS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
x K/A catalog 3.1-11
SYSTEM: 001 Control Rod Drive System (CRDS)
TASK MODE: 050 What If/ Abnormal Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2.01 Urgent failure alarm, including rod-out-of-sequence and motion-inhibit alarms................................... 3.7 3.9 A2.02 Quadrant power tilt..................................... 3.6 4.2 A2.03 Possible causes o f mismatched control rods. . . . . . . . . . . . . . 3.0 3.8 A2.04 Rod-misalignment alarm...... ........ . ... .......... 3.3 3.8 A2.05 Incorrect rod stepping sequence... ............... ... 3.2 3.8 A2.06 Axi a l fl ux d i s tri buti on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 6 4.0 A2.07 Isolation of left coil on affected rod to prevent coil burnout......................... ..................... . 2.6* 3.6*
A3 Ability to monitor automatic operation of the CRDS, including:
A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Stopping T/G load changes; only make minor adjustments to prevent coil burnout.............................. .. 2.9* 2.9*
A4.02 Stopping other changes in plant, e.g., turbine, S/G, SDBCS, boration, before adjusting rods.................. 2.7* 2.9*
A4.03 Resetting rod control logic while recovering from mis-aligned rod, using instrument Tech-Specs................ 3.0 3.4 A4.04 Stopping boration/ dilution or other means of reactivity change while adjusting either rod position or T-ave..... 3.1* 3.1*
SYSTEM GENERIC K/As
- 1. Kr.owledge of operator responsibilities during maintenance, test, and surveillance activities. 3.6 4.1
- 2. Knowledge of system status criteria which require the noti-fication of plant supervisors or off plant personnel. 2.9* 3.9
- 3. Knowledge of which events related to system operation / status should be reported. 2.7 3.9
- 4. Knowledge of system purpose and/or function. 3.9 4.2
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.9 4.3
- 6. Ability to locate and operate components, using local con-trols (outside the control room). 3.8 3.7 K/A catalog 3.1-12
.O SYSTEM: 001 Control Rod Drive System (CRDS)
TASK MODL: 050 What If/ Abnormal Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.6 4.1
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3. 6 4.5
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.9 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.3 4.5
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.4 4.4
( 12. Ability to perform specific system and integrated plant opera-( tions during:
Controlled plant load change................................... 3.8 3.8 No rmal p l a n t op e ra ti o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7 3.7 Plant heatup and startup....................................... 3.7 3.7 l
Plant shutdown and coo 1down.................................... 3.7 3.7 i
(
K/A catalog 3.1-13
O f i V
SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 000 Generic TASK: Perform lineup of the CVCS Perform boron concentration dilution (bleed) of the RCS Perform boration (feed) for the RCS IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems:
K1.01 PZRLCS.................................................3.6 4.0 K1.02 PZR and RCS temperature and pressure relationships...... 3.5 3.8 K1.03 Operation, function and control of T/G.................. 2.2 2.6 K1.04 RCPS, including seal injection flows.................... 3.4 3.8 K1.05 CRDS operation in automatic mode control................ 2.7* 3.2 K1.06 Makeup system to VCT.................................... 3.1 3.1 K1.07 NIS..................................................... 2.6 2. 9 K1.08 Interface of CVCS with PRT.............................. 2.2 2.4 K1.09 Relationship between CVCS and RPIS...................... 2.2* 2.7*
'~N Kl.10
/ Pneumatic valves and RHRS............................... 2.7 2.9
('~ K1.11 Expected PRT response when opening PORV during bubble formation in PZR........................................ 2.9 3.2 K1.12 Nitrogen systems........................................ 2.4 2. 6 Kl.13 Hydrogen systems........................................ 2.8 2.9 Kl.14 IAS..................................................... 2.6 2.8 Kl.15 ECCS.................................................... 3.8 4.0 Kl.16 Boric acid storage tank................................. 3.3 3.5 K1.17 PZR..................................................... 3.4 3.4 K1.18 CCWS.....................................................'2.9 3.2 Kl.19 Primary grade water supp1y. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7 2.9 K1.20 Location of sample points for chemically sampled fluid systems................................................. 1.7 2. 5 K1.21 WGDS.................................................... 2.4 2.8 K1.22 BWST.................................................... 3.4 3.7 K1.23 RWST.................................................... 3.4 3.7 K2 Knowledge of bus power supplies to the following:
K2.01 Boric acid makeup pumps................................. 2.9 3.1 K2.02 Ma k e u p p ump s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9 3.1 K2.02 C h a rg i n g p ump s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3 3.5 K2.04 BWST tank heaters....................................... 2.6 2.7 K2.05 M0Vs.................................................... 2.7 2.9 K2.06 Control instrumentation................................. 2.6* 2.7 K2.07 He a t t ra c i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7 3.2
\ 1 K/A catalog 3.1-15
SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K3 Knowledge of the effect that a loss of the CVCS will have on the following:
K3.01 CRDS (automatic)................................ ..... . 2.5* 2.9*
K3.02 PZRLCS..............................................3.7 4.1 K3.03 CCWS .................................... ........... .. 2.2 2.4 K3.04 RCPS.................... ............................... 3.7 3.9 K4 Knowledge of CVCS design feature (s) and/or interlock (s) which provide for the following:
K4.01 0xygen control in RCS................................... 2.8 3.3 K4.02 Control of pH, and range of acceptability............... 2.1 2.6 K4.03 Protection of ion exchangers (high letdown temperature will isolate ion exchangers)............................ 2.8 2.9 K4.04 Manual / automatic transfers of contro1................... 3.2 3.1 K4.05 Interrelationships and design basis, including fluid flow splits in branching networks (e.g., charging and seal injection f10w).................................... 3.3 3.2 K4.06 Isotopic control........................................ 2.3 2.7 K4.07 Water supplies.......................................... 3.0 3.3 K4.08 Hydrogen control in RCS................................. 2.8 3.2 K5 Knowledge of the following theoretical concepts as they apply to the CVCS:
KS.01 Importance of oxygen control in RCS..................... 2.7 3.3 K5.02 Explosion hazard associated with hyd ogen containing systems.................................................3.5 3.9 K5.03 Definition of pH, reasons for importance, range of acceptability in RCS......... .......................... 2.2 2.9 K5.04 Reason for hydrogen cover gas in VCT (oxygen scavenge).. 2.8 3.2 K5.05 Source of neutrons (leakage, effect of core life) and NIS indications......................................... 2.3* 2.8*
K5.06 Concept of boron " worth" or inverse boron " worth" (reactivity, pcm/ ppm)................................... 3.0 3.3 K5.07 Relationship between SUR and reactivity................. 2.8 3.2*
K5.08 Estimation of subcritical multiplication factor (K-eff) by means other than the 6-factor formula: relationship of count rate changes to reactivity changes............. 2.6 3.2*
K5.09 Thermal shock: high component stress due to rapid tem-perature change......................................... 3.7 4.2 K5.10 Importance of nil-ductility transition temperature in plant operations........................................ 3.2 3.7 K/A catalog 3.1-16
r _ __ __________ ____
/sm 'T SYSTEM: 004 Chemical and Volume Control System (CVCS)
(v ) TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K5.11 Thermal stress, brittle fracture, pressurized thermal shock................................................... 3.6 3.9 K5.12 Effects of temperature on corrosion..................... 2.3 2.7 K5.13 Galvanic and general corrosion.......................... 2.1 2.6 K5.14 Reduction process of gas concentration in RCS: vent-accumulated non-condensable gases from PZR bubble space, depressurized during cooldown or by alternately heating and cooling (spray) within allowed pressure band (drive mo re gas out of sol ution) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5 2.9
, K5.15 Boron and control rod reactivity effects as they relate toMTC..................................................3.3 3.5 K5.16 Source of T-ave. and T ref. signals to control and RPS.. 3.2 3.4 K5.17 Types and effects of radiation, dosimetry, and s hi el di ng- ti me-d i s tance. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 3.1 K5.18 Relationship between neutron flux and reactivity. . . . . . . . 2.8 3.3*
K5.19 Co nce p t o f SDM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5 3.9 K5.20 Reactivity effects of xenon, boration, and dilution..... 3.6 3.7 f- s K5.21 Ppm and wei ght % for boron. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2 2.7
( ) K5.22 Ion bead degradation by temperature..................... 2.3 2.6
\__ ' K5.23 Radioactive decay of crud............................... 1.9 2.4 K5.24 Decontamination factors................................. 1.9 2.5*
K5.25 Channel i ng of i on exchanger. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.4 K6 Knowledge of the applicable performance and design attributes of the following CVCS components:
K6.01 Spray / heater combination in PZR to assure uniform baron concentration........................................... 3.1 3.3 K6.02 Demineralizers and ion exchangers....................... 2.5 2.1 K6.03 Valves.................................................. 2.4 2.5 K6.04 Pumps.......................................... ........ 2.8 3.1 K6.05 Sensors and detectors................................... 2.5 2.5 K6.06 Motors.................................................. 2.0 2.2 K6.07 Heat exchangers and condensers.......................... 2.7 2.8 K6.08 Breakers, relays, and disconnects....................... 2.0 2.2 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including:
A1.01 Activity levels in primary system....................... 2.9 3.8 Na i K/A catalog 3.1-17
SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based j on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 RCS pressure allowed to exceed limits................... 3.8 4.2 A2.02 Loss of PZR level (failure mode)........................ 3.9 4.2 A2.03 Boundary isolation valve 1eak. . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 6 4.2 A2.04 Unplanned gas release................................... 3.7* 4.1 A2.05 RCP seal failures....................... ............... 4.0 4.3 A2.06 Inadvertent boration/dil uti on. . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 2 4.3 A2.07 Isol ation of l etdown/ makeup. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4 3.7 A3 Ability to monitor automatic operation of the CVCS, including:
A3.1 Water and boron i nventory. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5 3.7 A3.2 Letdown isolation....................................... 3.6 3.6 A3.3 Ion exchange bypass.............. ...................... 2.9 2.9 A3.4 VCT pressure control.................................... 2.8 2.9 A4 Ability to manually operate and/or monitor in the control room:
A4.01 Boron and control rod reactivity effects..... .......... 3.8 3.9 A4.02 Calculation of ECP and related boration/ dilution /
reactivity relationships................................ 3.2 3.9 A4.03 Construction and use of 1/M plots (inverse multiplica-tion, criticality prediction method).................. . 2.7 3.2 A4.04 Calculation of boron concentration changes.............. 3.2 3.6 O
K/A catalog 3.1-18 1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ .J
im
( ) SYSTEM: 004 Chemical and Volume Control System (CVCS)
\/ m TASK MODE: 010 Startup/ Shutdown TASK: Perform lineups of the CVCS Perform boration system flow path verification Fill and vent the CVCS Perform boration flow path verification Start up the CVCS Perform borated water source operability verification What if RCS temperature starts to increase after placing demineralizer in service? ,
Nitrogen purge the VCT I Perform boric acid pump functional test What if estimated critical position is not calculated properly and reactor goes critical before it is expected?
Perform hydrogen purge and establish hydrogen overpressure Shut down the CVCS Operate the CVCS to increase the primary system pressure IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems:
Kl.01 RHRS.................................................... 3.4 3.9 fx
\
\~ s'b K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the CVCS will have on the following:
K3.01 RCPS.................................................... 3.4 3.9 K3.02 PZRLCS.................................................3.8 4.2 K4 Knowledge of CVCS design feature (s) and/or interlock (s) which provide for the following:
K4.01 High temperature limit on CVCS to protect ion exchange resins.................................................2.4 3.1 K4.02 Minimum temperature requirements on borated systems (prevent crystallization)............................... 3.2 3.8 K4.03 Temperature / pressure control in letdown line: prevent boiling, lifting reliefs, hydraulic shock, piping damage, and burst................. ............................. 3.1 3.6 K4.04 Minimum level of VCT......................... .......... 3.1 3.4 K5 Knowledge of the following theoretical concepts as they apply to the CVCS:
pumps................................................. . 3.1 3.2 (f-s x,) } K5.02 Reason for nitrogen purge of CVCS........... ....... ... 2.6 3.2 K5.03 Reason for " burping" non-condensable gases from VCT..... 2.4 3.0 K/A catalog 3.1-19
SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.04 Reason for sampling for chloride, fluoride, sodium and solids in RCS................ . .... ..... ........ 2.6 3.3 K5.05 Relationship between temperature and pressure in CVCS components during solid plant operation.. .. .. ... . . 3.8 4.2 K5.06 Purpose of flow path around boric acid storage tank ..... 3.0* 3.4*
K5.07 Purpose and control of heat tracing (prevent crystal-lization)............................ .................. 3.1 3.4 K5.08 Use of a boronometer............................ ....... 2.3* 2.6*
K6 Knowledge of the applicable performance and design attributes of the following CVCS components:
K6.01 Purpose of VCT divert valve.... ........... ............ 2.8 3.1 K6.02 Boric acid storage tank / boron injection tank recircula-tion flow path..... ............ ......... . ........... 2.7 3.1*
K6.03 Recirculation valve on boric acid storage tank (why it is closed during functional test)....... ............... 2.4* 2.7*
K6.04 Principle of recirculation valve: (permit emergency flow even if valve is blocked by crystallized boric acid).... 2.6? 2.9?
K6.05 Purpose and function of the boration/ dilution batch controller.. .. ... ...... ...................... . . . . . 3.1 3.3 K6.06 Recirculation path for charging pumps. ....... ......... 2.7 3.0 K6.07 Reason for venting VCT and pump casings while filling:
vents must connect to LRS.... ...... ... .... ..... . . . . 2. 8 3.1 K6.08 Purpose of spray nozzle in VCT.... .... .......... . . . 2. 3 2.6 K6.09 Flow paths for emergency boration. .......... ........ . 4.4 4.6 K6.10 Desica characteristics of boric acid transfer pump. ... 2.0 2.3 K6.11 Purpose of centrifugal pump miniflows (recirculation)... 2.3 2.6 K6.12 Function of demineralizer, including boron loading and temperature limits........ .............. .... ........ 2.5 3.1 K6.13 Design and purpose of charging pump desurger..... ... .. 2.1* 2.4*
K6.14 Design minimum and maximum flow rates for letdown system. 2.6 2. 9 K6.15 Capacity of boron recovery tanks: plan not to exceed by inefficient boron movement; interface with boron recovery system. ... ..... ... . . . ...... . .... .. 2.1* 2.7*
K6.16 Valves.... . ..... . .... .... . ... ......... . .. . 2.2 2.5 K6.17 Sensors and detectors........... ... .. . .... ... . . 2.1 2. 5 K6.18 Demineralizers and ion exchangers.. . ........ . . . . 2. 2 2.6 K6.19 Controllers and positioners. .. .. .. . . . 2.5 2.6 K6.20 Pumps. . . . .. . . .. . . 2.7 2.9 K6.21 Motors. . . .. . 2.0 2. 2 K6.22 Heat exchangers and condensers. . . . . . 2. 3 2.6 K6.23 Breakers, relays, and disconnects. . . . . . 1. 8 2.1 O
K/A catalog 3.1-20
SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls inciuding:
A1.01 T-ave. and T-ref................. .......... .. ........ 3.4* 3.6 A1.02 RCS pressure........... ... ................ ..... ... . 3.8 3.8 :
A1.03 PZR pressure and level....... ............. ............ 3.9 4.1 A1.04 S/G pressure and level....... ............ .......... .. 2.9* 3.2 A1.05 VCT level................... ................ .. ....... 3.0 3.2 --
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Loss of heat tracing........ ......... .......... ...... 3.0 3.7 A2.02 High primary and/or secondary activity........ ......... 3.0 3.9 A2.03 Inadvertent boration/ dilution....... ..... ............. 3.9 4.2 a=
A2.04 Loss of IAS...... ........................ ....... .... 3.6 4.2 A2.05 CIAS, SIAS..... ................ . .. ... . ........ . 4.1 4.3 A2.06 Low RWST.......... ............................. ....... 3.6 3.9 A2.07 Emergency boration... ........ .... ..... .. ....... 3.8* 3.9 A2.08 High or low PZR leve1..................... . .. .. ... 3.5 3.7 A2.09 T-ave. and T-ref. deviations.... ...... . . ............ 3.2 3.6 A2.10 Low PZR presssure................ . . ........ ...... 3.4 3.7 A2.11 High VCT level.. ... .................. .... ......... 3.1 3.1 A2.12 High secondary and primary concentrations of chloride, fluoride, sodium and solids......... ...... . ......... 2.e 3.s A3 Ability to monitor automatic operation of the CVCS, including:
A3.01 RCS pressure and temperature.... .... ..... .... . 3.9 3.9 A3.02 T-ave. and T-ref. ................ ......... ... ....... 3.9 3.8 A3.03 S/G level and pressure........... ........ ........... 3.3 3.3 A3.04 Reactor power.......... ................................ 3.9 3.9 A3.05 VCT level...... ........... . ... .... . ... ........ 3.3 3.2 A3.06 PZR level and pressure. ................... ..... ...... 3.9 3.9 A3.07 Charging / letdown...... ..... . .. ......... . . ....... 3.6 3.4 A4 Ability to manually operate and/or monitor in the control room:
A4.01 Letdown pressure and temperature control valves. ...... 3.6 3.1 A4.02 Letdown isolation and flow control valves.. . . . .... 3.6 3.1 K/A catalog 3.1-21 l
SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 010 Startup/ Shutdown d
Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A4.03 Boration/ dilution.. .... . . ........................... 3.9 3.7 A4.04 Charging...........................................3.8 3.4 A4.05 PZR spray and heater controls........................... 3.5 3.3 A4.06 Boric acid pumps.......................... .......... .. 3.6 3.2 A4.07 RCP seal injection..................................... . 3.4 3.3 9
i i
1 l
l O
K/A catalog 3.1-22
/"T SYSTEM: 004 Chemical and Volume Control System (CVCS)
! / TASK MODE: 020 Normal Operations v
TASK: Perform baron concentration change calculations Perform boron concentration dilution (bleed) of the RCS Perform boration (feed) of the RCS Shift to automatic feed and bleed of the RCS Operate a mixed-bed demineralizer Operate the cation bed demineralizer Operate a deborating demineralizer Perform RCS dilution using purification demineralizer in series with deborating demineralizer Deborate to a critical condition during reactor startup Monitor the CVCS operation Perform excess letdown to either VCT or radwaste Perform excess letdown to the reactor coolant drain /CVCS holdup tank Operate the CVCS to form a steam bubble in the PZR Operate the CVCS to collapse the steam bubble in the PZR Switch the letdown filters (post-demineralizer filters)
Operate letdown coolers Operate seal injection subsystem (auto-manual)
Vent a volume control / makeup tank (VCT)
Manual makeup to the VCT Perform low pressure purification using the RHRS Degas the RCS through the VCT Adjust the charging flow rate Adjust the letdown flow rate V) r
~
Change the seal injection filters Operate the CVCS to make up to the RWST Degas the RCS through the PZR IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K1 knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems:
Kl.01 Interface between HPI flow path and excess letdown f l ow p a t h . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7* 3.2*
K1.02 Flow path from CVCS to reactor coolant drain tank and holdup tank............................................. 2.7 2.8 Kl.03 Relationship between seal filter and letdown filter..... 2.3* 2.3*
K1.04 Interface between high-activity waste tank and letdown f i l te r d ra i n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1* 2.4*
K1.05 Effect and detection of leaking PORV or relief: on PZR level and pressure, including VCT makeup activity in automatic mode.......................................... 3.4 4.0 Kl.06 Relationship between letdown flow and RCS pressure. . . . . . 2.9 3.1 K1.07 Interface between CVCS and degassifier (WGDS)........... 2.3 2.5 K1.08 Minimum VCT pressure effect on RCP seals................ 2.8 3.1 O Kl.09 Interface between clean waste receiver tank and seal injection filters............... ....................... 2.3* 2.7*
K/A catalog 3.1-23
SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1.10 Interface between CVCS and reactor coolant drain tank and PZR PCS....... ...................................;.. 2.7 2. 9 Kl.11 Understanding of interface with LRS............... 2.5 2.8 K1.12 CCWS................ ............. .... ............ ... ... 2.6 2.8 K2 Knowledge of power supplies to the following:
K3 Knowledge of the effect that a loss of the CVCS will have on the following:
K3.01 RCS temperature and pressur............... 3.4
.... . ...... 3. 6 K3.02 PZR level and pie:,sure.......... . .................... 3.8 4.1 K3.03 RCP seal injection................ .....................3.6 3.8 K4 Knowledge of CVCS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Interlock between letdown isolation valve and flow K4.02 control valve..... ......................... ........... 3.2* 3.5*
Control interlocks on letdown system (letdown tank bypass valve)......................... ................. 2.8* 3.2*
K4.03 Interlocks associated with operation of orifice isola-K4.04 tion valves.. ...................... .. ................ 3.0*
3.4*}
Temperature at which the temperature control valve auto-matically diverts flow from the demineralizer to the ,
VCT; reason for this diversion...... ............... .. 2.6 3. 0 K5 Knowledge of the following theoretical concepts as they apply to the CVCS:
K5.01 For ion exchangers: demineralization, boration/
deboration, thermal regeneration, lithium control.... .. 2.4 2.8 K5.02 Heat exchanger principles and the effects of flow, tem-perature and other parameters. . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5 2.9 K5.03 Solubility of boron in water; temperature effect........ 2.5 2.8 K5.04 Ef fects of boron saturation on ion exchanger behavior. . . 2.6 3.1 K5.05 Use of thermal well for accessibility of resistance temperature detector................ ................... 1.4 1. 9 KS.06 Relationship between flow and pressure drop for fluids I passing through valves and orifices....... ....... ..... 2. 8 2.7 K5.07 Response of PRT during bubble formation in PZR: in- T crease in quench tank pressure when cycling PORV shows (
that complete steam bubble does not exist, that signifi-cant noncondensable gas is still present................ 3.C,g 3.4*
K5.08 Solubility of gases in solution: temperature and pres- ,
sure effects................... ........... ... .. ..... 2.3 2.6 K/A catalog 3.1-24
/^ ~ SYSTEM: 004 Chemical and Volume Control System (CVCS)
I D) TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.09 Solubility of boron in water: temperature effect....... 2.4 2.7 K5.10 Saturation, subcooling, superheat in steam / water........ 3.6 3.9 K5.11 Pressure response in PZR during in-and-out surge........ 3.2 3.4 K5.12 Resistance heating: power / current relations............ 1.8 2.1 K5.13 Reason for going solid in PZR (collapsing steam but'-
ble): make sure no steam is in PRT when PORV is opened to drain RCS..................................... 2.5* 2.9*
K5.14 Reason for second CCW pump when second heat exchanger is lined up............................................. 2.4* 2.9*
K5.15 Purpose of hydrogen purging and sampling processes. . . . . . 2.2 2.9 K5.16 Purpose and method of hydrogen removal from RCS before opening system: explosion hazard, nitrogen purge....... 2.7 3.3 K5.17 Design basis letdown system temperatures: resin integrity............................................... 2.6 2.7 K5.18 Operation principle of hydrogen catalytic recombiners. . . 1.9* 2.3*
K5.19 Reason for of reducing letdown rate when filling PZR; collapse steam bubb1e................................... 2.4 2.7 K5.20 Reason for keeping VCT pressure as low as possible f K5.21 during degas............................................
Calculation of rate of boron change in RCS as function 2.3 2. 6 flow rate............................................... 2.2 2.6 K5.22 Factors which effect changes in letdown temperature..... 2.3 2.4 K5.23 Sources of radio iodine in RCS (hazard in filter changeout).............................................. 2.1 2.7 K6 Knowledge of the applicable performance and design attributes of the following CVCS components:
K6.01 Tank capacity: RCS makeup, CVCS, and boron recovery system.................................................. 2.2 2.6 K6.02 Methods of pressure control of solid plant (PZR relief and water inventory).................................... 3.8 4.1 K6.03 Purpose of RHR relief and isolation valves.............. 3.4 3.6 K6.04 Interface between high-activity waste tank and letdown filter drain............................................ 2.2* 2.5*
K6.05 Reason for excess letdown and its relationship to CCWS.. 2.7 3.1 K6.06 Purpose and control of degassifier inlet and divert valves........................................ ......... 2.3* 2.5*
K6.07 Seal injection system and limits on flow range. . . . . . . . . . 3.1 3.5 K6.08 Venting of VCT: reduce concentration of gases in solution, keep stress in tank down...................... 2.1 2.5 K6.09 Principles of boronometer............................... 1.9* 2.1*
K6.10 Maximum allowable purge flow rate....................... 1.9 2.2 O K6.11 Relationship between VCT vent rate and vent header pressure..................................... ......... 2.2 2.5 K/A catalog 3.1-25
SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6.12 Letdown pressure control to prevent RCS coolant from flashing to steam in letdown piping........... .. ..... 2.9 3.1 K6.13 Boron loading of demineralizer resin............ ....... 2.9 3.4 K6.14 Valves. ... ......... .. ...... ........ .. . ........ 2.2 2.3 K6.15 Sensors and detectors...... ................. ..... ... 2.2 2.4 K6.16 Demineralizers and ion exchangers............ ... ..... 2.3 2.6 K6.17 Controllers and positioners.. ... .... . .. .. .. ... 2.4 2.4 K6.18 Pumps... ........ . .... ... ........ .................. 2.5 2.6 K6.19 Motors.................................................2.1 2.3 K6.20 Heat exchangers and condensers... ............ . .. .. 2.4 2.4 K6.21 Breakers, relays, and disconnects.................. . . . . 1. 8 2.2 K6.22 Methods of minimizing the amount of RCS coolant water processed and reducing the amount of waste water g e n e ra t e d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4 3.2 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including:
A1.01 Maximum specified letdown flow... ... .. . . .. .... 2.7 3.1 A1.02 Normal operating band for letdown flew rate. . . ........ 2.7 2.9 A1.03 RCS pressure and temperature. . ... ..... .......... . 3.6 3.8 A1.04 VCT level. . . ........... .. .... .............. ... . 2.8 3.0 A1.05 PZR pressure and level........ . .. ....... ..... ... 3.7 3.8 A1.06 Reactor power............ ... ..... ............ ...... 3.7 3.9 A1.07 S/G pressure and level....... ..... .. . .......... .... 2.9 3.0 A1.08 Letdown and charging flows.... ........................ . 3.0 3.0 A1.09 Rate of boron concentration reductian in RCS as a function of letdown flow while deborating demineral-izer is in service... .... ............................ 2.8 3.2 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Shifting demineralizer while divert valve is lined up to VCT...... ............. ................... . . . . 2. 7 2.7 A2.02 Excessive letdown flow, pressure, and temperatures or ion exchange resins (also causes)........... . ... .... 2.7 2.7 A2.03 Mismatch of letdown and changing flows. .... ........... 3.2 3.1 A2.04 High filter D/P... .. ........ . ..... .. .... .. . 2.6 2.7 K/A catalog 3.1-26
('~ ~ 1., SYSTEM: 004 Chemical and Volume Control System (CVCS)
(J ! TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2.05 Isolation of both letdown filters at one time: down-stream relief 1ifts..................................... 2.8 2. 8 A2.06 Uncontrolled boration or dilution....................... 3.8 4.3 A2.07 Low VCT pressure........................................ 2.8 3.0 A2.08 Improper RWST boron concentration....................... 3.5 4.2 A2.09 Depressurizing of RCS while it is hot................... 3.7 4.3 A2.10 Indication by increased letdown flow that demineral-izers are bypassed...................................... 2.3 2.4 A2.11 Reduction of baron concentration in the letdown flow; i ts ef fects on reactor operation. . . . . . . . . . . . . . . . . . . . . . . . 3. 3 3.6 A2.12 Potential for RCS chemical contaminatico when placin CVCS demineralizer in service.......................g.... 2.3 2.7 A2.13 Expected reactivity changes after valving in a new mixed-bed demineralizer that has not been preborated.... 3.4 3.9 A2.14 Fact that isolating cation demineralizer stops boron dilution and enables restoration of normal boron .
concentration........................................... 2.7 3.3
_s A2.15 Fact that for very low RCS boron concentrations, de-
[
} borating demineralizers may be more cost effective than
( ,,/ using makeup water...................................... 2.2* 2. 3 A2.16 Reactor trip............................................ 3.3 3.8 A3 Ability to monitor automatic operation of the CVCS, including:
A3.01 Interpretation of letdown demineralizer flow-divert valve position indicating lights. . . . . . . . . . . . . . . . . . . . . . . . 3. 0 2.7 A3.02 RCS temperature and pressure............................ 3.4 3.6 A3.03 Letdown and charging flows.............................. 3.4 3.1 A3.04 PZR pressure and temperature............................ 3.5 3.6 A3.05 VCTlevel...............................................3.2 3.0 A3.06 Reactor power........................................... 3.8 3.9 A3.07 S/G level and pressure.................................. 3.1 3.1 A3.08 Interpretation of emergency borate valve position indi-cating lights........................................... 3.8 4.2 A3.09 Interpretation of ion exchanger status light............ 2.3 2.4 A3.10 Interpretation of letdown orifice isolation valve posi-tion indicators......................................... 2.8 2.7 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Boration/ dilution batch contro1......................... 3.8 3.3 A4.02 Charging / letdown........................................ 3.7 3.3
('~'}
Q)
K/A catalog 3.1-27
SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A4.03 PZR sprays and heaters..... ..... .... ............... 3.7 3.3 A4.04 VCT level control and pressure control.... ............. 3.3 2.9 A4.05 Ion exchangers and demineralizers....................... 2.8 2.4 A4.06 Boron concentration.......... ....... . ........ ....... 3.6 3.7 A4.07 Activity levels of RCS and letdown......... ......... 2.7 3.5 A4.08 Deborating demineralizer.............. ........... ..... 2.7 2.7 A4.09 Emergency borate valve..... ............................ 4.3 4.1 A4.10 CVCS letdown orifice isolation valve and valve control switches................ .... ................. ..... 3.1 2.8 A4.11 Deborating demineralizer selector valve and selector valve control switch................ .......... ........ 2.6 2.5 A4.12 Letdown demineralizer flow divert valve control switch.. 2.6 2.3 A4.13 Boronometer chart recorder.............................. 2.5* 2.5*
A4.14 Calculation of the required volume through the deborat-ing demineralizer, using the appropriate equation....... 2.1 2.3 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.6 4.1
- 2. Knowledge of system status criteria which require the noti-fication of plant supervisors or off plant personnel. 3.0* 3.8
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.8
- 4. Knowledge of system purpose and/or function. 3.6 3.9
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.9 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.7 3.7
- 7. Ability to locate, explain, and apply all limits and precautions. 3.4 4.1
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for technical specifications. 3.6 4.4
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.9 3.6 K/A catalog 3.1-28
N SYSTEM: 004 Chemical and Volume Control System (CVCS)
TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures 4.3 4.5
- 11. Ability to' perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4. i
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change....................................-3.8 3.7 Normal plant operations........................................ 3.7 3.7 Plant heatup and startup....................................... 3.7 3.7 Plant shutdown and cooldown.................................... 3.7 3.7 K/A catalog 3.1-29
1 (N
. Q SYSTEM: 014 Rod Position Indication System (RPIS)
TASK MODE: 000 Generic i TASK: Start up the RPIS 1
Shut down the RPIS Record the primary coil voltage to verify rod position IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-
! effect relationships between the RPIS and the follow-
, ing systems:
i i
K1.01 K2.02 CRDS.................................................... 3.2* 3.6 NIS..................................................... 3.0 3.3 i
i K2 Knowledge of bus power supplies to the following:
i i
K2.01 K2.02 Reed switches........................................... 1.8 2.0 Metroscope.............................................. 1.9* 2.2 K2.03 Pulse counters.......................................... 1.7 2.1 i 7 -~3 k,_- K3 Knowledge of the effect that a loss of the RPIS will l have on the following:
K3.01 CRDS.................................................... 2.4 2.8*
1 K3.02 Plant computer.......................................... 2.5 2.8*
i K4 Knowledge of RPIS design feature (s) and/or interlock (s) which provide for the following:
1 K4.01 Upper electrical limit.................................. 2.5* 2.7*
K4.02 Lower electrical limit.................................. 2.5* 2.7*
K4.03 Rod bottom lights....................................... 3.2 3.4*
K4.04 Zone reference lights................................... 2.6* 2.9*
K4.05 Rod ho l d i n te rl oc ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.3
, K4.06 Individual and group misalignments...................... 3.4 3.7 Knowledge of the following theoretical concepts as they t
K5
! apply to the RPIS:
K5.01 Reasons for differences between RPIS and step counter... 2.7 3.0 K5.02 RPIS independent of demand position..................... 2.8 3.3 K5.03 Differences in accuracy of reed switches and pulse counters................................................ 2.1 2.3 K5.04 Concepts of magnetic flux and permeability of stainless i / ) steel housing........................................... 1.5 1.7 l
i f
3 K/A catalog 3.1-31 1
I
SYSTEM: 014 Rod Position Indication System (RPIS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6 Knowledge of the applicable performance and design attributes of the following RPIS components:
K6.01 Sensors and detectors................................... 2.3 2. 5 K6.02 Breakers, relays, and disconnects....................... 1.7 1.8 K6.03 Metroscope.............................................. 2.1* 2.6 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including:
A1.01 Metroscope reed switch display.......................... 2.9* 3.1 A1.02 Control rod position indication on control room panels.. 3.2 3.6 A1.03 PDIL, PPDIL............................................. 3.6? 3.8?
A1.04 Axial and radial power distribution..................... 3.5 3.8 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Loss of offsite power....................... ........... 2.8 3.3*
A2.02 Loss of power to the RPIS............................... 3.1 3.6 A2.03 Dropped rod............................................. 3.6 4.1 A2.04 Misaligned rod.......................................... 3.4 3.9 A2.05 Reactor trip............................................ 3.9 4.1 A2.06 Loss of LV0T............................................ 2.6* 3.0*
A2.07 Loss of reed switch..................................... 2.6 2.9 A3 Ability to monitor automatic operation of the RPIS, including:
A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Rod selection control........... .............. . ..... 3.3 3.1 A4.02 Control rod mode-select switch............... ...... .. 3.4 3.2 A4.03 Primary coil voltage measurement............. ....... . 2.6* 2.7*
A4.04 Rezeroing of rod position prior to startup.......... ... 2. 7 2. 7 O
K/A catalog 3.1-32
[ SYSTEM: 014 Rod Position Indication System (RPIS)
V) TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.1 3.5
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.6
- 3. Knowledge of which e/ents related to system operation / status should be reported. 2.4 3.7
- 4. Knowledge of system purpose and/or function. 3.4 3.7
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.9 3.9
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.5 2.7
/'N i i 7. Ability to locate, explain, and apply all limits and O precautions. 3.1 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for technical specifications. 3.6 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.2 3.2
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.3
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 4.2
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 3.1 3.2 Normal plant operations........................................ 3.1 3.1 Plant heatup and startup....................................... 3.1 3.1 Plant shutdown and cooldown.................................... 3.0 3.2 K/A catalog 3.1-33 s
n SYSTEM: 000 Emergency Plant Evolutions
-EPE MODE: 001 Continuous Rad Withdrawal IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they apply to the Continuous Rod Withdrawal emergency task:
EK1.01 P romp t c ri t i c al i ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 4
- 3.7 i EK1.02 SUR..................................................... 3.6 3.9 EKl.03 Relationship of reactivity and reactor power to rod movement................................................ 3.9 4.0 EK1.04 Effect of continuous rod withdrawal on insertion limits and SDM................................................. 3.7 3.9 EK1.05 Effects of turbine-reactor power mismatch on rod contro1................................................. 3.5 3.8 EK1.06 Relationship of reactivity and reactor power to rod ;
movement................................................ 4.0 4.2 EK1.07 Effects of power level and control position on flux..... 3.5 3.8 EKl.08 Control rod motion on S/G pressure...................... 2.9 3.2 1 EK1.09 Reason for use of pulse / analog converter (determination ,
of actual rod positions)................................ 2.1* 2.6 EK1.10 Definition of T-ave., T-ref., 'F, linear scale, % mega- ;
watts, reactor power, Kg/fe, pce, Ak/k, rate, % of i leve1................................................... 2.4 2.6 EK1.11 Definitions of core quadrant power tilt................. 2.8 3.3 ;
EK1.12 Long-range effects of core quadrant power tilt.......... 2.8 3.8 i EK1.13 Units of measure for power range indication............. 2.4 2.9 ;
EK1.14 Interaction of ICS control stations as well as purpose, j function, and modes of operation of 1C5................. 3.4* 3.7 :
EK1.15 Theory of operation of rod drive motors................. 1.7 2.0 EKl.16 Definition and application of power defect.............. 3.0 3.4 l EK1.17 MTC..................................................... 3.4 3.7 '
EKl.18 Fuel temperature coefficient............................ 3.4 3.8 ;
EK1.19 Voids coefficient....................................... 2.6 2.8 I EKl.20 Differential rod worth.................................. 3.1 3.3 !
EK1.21 Integral rod worth...................................... 2.9 3.2 l EK1.22 Delta flux (A1)......................................... 3.2 3.6 '
EK1.23 Calculation of power defect: algebraic sum of moderator temperature and fuel temperature defects................ 2.6 2.9 '
EK2 Knowledge of the following components:
EK2.01 Rod bank step counters.................................. 2.9 3.2 l EK2.02 Controllers and positioners............................. 2.4 2. 5 l EK2.03 Sensors and detectors................................... 2.3 2.6 EK2.04 Breakers, relays, disconnects, and control room switches. 2.4 2.6 ;
i h
t K/A catalog 3.1-35 ,
~-wm--r-.- ,,ww .,-.-e.-., , , , - ,nww.y-- wse-- .-.w_s---.--,,e,,m,y g- ,,- ,.w p w r-~ m m - - m
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 001 Continuous Rod Withdrawal IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 EK2.05 Rod motion lights....................................... 2.9* 3.1 EK2.06 T-ave./ref. deviation meter. ........................... 3.0* 3.1 EK2.07 Boric acid pump running lights.......................... 2.8 2.9 EK2.08 Individual rod display lights and indications. ....... 3.1 3.0 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Manually driving rods into position that existed before start of casualty...... ................ . ............. 3.2 3.6 EK3.02 Tech-Spec limits on rod operability..................... 3.2 4.3 ABILITY EAl Ability to operate and monitor the following:
EA1.01 Bank select switch.......... .......... ................ 3.5 3.2 EA1.02 Rod in-out-hold switch................................ . 3.6 3.4 EA1.03 Boric acid pump control switch...... .................3.4 3.2 EA1.04 Operating switch for emergency boration motor-operated valve operating switch.................................. 3.8 3.6 EA1.05 Reactor trip switches......... ........................ . 4.3 4. 2 EA1.06 Rod transfer switches.............................. .... 3.0* 2.9*
EA1.07 RPI..................................................... 3.3 3.1 EA2 Ability to determine or interpret:
EA2.01 Reactor tripped breaker indicator................. ..... 4.2 4.2 EA2.02 Position of emergency boration va1ve.................... 4.2 4.2 EA2.03 Proper actions to be taken if automatic safety functions have not taken place.................................... 4.5 4.8 EA2.04 Reactor power and its trend............................. 4.2 4.3 EA2.05 Uncontrolled rod withdrawal, from available indications. 4.4 4.6 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 3.1* 3.9
- 3. Knowledge of which events related to system operation / status should be reported. 3.0* 3. 9
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.0 3.2 K/A catalog 3.1-36
('~'N SYSTEM: 000 Emergency Plant Evolutions
( ) EPE MODE: 001 Continuous Rod Withdrawal v
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 7. Ability to locate, explain, and apply all limits and pre-cautions. 3.6 4.0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for technical specifications. 3.5 4.4
- 9. Ability to verify system alarm setpoints and operate con-trols identified in the alarm response manual. 3.6 3.7
- 10. Ability to recognize abnormal indications for system oper-ating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.0 4.4
- 11. Ability to perform those actions, without reference to pro-cedure, for all casualties which require immediate operation of s3 stem components or controls. 4.2 4.3 n
(o) i I
1 L
l t
i K/A catalog 3.1-37
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 003 Dropped Control Rod IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the Dropped Control Rod emergency task:
EKl.01 deason for turbine following reactor on dropped rod event................................................... 3.2 3.7 EK1.02 Effects of turbine-reactor power mismatch on rod control................................................3.1 3.4 EK1.03 Relationship of reactivity and reactor power to rod movement................................................3.5 3.8 EK1.04 Effects of power level and control position on a flux... 3.1 3.7 EK1.05 CVCS response to dropped rod............................ 2.3* 2.6*
EKl.06 Control rod motion on S/G pressure...................... 2.3 2.7 EK1.07 Effect of dropped rod on insertion limits and SDM....... 3.1 3.9 EKl.0L Reason for use of pulse / analog converter (determination of actual rod positions)................................ 2.1* 2.5*
EK1.09 Definition of T-ave., T-ref., F, linear scale, %
megawatts, reactor power, Kw/ft, pcm, Ak/k, rate,
%oflevel..............................................2.3 2.6 EKl.10 Definitions of core quadrant power tilt................. 2.6 2.9 EK1.11 Long-range ef fects of core quadrant power tilt. . . . . . . . . . 2. 5 3.5 EK1.12 Units of measure for power range indication............. 2.3* 2.5*
EKl.13 Interaction of ICS control stations as well as purpose, function, and modes of operation of 105. . . . . . . . . . . . . . . . . 3.2* 3.6 EK1.14 Theory of operation of rod drive motors................. 1.5 1.8 EKl.15 Definition and application of power defect.............. 2.8 3.0 EKl.16 MTC...................................................... 2.9 3.2 EKl.17 Fuel temperature coefficient........................... . 2.9 3.1 EKl.18 Voids coefficient....................................... 2.1 2.2 EKl.19 Differential rod worth.................................. 2.8 2.9 EK1.20 Integral rod worth...................................... 2.6 2.7 EK1.21 Delta flux (AI).......... .............................. 2.7 3.2 EKl.22 Calculation of power defect: algebraic sum of moderator temperature and fuel temperature defects................ 2.5 2.6 EK2 Knowledge of the following components:
EK2.01 Controllers and positioners............................. 2.1 2.1 EK2.02 Breakers, relays, and disconnects....................... 2.1 2.2 EK2.03 Metroscope.............................................. 3 . 1* 3.2*
EK2.04 Sensors and detectors................................... 2.4* 2.4 EK2.05 Cor. trol rod drive power supplies and logic circuits..... 2.5 2.8 EK3 Knowledge of the bases or reasons for the following:
EK3.01 When ICS logic has failed on a dropped rod, the load must be reduced until A flux is within specified target bank.................................................... 3.5* 3.9*
EK3.02 Reactor runback with a dropped control rod.............. 3.3* 3.7*
K/A catalog 3.1-38
[
p SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 003 Dropped Control Rod IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK3.03 Turbine automatic runback with reactor in order to balance power output.................................... 3.4* 3.7*
l EK3.04 Actions contained in E0P for dropped control rod........ 3.8* 4.1 EK3.05 Tech-Spec limits for reduction of load to 50% power if a flux cannot be brought back within specified target band............................................. 3.4* 4.1*
EK3.06 Reset of demand position counter to zero................ 2.7* 3.0*
EK3.07 Tech-Spec limits for T-ave.............................. 3.8* 3.9*
EK3.08 Criteria for inoperable control rods.................... 3.1 4.2 EK3.09 Recording of group bank position for dropped rod (ref-erence point used to withdraw dropped rod to equal height with other rods in the bank)..................... 3.0* 3.5*
EK3.10 RIL and PDIL............................................ 3.2? 4.2?
ABILITY J
EA1 Ability to operate and monitor the following:
l EA1.01 Demand position counter and pulse /anolog converter...... 2.9* 2.9 a EA1.02 Controls and components necessary to recover rod........ 3.6 3.4 CN EA1.03 Rod control switches.................................... 3.6 3.3 Q EA1.04 Control rod drive safety rod outlimit bypass switch or key.................................................. 3.4* 3.3*
EA1.05 Reactor power - turbine power........................... 4.1 4.1 EA1.06 RCS pres sure and temperature. . . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 0 4.1 EA1.07 In-core and ex-core instrumentation..................... 3.8 3.8 i EA2 Ability to determine or interpret:
EA2.01 Rod position indication to actual rod position.......... 3.7 3.9 EA2.02 Signal inputs to rod control system..................... 2.7 2.8 EA2.03 Dropped rod, using in-core /ex-core instrumentation, ,
in-core or loop temperature measurements................ 3.6 3.8 EA2.04 Rod motion stops due to dropped rod..................... 3.4* 3.6*
EA2.05 Interpretation of computer in-core TC map for dropped ,
I rod location............................................ 2.5* 3.2* ;
SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the noti-fication of plant supervisors or off plant personnel. 2.8* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.8 p 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.7 3.9 i
K/A catalog 3.1-39 I
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 003 Dropped Control Rod IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 6. Ability to locate and operate components, using local con-trols (outside the control room). 2.6 2.8
- 7. Ability to locate, explain, and apply all limits and i precautions. 3. 5 4.2
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for technical specifications. 3.4 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.6 3.6
- 10. Ability to recognize abnormal indications for system oper-ating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.6
- 11. Ability to perform those actions, without reference to pro-cedure, for all casualties which require immediate operation of system components or controls. 4.2 4.4 0
O K/A catalog 3.1-40
y- 's SYSTEM: 000 Emergency Plant Evolutions
) EPE MODE: 005 Inoperable / Stuck Control Rod v
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they apply to the inoperable / stuck control rod emergency task:
EKl.01 Axial power imbalance................................... 3.1 3.8 EKl.02 Flux ti1t............................................... 3.1 3.9 EKl.03 Xenon transient........................... . ........... 3.2 3.6 EKl.04 Definitions of axial imbalance, neutron error, power demand, actual power tracking mode, ICS tracking........ 3.0* 3.4*
EKl.05 Calculation of minimum shutdown margin.................. 3.3 4.1 EKl.06 Bases for power limit, for rod misalignment........ . .. 2.9 3.8 EK2 Knowledge of the following components:
EK2.01 Controllers and positioners...................... ...... 2.5 2.5 EK2.02 Breakers, relays, disconnects, and control room switches............................. .................. 2.5 2.6 EK2.03 Metroscope...... ................ ... ... ........ .... 3.l* 3.3*
EK2.04 Sensors and detectors... ............................... 2.4 2.6 EK3 Knowledge of the bases or reasons for the following:
('"'N EK3.01 Boration and emergency boration in the event of a stuck rod during trip or normal evolutions..... . ............ 4.0 4.3 EK3.02 Rod insertion limits.... ............................... 3.6 4.0 EK3.03 Tech-Spec limits for rod mismatch......... ............. 3.6 4. P EK3.04 Tech-Spec limits for inoperable rods....... ........... . 3.4 4. F EK3.05 Power limi ts on rod mi salignment. . . . . . . . . . . . . . . . . . . . . . . . 3.4 4. '!
EK3.06 Actions contained in E0P for inoperable / stuck control rod.................................................... . 3.9 4. 2 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 CRDS.................................................... 3.6 3.4 EA1.02 Rod selection switches.................................. 3.7 3.5 EA1.03 Metroscope...................................... ...... 3.4* 3.4*
EA1.04 Reactor and turbine power..................... . ....... 3.9 3.9 EA1.05 RPI............ .. ..................................... 3.4 3.4 EA2 Ability to determine or interpret:
EA2.01 Stuck or inoperable rod from in-core and ex-core NIS, in-ccre or loep temperature measurements................ 3.3 4.1 r-'s EA2.02 Difference bd. ween jog and run rod speeds, effect on CRDM of stuck rod....................................... 2.5* 3.0*
( )
v K/A catalog 3.1-41
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 005 Inoperable / Stuck Control Rod IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.03 Required actions if more than one rod is stuck or inoperable......................... . ........... ..... 3.5 4.4 EA2.04 Interpretation of computer in-core TC map for dropped rod location......... . ............. .... .... ........ 2.3* 3.4 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the noti-fication of plant supervisors or off plant personnel. 2.8* 3.6
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.7
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.7 4.1
- 6. Ability to locate and operate components, using local con-trols (outside the control room). 2.7 3.1
- 7. Ability to locate, explain, and apply all limits and precautions. 3.4 4.0
- 8. Ability to recognize indications for system operating parameters, which are entry level conditions for technical specifications. 3.5 4.4
- 9. Ability to verify system alarm setpoints and operate con-trols identified in the alarm response manual. 3.4 3.8
- 10. Ability to recognize abnormal indications for system oper-ating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.5
- 11. Ability to perform those actions, without reference to pro-cedure, for all casualties which require immediate operation of system components or controls. 4.4 4.3 O
K/A catalog 3.1-42
- - =_ - - - _ _ _ _
f'~'3 SYSTEM: 000 Emergency Plant Evolutions
) EPE MODE: 007 Reactor Trip IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the reactor trip emergency task:
EK1.01 Principles of neutron detection......................... 2.4 2.9 EKl.02 Shutdown margin......................................... 3.4 3.8 EK1.03 Reasons for closing the main turbine governor valve and the main turbine stop valve after a reactor trip.... 3.7 4.0 EKl.04 Decrease in reactor power following reactor trip (prompt drop and subsequent decay).............................. 3.6 3.9 EKl.05 Decay power as a function of time....................... 3.3 3.8 EK1.06 Relationship of emergency feedwater flow to S/G and decay heat removal foll ow ; .g reactor trip. . . . . . . . . . . . . . . 3. 7 4.1 EK2 Knowledge of the following components:
EK2.01 Sensors and detectors................................... 2.3 2.3 EK2.02 Breakers, relays and disconnects........................ 2.6 2.8 EK2.03 Reactor trip status pane 1............................... 3.5 3.6 EK2.04 Controllers and pocitioners............................. 2.3 2.4
/m\ EK3 Knowledge of the bases or reasons for the following:
EK3.01 Actions contained in E0P for reactor trip............... 4.0 4.6 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 T/G controls............................................ 3.7 3.4 EA1.02 MFW System.............................................. 3.8 3.7 EA1.03 RCS pressure and temperature............................ 4.2 4.1 EA1.04 RCP operation and flow rates............................ 3.6 3.7 EA1.05 Nuclear instrumentation................................. 4.0 4.1 EA1.06 Reactor trip (scram): verification that the control and safety rods are in after the trip................... 4.4 4.5 EA1.07 MT/G trip; verification that the MT/G has been tripped.. 4.3 4.3 EA1.08 AFW System.............................................. 4.4 4.3 EA1.09 CVCS........ ....................................... ... 3.2 3.3 EA1.10 S/G pressure............................................ 3.7 3.7 EA2 Ability to determine or interpret:
EA2.01 Decreasing power level, from available indications. . . . . . 4.1 4.3 EA2.02 Proper actions to be taken if the automatic safety func-tions have not taken place.............................. 4.3 4.6 EA2.03 Reactor trip breaker posi tion. . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 2 4.4 h('~'i K/A catalog 3.1-43
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 007 Reactor Trip IMPORTANCE K/A NO. ABILITY R0 SRO EA2.04 If reactor should have tripped but has not done so, manually trip the reactor and carry out actions in A TWS E 0 P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.4 4.6 EA2.05 Reactor trip first-out indication....................... 3.4 3.9 EA2.06 Occurrence of a reactor trip............................ 4.3 4.5 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the noti-fication of plant supervisors or off plant personnel. 3.2* 3.8
- 3. Knowledge of which events related to system operation / status should be reported. 3.1* 3.8
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2. 7 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.6 3.7
- 7. Ability to locate, explain, and apply all limits and precautions. 3.5 4.4
- 8. Ability to recognize indications for system operating parameters, which are entry level conditions for technical speci fications. 3.4 4.4
- 9. Ability to verify system alarm setpoints and operate con-trols identified in the alarm response manual. 3.4 3.7
- 10. Ability to recognize abnormal indications for system oper-ating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3. 9 4.6
- 11. Ability to perform those actions, without reference to pro-cedure, for all casualties which require immediate operation of system components or controls. 4.4 4.5 O
K/A catalog 3.1-44
/ s SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 024 Emergency Boration IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the emergency boration emergency task:
EKl.01 Relationship between boron addition and change in T-ave................................................... 3.4 3.8 EK1.02 Relationship between boron addition and reactor power... 3.6 3.9 EKl.03 Calculation of boration time from volumetric baron addition and addition rate............................ . 2.4 2.9 EKl.04 Low temperature limits for boron concentration.......... 2.8 3.6 EK2 Knowledge of the following components:
EK2.01 Va1ves.................................................. 2.7 2.7 EK2.02 Sensors and detectors................................... 2.1 2.2 EK2.03 Controllers and positioners............................. 2.6 2.5 EK2.04 Pumps................................................... 2.6 2.5 EK2.05 Motors.................................................. 2.1 2.1 EK2.06 Breakers, relays, and disconnects....................... 2.0 2.1 o EK3 Knowledge of the bases or reasons for the following:
V)
I EK3.01 EK3.02 When emergency boration is required.....................
Actions contained in E0P for emergency boration.........
4.1 4.2 4.4 4.4 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Use of spent fuel pool as backup to BWST................ 2.7* 3.4*
EA1.02 Boric acid pump.......................................... 3.7 3.5 EA1.03 Boric acid controller................................... 3.5 3.3 EA1.04 Manual boration va1ve................................... 3.6* 3.7 EA1.05 Performance of letdown system during emergency boration. 3.1 3.2 EA1.06 BWST temperature........................................ 3.2 3.1 EA1.07 BWST 1evel.............................................. 3.3 3.4 EA1.08 Pump speed controlled to protect pump seals............. 2.7* 3.0*
EA1.09 Safety injection........................................ 3.5* 3.5*
EA1.10 CVCS centrifugal charging pumps......................... 3.5* 3.4*
EA1.11 BIT suction and recirculation va1ves.................... 2.9* 2.7*
EA1.12 Normal boron flow meter................................. 2.4 2.3 EA1.13 Boric acid flow contro11er.............................. 3.2 3.0 EA1.14 RCS makeup isolation valve indicators................... 2.6* 2.4 i
EA1.15 Boric acid transfer pump speed selector switch and running lights.......................................... 3.1* 2.9*
l EA1.16 T-ave. meters........................................... 3.3 3.2 g) EA1.17 Emergency borate control valve and indicators........... 3.9 3.9 l
t (V EA1.18 EA1.19 Emergency boron flow meter..............................
Makeup control system selector switch for CVCS isola-3.7* 3.6*
tion va1ve.............................................. 3.2* 3.1*
K/A catalog 3.1-45 l
l
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 024 Emergency Boration IMPORTANCE K/A NO. ABILITY R0 SR0 EA1.20 Manual boration valve and indicators.................... 3.2* 3.3 EA1.21 CVCS charging pump miniflow isolation valves and indicators..................................... ........ 2.8* 2.7*
EA1.22 Safety injection valves, switches, flow meters, and indicators............................ ................ 3.2* 3.2 EA1.23 CVCS centrifugal charging pump switches and indicators.. 3.3* 3.3*
EA1.24 BIT inlet and outlet valve switches and indicators...... 3.2* 3.1*
EA1.25 Boration valve indicators............................... 3.4* 3.3 EA1.26 Boric acid storage tank................................. 3.3 3.3 EA2 Ability to determine or interpret:
EA2.01 Whether boron flow and/or M0Vs are malfunctioning, from plant conditions .................................. 3.8* 4.1 EA2.02 'Vhen use of manual boration valve is needed. . . . . . . . . . . . .
. 3.9 4.4 EA2.03 Correlation between boric acid controller setpoint and boric acid flow..................................... 2.9* 3.0 EA2.04 Availability of BWST.................................... 3.4 4.2 EA2.05 Amount of baron to add to achieve required SDM.......... 3.3 3.9 EA2.06 When boron dilution is taking place..................... 3.6 3.7 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the noti-fication of plant supervisors or off plant personnel. 2.9* 3.8
- 3. Knowledge of which events related to system operation / status should be reported. 2.9* 3.9
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8 4.1
- 6. Ability to locate and operate components, using local con-trols (outside the control room). 3.4 3.7
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.4 4.0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for technical speci-fications. 3.4 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.6 3.6
- 10. Ability to recognize abnormal indications for system oper-ating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.2 K/A catalog 3.1-46
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 024 Emergency Boration
^
SYSTEM GENERIC K/As p
- 11. Ability to perform those actions, without reference to pro-ccdure, for all casualties which require immediate operation of system components or controls. 4.0 4.0 i
G l
l' l
K/A catalog 3.1-47
I SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 029 Anticipated Transient Without Scram (ATWS)
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they apply to the ATWS emergency task:
EK1.01 Reactor nucleonics and therno-hydraulics behavior....... 2.8 3.1 EK1.02 Definition of reactivity................................ 2.6 2. 8 EKl.03 Ef fects of boron on reacti vi ty. . . . . . . . . . . . . . . . . . . . . . . . . . 3. 6 3.8 EK1.04 Interpretation of terms: milliamps, logs, mils, per-cent , and reacti vi ty uni ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2 2.5*
EK1.05 Definition of negative temperature coefficient as applied to large PWR coolant systems.................... 2.8 3.2 1
EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 1.9 2.1 EK2.02 Sensors and detectors................................... 2.2 2.5 EK2.03 Controllers and positions............................... 2.1 2. 3 EK2.04 Pumps.................................... .............. 2.1 2.1 EK2.05 Motors.................................................. 1.9 1. 9 EK2.06 Breakers, relays, and disconnects....................... 2.9* 3.1*
EK3 Knowledge of the bases or reasons for the following:
EK3.01 Verifying a reactor trip; methods....................... 4.2 4.5 EK3.02 Starting a specific charging pump....................... 3.1 3.1 EK3.03 Opening BIT inlet and outlet valves..................... 3.7* 3.6*
EK3.04 Closing the normal charging header isolation valves..... 3.1* 3.1*
EK3.05 Closing the centrifugal charging pump recirculation va1ve................................................... 3.4* 3.5*
EK3.06 Verifying a main turbine trip; methods. . . . . . . . . . . . . . . . . . 4.2 4.3 EK3.07 Using local turbine trip lever. . . . . . . . . . . . . . . . . . . . . . . . . . 3.1* 3.4*
EK3.08 Closing the main steam isolation valve.................. 3.6* 3.8 EK3.09 Opening centrifugal charging pump suction valves from RWST.................................................... 3.7* 4.0*
EK3.10 Manual rod insertion.................................... 4.1 4.1 EK3.11 Initiating emergency boration........................... 4.2 4.3 EK3.12 Actions contained in E0P for ATWS....................... 4.4 4.7 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Charging pumps.......................................... 3.4* 3.1 EA1.02 Charging pump suction valves from RWST operating switch. 3.6* 3.3 EA1.03 Charging pump suction valves from VCT operating switch.. 3.5* 3.2 EA1.04 BIT inlet valve switches................................ 3.9* 3.8*
EA1.05 BIT outlet valve switches............................... 3.7* 3.6*
EA1.06 Operating switches for normal charging header isolation valves.................................................. 3.2* 3.1 EA1.07 Operating switch for charging pump recirculation valve.. 3.4* 3.1*
K/A catalog 3.1-48
000 Emergency Plant Evolutions p) i SYSTEM:
EPE MODE: 029 Anticipated Transient Without Scram (ATWS)
- V IMPORTANCE K/A NO. ABILITY R0 SR0 EA1.08 Reactor trip switch pushbutton.......................... 4.5 4.5 EA1.09 Manual rod contro1...................................... 4.0 3.6 EA1.10 Rod control function switch............................. 3.6 3.2 EA1.11 Manual opening of the CROS breakers..................... 3.9* 4.1
- EA1.12 M/G set power supply and reactor trip breakers. . . . . . . . . . 4.1 4.0 EA1.13 Manual trip of main turbine............................. 4.1 3. 9 EA1.14 Driving of control rods into the core. . . . . . . . . . . . . . . . . . . 4.2 3.9 EA1.15 AFW system.............................................. 4.1 3. 9 EA2 Ability to determine or interpret:
EA2.01 Reactor nuclear instrumentation......................... 4.4 4.7 EA2.02 Reactor trip a1 arm...................................... 4.2 4.4 EA2.03 Centrifugal charging pump ammeter....................... 2.9* 3.1*
EA2.04 CVCS centrifugal charging pump operating indication..... 3.2* 3.3*
EA2.05 System component valve position indications............. 3.4* 3.4*
EA2.06 Main turbine trip switch position indication............ 3.8 3.9 EA2.07 Reactor trip breaker indicating lights. . . . . . . . . . . . . . . . . . 4. 2 4.3 EA2.08 Rod bank step counters and RPI.......................... 3.4 3.5 EA2.09 Occurrence of a main turbine / reactor trip............... 4.4 4.5 EA2.10 Positive displacement charging pumps.................... 3.1* 3.4*
v SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 3.0* 3.9
- 3. Knowledge of which events related to system operation / status should be reported. 2.9* 3.9
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 3.0 4.2
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.9 4.2
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.5 4.2
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for technical speci-fications. 3.5 4.4
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. . 3.5 3.7 V
l K/A catalog 3.1-49
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 029 Anticipated Transient Without Scram (ATWS)
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 10. Ability to recognize abnormal indications for system oper-ating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.5
- 11. Ability.to perform those actions, without reference to pro-cedure, for all casualties which require immediate operation of system components or controls. 4.5 4.7 O
l l
l l
l l
l i
- O K/A catalog 3.1-50
d u
R a
a al sl
~A I
RCS Inventory Control Systems O and Malfunctions O
.i v
i SYSTEM: 002 Reactor Coolant System (RCS)
TASK MODE: 000 Generic
! TASK: Perform lineups on the RCS Vent the CRDM Drain the.RCS Drain the S/G (primary side)
Drain the refueling cavity
. . Fill the refueling cavity IMPORTANCE K/A N0. -KNOWLEDGE R0 SRO 4
K1 Knowledge of the physical connections and/or cause-
, effect relationships between the RCS and the following systems:
K1.01 RWST.................................................... 3.7 3.9 Kl.02 CRDS.................................................... 2.9* 3.0*
j~
K1.03 Borated water storage tank.............................. 3.8 3.8 Kl.04 RCS vent system......................................... 2.8 3.2 Kl.05 PRT..................................................... 3.2 3.4 K1.06 CVCS.................................................... 3.7 4.0
(_ KI.07 Reactor vessel level indication system.................. 3.5* 3.7*
K1.08 ECCS.................................................... 4.5 4.6 K1.09 PZR..................................................... 4.1 4.1 K1.10 Reac tor cool ant d rai n tan k. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.8 3.1 Kl.11 S/GS, feedwater systems................................. 4.1 4.2 K1.12 NIS..................................................... 3.5* 3.6 Kl.13 RCPS.................................................... 4.1 4.2
- K1.14 Spent-fuel pool purification............................ 2.3 2.6 K1.15 Refueling canal......................................... 2.2 2.4 Kl.16 Refueling water purification............................ 1.9 2.2 i
] K2 Knowledge of bus power supplies to the following:
I K3 Knowledge of the effect that a loss of the RCS will have on the following:
K3.01 LRS................................................ ... 2.1 2.6 K4 Knowledge of RCS design feature (s) and/or interlock (s) which provide for the following:
i K4.01 Fi lli ng and drai ni ng the RCS. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7 3.0 K4.02 Monitoring reactor vessel leve1......................... 3.5* 3.8*
K4.03 Venting the RCS......................................... 2.9 3.2 K4.04 Filling and draining the refueling canal................ 2.2 2.7 K4.05 Detection of RCS leakage................................ 3.8 4.2
, K/A catalog 3.2-1 4
i
SYSTEM: 002 Reactor Coolant System (RCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K4.06 Prevention of missile hazards. ...... . .. . ...... 1.9 2.2 K4.07 Contraction and expansion during heatup and cooldown.. 3.1 3.5 K4.08 Anchorjng of components--i.e., loops, vessel, S/Gs, and coolant pumps....... .... . .. ..... . ... . 1.5 1.8 K4.09 Operation of loop isolation valves.... .. .......... 3.2* 3.2*
K4.10 Overpressure protection.. .. ... .. ... .. ..... .... 4.2 4.4 K5 Knowledge of the following theoretical concepts as they apply to the RCS:
K5.01 Basic heat transfer concepts... .. . .............. 3.1 3.4 K5.02 Purpose of vent flow path when draining. .... ....... 2.5 2.9 K5.03 Difference in pressure-temperature relationship between the water / steam system and the water / nitrogen system. .. 2.2 2.6 K5.04 Reason for requiring the plant to be in steady-state condition during RCS water inventory balance.... ...... 2.9 3.4 K5.05 Reason for drain tank pressure rise during water inven-tory operations.... . ........ .. ... .... ... .. .... 2.7 3.0 K5.06 Pressure, temperature, and volume relationships of nitrogen gas in association with water. .. ......... .. 2.3 2.6 X5.07 Reactivity effects of RCS boron, pressure and temperature............... . .. .. ..... .... . . .... 3.3 3.6 K5.08 Why PZR level should be kept within the programmed band. 3.4 3.9 K5.09 Relationship between pressure and temperature for water at saturation and subcooled conditions. .... .. ....... 3.7 4.2 K5.10 Relationship between reactor power and RCS differential temperature........... ... ..... ............ .. ...... 3.6 4.1 X5.11 Relationships between effects in the primary coolant system and the secondary coolant system.. .............. 4.0 4.2 K5.12 Relationship of temperature average and loop differen-tial temperature to loop hot-leg and cold-leg tempera-ture indications.... . .... . .... ................ . 3.7 3.9 K5.13 Causes of circulation. ...... .............. ..... .... 3.3 3.6 X5.14 Consequences of forced-circulation loss....... . .. . . 3.7 4.2 K5.15 Reason for maintaining subcooled margin during natural circulation.. .................. ....... .............. 4.2 4.6 K5.16 Reason for automatic features of the feedwater control system during total loss of reactor coolant flow....... 3.5* 4.0*
K5.17 Need for monitoring in-core thermocouples during natural circulation.. .......... .............. .... .... ...... 3.8 4.1 K5.18 Brittle fracture.. ......... ..................... ..... 3.3 3.6 K5.19 Neutron embrittlement. ...... .. ...... ...... ......... 2.6 2.9 K5.20 Corrosion control principles. .. .. ............ ..... 2.3 2.7 9
K/A catalog 3.2-2
i I
SYSTEM: 002 Reactor Coolant System (RCS) y TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6 Knowledge of the applicable performance and design attr 'butes of the following RCS components:
K6.01 RCS valves that may pose an unusually high radiological hazard because of trapped crud.......................... 2.2 2.9 K6.02 RCP.......................... ................ ......... 3.6 3.8 K6.03 Reactor vessel level indication................... ..... 3.1* 3.6*
K6.04 RCS vent valves......................................... 2.5 2.9 K6.05 Valves.. ................................ .............. 2.1 2.4 K6.06 Sensors and detectors......... .................... .... 2.5 2.8 K6.07 Pumps.......................... ........................ 2.6 2.9 K6.08 Controller and positioners....... ......... ............ 2.4 2.7 K6.09 Motors................. .............. ................. 2.1 2.5 K6.10 Breakers, relays, and disconnects............ .......... 2.2 2.4 K6.11 Thermal sleeves.......... ... .......................... 2.2 2.6 K6.12 Code safety valves....... ............... ............. 3.0 3.5 K6.13 Reactor vessel and i nternal s . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3 2.8
,-s K6.14 Core components.................... ....... ....... .... 2.2 2.8
/s i h ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCS controls including:
A1.01 Prima ry and secondary pressure . . . . . . . . . . . . . . . . . . . . . . . . . . 3.8 4.1 A1.02 PZR and makeup tank leve1............................... 3.6 3.9 A1.03 Temperature............................................. 3.7 3.8 A1.04 Subcooling margin....................................... 3.9 4.1 A1.05 RCS f10w................................................ 3.4 3.7 A1.06 Reactor power.......................... ................ 4.0 4.0 A1.07 Reactor di f ferential temperature. . . . . . . . . . . . . . . . . . . . . . . . 3.3 3.5 A1.08 RCS average temperature................................. 3.7 3.8 A1.09 RCS T-ave.................................... .......... 3.7 3.8 A1.10 RCS T-ref........................ ...................... 3.2 3.5 A1.11 Relative level indications in the RWST, the refueling cavity, the PZR and the reactor vessel during prepara-t i on fo r re fue l i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... 2.7 3.2 A1.12 Radioactivity level when venting CRDS. ....... ......... 2.9* 3.3 A1.13 Core exit thermocouples................................. 3.4 4.0 t
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based
/'~N on those predictions, use procedures to correct, con-( trol, or mitigate the consequences of those malfunc-i \ tions or operations:
K/A catalog 3.2-3
SYSTEM: 002 Reactor Coolant System (RCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A2.01 Loss of coolant inventory... ................... ....... 4.3 4.4 A2.02 Loss of coolant pressure........ ... . ........ . ... .. 4.2 4.4 A2.03 Loss of forced circulation.............. .... ... ... . 4.1 4.3 A2.04 Loss of heat sinks..... ................................ 4.3 4.6 A3 Ability to monitor automatic operation of the RCS, including:
A3.01 Reactor coolant leak detection system.... .............. 3.7 3.9 A3.02 Containment sound-monitoring system............ ........ 2.6* 2.8*
A4 Ability to manually operate and/or monitor in the control room:
A4.01 RCS leakage calculation program using the computer...... 3.5* 3.8*
A4.02 Indications necessary to verify natural circulation from appropriate level, flow, and temperature indica-tions and valve positions upon loss of forced circulation................ .. ............. ..... .... 4.3 4.5 A4.03 Indications and controls necessary to recognize and correct saturation conditions......... ......... .. .. 4.3 4.4 A4.04 The filling / draining of LPI pumps during refueling. . . . . . 2.8 2.6 A4.05 The HPI system when it is used to refill the refueling cavity. .. ..... .............. ....... ... ..... 2.8* 2.7*
A4.06 Overflow level of the RWST.... . ........ . .......... 2.9 2.7 A4.07 Flow path linking the RWST through the RHR system to the RCS hot legs for gravity refilling of the refueling cavity......... . .. ........ ..... .... .............. 2.8 3.1 A4.08 Safety parameter display systems. ............... ...... 3.4* 3.7*
O K/A catalog 3.2-4
SYSTEM: 002 Reactor Coolant System (RCS)
V TASK MODE: 020 Normal Operations TASK: Perform RCS water inventory balance Add nitrogen to the PZR Monitor the RCS Establish natural circulation IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems:
K1.01 MT/G.................................................... 3.5 3.8 K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the RCS will have on the following:
K3.01 Fuel.................................................... 4.2 4.5 K3.02 Containment............................................. 4.2 4.6 K4 Knowledge of RCS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Detection of RCS leakage................................ 3.6 3.8 K4.02 Prevention of missile hazards........................... 2.1 2.4 K4.03 Contraction and expansion during heatup and cooldown.... 3.1 3.4 K4.04 Anchoring of components, i.e., loops, vessels, S/Gs, coolant pumps........................................... 1.9 2.1 K5 Knowledge of the following theoretical concepts as they apply to the RCS: ;
K5.01 Basic heat transfer concepts............................ 3.2 3.6 K5.02 Reason for requiring the plant to be in steady-state condition during RCS water inventory balance. . . . . . . . . . . . 3.1 3.4 K5.03 Reason for drain tank pressure rise during water inven-tory operations......................................... 2.9 3.3 K5.04 Reactivity affects of RCS boron, pressure and temperature............................................. 3.6 ~.9 K5.05 Why PZR level should be kept within the programmed band., 3.3 3.8 K5.06 Pressure-temperature relationship for water at satura-tion and subcooled conditions........................... 3.4 3.8 K5.07 Relationship between reactor power and RCS differential temperature............................................. 3.6 3.9 K5.08 Relationships between effects in the primary coolant system and the secondary coolant system................. 3.8 4.1 7
K/A catalog 3.2-5
1 SYSTEM: 002 Reactor Coolant System (RCS)
TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.09 Relationship of temperature average and loop differen-tial temperature to loop hot-leg and cold-leg indica-tions. ........... .. ......................... .. ... 3.6 3.9 K5.10 Causes of natural circulation.. .... .... ........ .... 3.5 3.9 K5.11 Consequences of forced-circulation loss.... .. ....... 3.8 4.1 K5.12 Reason for maintaining subcooled margin during natural circulation..... ..... .. .... ... ................ ... 4.1 4.3 K5.13 Reason for automatic features of the feedwater control system during total loss of reactor coolant flow. ..... 3.3* 3.7*
K5.14 Need for monitoring in-core thermocouples during natu-ral circulation.......... .............. ..... ..... . 3.7 4.2 K6 Knowledge of the applicable _p_e_rformance and design attributes of the following RCS components:
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding desi_gn limits) associated with operating the RCS controls including:
A2 Ability to (a)J redict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A3 Ability to monitor automatic operation of the RCS including:
A3.01 Pressure, temperatures, and flows.. . . .. ........ .... 4.4 4.6 A4 Ability to manually _pperate and/or monitor in the control room:
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.6 4.1
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.8 K/A catalog 3.2-6
f
/ 'h SYSTEM: 002 Reactor Coolant System (RCS)
(s_,/ TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 4. Knowledge of system purpose and/or function. 3.9 4.1
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.9 4.1
- 6. Ability to locate and operate components, using local controls j (outside the control room). 3.6 3.7
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.7 4.3
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Spect-fications. 3.5 4.4
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.7 3.9 s_- 10. Ability to recognize abnormal indications for system operating ,
parameters, which are entry-level conditions for emergency and
- abnormal operating procedures. 4.4 4.6
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of j system components or controls. 4.6 4.6
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 3.7 3.6 Normal plant operations........................................ 3.8 3.7 Plant heatup and startup.................. . ................ 3.6 3.7 Plant shutdown and coo 1down.................................... 3.7 3.7 i
l\
K/A catalog 3.2-7
,a \
i t !
'd SYSTEM: 006 Emergency Core Cooling System (ECCS)
TASK MODE: 000 Generic TASK: Perform ECCS pump operability checks Fill the high pressure SIS Fill the accumulators / core flood tanks / safety injection tanks Perform core ficading isolation valves alarms actuation test Drain the accumulators / core flood tanks / safety injection tanks Perform ECCS leak rate test Fill the boron injection tank Perform safety injection tank outlet isolation valve test Prepare the SIS for a normal plant startup Fill the refueling / borated water storage tank Perform high-head safety injection test and flushing of stainless steel pipe Recirculate and/or purify the refueling / borated water storage tank Adjust HPI flow Prepare the high pressure SIS for shutdown Secure the high pressure SIS Drain the high pressure SIS
'~
/ 's IMPORTANCE
{V) K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following systems:
K1.01 Spent fuel cooling system............................... 2.4* 2.8*
K1.02 E S FA S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3 4.6 K1.03 RCS..................................................... 4.2 4.3 K1.04 Auxiliary spray system.................................. 2.7* 2.8*
Kl.05 RCP seal injection and return........................... 2.8* 2.9*
K1.06 Liquid waste tank / reactor drain tank.................... 2.2 2.4 K1.07 MFW System.............................................. 2.9* 3.3*
K1.08 CVCS.................................................... 3.6 3.9 K1.09 Nitrogen................................................ 2.6 2.7 Kl.10 Safety injection tank heating system.................... 2.6* 2.8*
K1.11 CCWS.................................................... 2.8 3.2 K2 Knowledge of bus power supplies to the following:
K2.01 ECCS pumps.............................................. 3.6 3.9 K2.02 Valve operators for accumulators........................ 2.5* 2.9 K2.03 Heat tracing............................................ 2.3 2.5 K2.04 ESFAS-operated va1ves................................... 3.6 3.8 o
I \
G' K/A catalog 3.2-9
SYSTEM: 006 Emergency Core Cooling System (ECCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A h:1 KNOWLEDGE R0 SRO K3 Knowledge of the effect that a loss of the ECCS will have on the following:
K3.01 RCS.... ................ ........ ...................... 4.1* 4.2 K3.02 Fuel.......................... . .. ................. . 4.3 4.4 K3.03 Containment............ ....... ........................ 4.2 4.4 K4 Knowledge of ECCS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Cooling of centrifugal pump bearings............... .... 2.6 2.9 K4.02 Relieving shutoff head (recirculation)...... ........... 2.8 3.0 K4.03 Flushing of piping following transfer of highly concen-trated boric acid............. ........... ............. 2.4 2.5 K4.04 System venting.... ..................................... 2.3 2.5 K4.05 Auto s ta r t o f HP I/LP I/S I P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 3 4.4 K4.06 Cross-connection of HPI/LPI/ SIP......................... 3.9 4.2 K4.07 RHR pump test flow path................... ....... ..... 2.4 2.6 K4.08 Interlocks between RHR valves and RCS................... 3.2 3.5 K4.09 Safety injection valve interlocks...... . .............. 3.8 4.1 K4.10 Valves normally isolated from their control power....... 3.6* 3.7 K4.11 Interlocks to storage tank makeup valve................. 3.0 3.1 K4.12 Automatic closure of common drain line and fill valves to accumulator... ...................................... 3.2* 3.5*
K4.13 Bypassing / blocking ESF channels......................... 4.1 4.3 K4.14 Interlocks between RCP seal flow rate and standby HPI pump.................................................... 3.4* 3.7*
K4.15 Demineralized water supply to RWST.................. ... 2.3* 2.5*
K4.16 Water inventory control............. ................... 2.6 3.0 K4.17 Concentrated boric acid supply to RWST.................. 2.8 3.2 K4.18 Pa ra l l el redunda n t sy s tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3 3.8 K4.19 Alarm for misalignment of the accumulator isolation valve................................................... 2.9 3.4 K4.20 RHR..................................................... 3.2 3.5 K4.21 BIT recirculation........................... ........... 2.5* 2.9*
K4.22 Containment isolation................................... 3.6 3.9 K5 Knowledge of the following_ theoretical concepts as they apply _to the__ECCS:
K5.01 Effects of temperatures on water level indications...... 2.8 3.3*
K5.02 Relationship between accumulator volume and pressure.... 2.8 2.9 K5.03 Weight percent calculation boron concentration........... 1.9 2.2 K5.04 Brittle fracture, including causes and preventative actions.................... ....... .................... 2.9* 3.1*
K/A catalog 3.2-10
SYSTEM: 006 Emergency Core Cooling System (ECCS) lO l
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 l K5.05 Effects of pressure on a solid system................... 3.4 3.8
, K5.06 Relationship between ECCS flow and RCS pressure......... 3.5 3.9 l
K5.07 Thermodynamics of water and steam, including subcooled ma rgin , superhea t , and satura tion. . . . . . . . . . . . . . . . . . . . . . . 3. 3 3.6 i K6 Knowledge of the applicable performance and design
- attributes of the following E'Cd components:
l l
K6.01 BIT / borated water sources............................... 3.4 3.9 l K6.02 Core flood tanks (accumulators)......................... 3.4 3.9 K6.03 Safety injection pumps.................................. 3.6 3.9 K6.04 Breakers, relays and disconnects........................ 2.1 2.5 K6.05 HPI/LPI cooling water................................... 3.0 3.5 K6.06 Isolation valves........................................ 2.3 2.7 K6.07 Drain and fill valves................................... 1.7 2.2 K6.08 Accumulator sample system............................... 1.7 1.9 ,
j K6.09 RWST purification system................................ 1.8 1.9 K6.10 Va1ves.................................................. 2.2 2.4 K6.11 Sensors and detectors................................... 2.3 2.7 K6.12 Controllers and positioners............................. 2.1 2.6 i K6.13 Pumps................................................... 2.6 2.9 l K6.14 Motors.................................................. 2.1 2.4 l K6.15 Filters................................................. 1.8 2.0 l K6.16 Demineralizers.......................................... 1.8 2.2 l K6.17 Heat exchangers and condensers.......................... 2.1 2.4 j K6.18 Subcooling margin indicators............................ 3.5 3.9 l
l ABILITY l
l l Al Ability to predict and/or monitor changes in parameters I (to prevent exceedjng_ design limits) associated with l operating the GCCS controls including:
A1.01 Avoidance of thermal and pressure stresses due to pump startup................................................. 3.1 3.4 A1.02 Boron concentration in accumulator, boron storage tanks. 3.0 3.6 A1.03 Flow rates in BWST/BW recirculation pumps............... 2.4 2.6 A1.04 D/P across accumulator isolation valve.................. 2.2 2.5*
A1.05 CCW flow (establish flow to RHR heat exchanger prior to placing in service)..................................... 2.9 3.3 A1.06 Subcooling margin....................................... 3.6 3.9 z)
K/A catalog 3.2-11
SYSTEM: 006 Emergency Core Cooling System (ECCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A2 Ability to (a) predict the impacts of the following malfunctions or operations ore the ECCS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 High bearing temperature................................ 2.9 3.1 A2.02 Loss of flow path....................................... 3.9 4.3 A2.03 System 1eakage..................................... .... 3.3 3.7 A2.04 Improper discharge pressure............................. 3.4 3.8 A2.05 Improper amperage to the pump motor..................... 3.4 3.5 A2.06 Wa t e r h a mm e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3 3.5 A2.07 Loss of heat tracing................................. .. 2.8 3.1 A2.08 Effect of electric power loss on valve position......... 3.0 3.3 A2.09 Radioactive release from venting RWST to atmosphere..... 2.6 3.2*
A3 Ability to monitor automatic operation of the ECCS, including:
A3.01 Accumulators............................................ 4.0* 3.9 A3.02 Pumps................................................... 4.1 4.1 A3.03 ESFAS-operated va1ves................................... 4.1 4.1 A3.04 Cooling water systems................................... 3.8 3.8 A4 Ability to manually operate and/or monitor in the control room:
A4.01 Pumps................................................... 4.1 3.9 A4.02 Va1ves.................................................. 4.0* 3.8 A4.03 Transfer from boron storage tank to boron injection tank................ ................................... 3.5* 3.5*
O K/A catalog 3.2-12
g l
r l,-s SYSTEM: 006 Emergency Core Cooling System (ECCS)
TASK MODE: 020 Normal Operations
((V)
TASK: Adjust accumulator / core flood tank / safety injection tank pressure Vent accumulation / core flood tank / safety injection tanks Monitor'the SIS Operate the SIS in the recirculation mode l IMPORTANCE K/A NO. KNOWLEDGE R0 SRO l
l K1 Knowledge of the physical connections and/or cause-effect relationships between the ECCS and the following sy_ stems :
K1.01 CVCS.................................................... 3.1 3.2 K1.02 Nitrogen system............. ........................... 2.6 2.9 v,1.03 Accumulator vent system................................. 2.4 2.6 K1.04 RCS..................................................... 3.7 3.8 K1.05 CSS. ................................................... 3.3* 3.6*
K1.06 IAS..................................................... 3.0 3.4*
K1.07 Accumulator drains...................................... 2.2* 2.2" K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the ECCS will
/'~'T have on the following:
! /
\' K4 Knowledge of ECCS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Recirculation of minimum flow through pumps............. 2.7 3.0 K4.02 Normal water supply for S15............................. 3.3 3.6 K4.03 Recirculation flowpath of reactor building sump......... 3.2* 3.6*
K4.04 Valve positioning on safety injection signal............ 3.8 4.2 K4.05 Redundant pressure meters............................... 2.9 3.2 K4.06 Reset of S1S.............................. ............. 3.9 4.2 K5 Knowledge of the following theoretical concepts as they apply to the ECCS:
K5.01 Theory of thermal stress................................ 2.5 2.9*
K5.02 Basic heat-transfer equation............................ 2.2 2.4*
K5.03 T h e o ry o f f l u i d f l ow . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4 2.6 K6 Knowledge of the applicable performance and design attributes of the following ECCS components:
K6.01 Pumps................................................... 2.8 3.1 K6.02 Valves.................................................. 2.6 2.8 ,
K6.03 Accumulators............................................ 3.0 3.2* '
K6.04 Motors.................................................. 2.4 2.5 K6.05 Heat exchangers and condensers.......................... 2.2 2.6
[V]
K/A catalog 3.2-13
SYSTEM: 006 Emergency Core Cooling System (ECCS)
TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO Al Ability to predict and/or monitor changes in parameters ho_preventexceedingdesignlimits)associatedwith operating.the ECCS controls including:
A1.01 Pressure, high and low............ ..................... 3.3 3.6 A1.02 Temperature, high motor and bearing..................... 2.8 3.1 A1.03 Pump amperage, including start, normal and locked....... 2.8 3.2 A1.04 CVCS letdown flow.. ......... ...... ................... 2.4 2.7*
A1.05 Boron concentration..................................... 3.1 3.4 A1.06 RHR heatup limits....................................... 2.9 3.4 A1.07 Accumulator pressure (level, boron concentration)....... 3.5 3.7 A1.08 Re a c to r ve s s e l l e v e 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5 3.8 A1.09 RWST l evel a nd tempe ra tu re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3 3.9 A2 Ability to (a) predict the impacts __ of the following malfunctionsoroperationsontheECCS;and(b) based on those_ predictions, use procedures to_ correct, control u or mitigate the consequences of those malfunctions or operations:
A2.01 Low boron concentration in S15.......................... 3.4 3.9 A2.02 Rupture of ECCS header.................................. 4.0 4.4 A3 Ability to monitor automatic operation of_the ECCS t including:
A3.01 Safety injection pumps.................................. 4.2 4.3 A3.02 Valve lineups.................................. ........ 3.9 4.7 A3.03 RHR pumps.................................... . ... ..... 3.6* 3.7 A3.04 Automatic transfer of ECCS flowpaths.................... 4.2 4.3 A4 Ability to manually _ operate and/or monitor in the control room:
A4.01 RHRS............................................. ...... 3.7* 3.6 A4.02 Transfer of ECCS flowpaths prior to recirculation....... 3.9 3.8 O
K/A catalog 3.2-14
SYSTEM: 006 Emergency Core Cooling System (ECCS) sg TASK MODE: 030 Mode Change TASK: Manually initiate safety injection IMPORTANCE i K/A NO. KNOWLEDGE R0 SRO
- K1 Knowledge of the physical connections and/or caus effect relationships between the ECCS and the fol_e-iowing systems
K1.01 ESFAS................................................... 4.2 4.4 ,
i K2 Knowledge of bus yower suppites to the following:
K3 Knowledge of the effect that a loss of the ECCS will have on the following:
, K4 Knowledge of ECCS design feature (sj and/or interlock (s) which provide for the fo1 Towing:
K4.01 Recirculation of minimum flow through pumps............. 2.7 3.1 K4.02 Normal water supply for $15............................. 3.4 3.8 K4.03 Recirculation flowpath of reactor building sump......... 3.4 3.6 K4.04 Valve positioning on safety injection signal............. 3.9 4.1
, K4.05 Redundant pressure meters............................... 3.3 3.6 Q K4.06 Reset of S15............................................ 3.7 4.1 K5 Knowledg_e of the following theoretical concepts as they apply __to the CCCS:
K5.01 Expected temperature levels in various locations of the RCS due to various plant conditions..................... 2.7 3.0 K5.02 Thermodynamics of water and steam....................... 2.8 3.2 :
l K6 Knowledge of the applicable pe_rformance and design
- attributes of the foTfowing_ECCS components
K6.01 HPI and LPI systems..................................... 3.7 3.9 ,
K6.02 Subcooled-margin indicators............................. 3.6 3.8 K6.03 Pumps................................................... 3.3 3.6 ABILITY i Al Ability A predict and/or monitor changes in parameters (to_ prevent exceedin.g design limitsf associated with operating. the ECCS controis inclu_ ding:
A1.01 RCS temperature, including superheat, saturation, and subcoo1ed............................................... 4.1 4.2 A1.02 ECCS flow rate.......................................... 4.2 4.3 J] /
A1.03 Reactor vessel 1evel.................................... 3.6 3.9 K/A catalog 3.2-15
SYSTEM: 006 Emergency Core Cooling System (ECCS)
TASK MODE: 030 Mode Change Tasks as noted previously.
IMPORTANCE K/A N0. ABILITY R0 SRO A2 Ability to (a) predict the impacts _.of the following ,
malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to_ correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Conditions requiring actuation of ECCS.................. 4.5 4.8 A3 Ability to monitor automatic operation _of the ECCS iidluding:
A4 Ability to_ manually operate and/or monitor in the control room:
A4.01 ESF control panel....................................... 4.4 4.4 A4.02 ECCS pumps and valves.................. ........ ....... 4.4 4.4 O
O K/A catalog 3.2-16
I i
i i
l SYSTEM: 006 Emergency Core Cooling System (ECCS) i TASK MODE: 050 What If/ Abnormal t
TASK: What if HPI is overpressurizing the reactor?
t IMPORTANCE K/A N0. KNOWLEDGE R0 SRO l
K1 Knowledge of the physical connections and/or cause-effect relationships between. the ECCS and the following systems:
K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the ECCS will have on the following: ,
K4 Knowledge of ECCS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Reset of $15............................................ 3.9 4.2 K4.02 HPI flow throttling..................................... 4.1* 4.3*
K4.03 Reset of containment i solation. . . . . . . . . . . . . . . . . . . . . . . . . . 3.8 4.1 K5 Knowledge of the following theoretical concepts as they apply to the ECCS:
( K5.01 Operation of pumps in paralle1.......................... 2.9* 3.1*
K6 Knowledge of the applicable performance and design attributes o' the following ECCS components:
ABILITY Al Ability to predict and/or monitor changes in parameters
[topreventexceedingdesignlimi.ts)associatedwith operating the ECCS controls including:
A1.01 PZR level and pressure.......... ....................... 4.0 4.3 A1.02 Subcooling..............................................4.0 4.4 A2 Ability _to (a) pr_ edict the impacts of the following l malfunctions __or operations on the ECCS; and (b) based on those predictions, use procedures to correct, con-trol. or mitigate the consequences of those malfunc-tions or operations:
A2.01 Inadvertent SIS actuation............................... 3.9 4.2 A3 Ability __to monitor automatic operation of_the ECCS, including:
b
'()
K/A catalog 3.2-17 I
t
i SYSTEM: 006 Emergency Core Cooling System (ECCS)
TASK MODE: 050 What If/ Abnormal >
Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A4 Ability to manually operate and/or monitor in the control room:
A4.01 ESF system, including reset.. ...... .......... .. .... 4.2 4.3 A4.02 PZR LC S a nd PZ R PC S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1 4.2 A4.03 Safety parameter display system.... .. ... . ... 3.8* 4.2*
A4.04 Overpressure protection system........... .... ......... 4.2 4.3 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.8 4.0
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 3.1* 3.8
- 3. Knowledge of which events related to system operation / status should be reported. 2.9* 3.9
- 4. Knowledge of system purpose and/or function. 4.2 4.3
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.2 4.3
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.8* 3.8
- 7. Ability to locate, explain, and apply all limits and precautions. 3.8 4.2
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for technical specifications. 3.6 4.4
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.8 4.0
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.5 4.7
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4.6 K/A catalog 3.2-18
,O SYSTEM: 006 Emergency Core Cooling System (ECCS)
\ TASK MODE: 050 What If/ Abnormal Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change........ .......................... 2.9* 2.9*
Normal plant operations........................................ 2.9* 2.9*
Plant heatup and startup....................................... 3.2* 3.3 Plant shutdown and cooldown.................................... 3.3* 3.3 1
l iq -
K/A catalog 3.2-19
t lG 1 V
SYSTEM: 011 Pressurizer Level Control System (PZR LCS)
TASK MODE: 000 Generic TASK: Operate PZR level control in manual Transfer from manual to automatic PZR level control Monitor the PZR LCS
- i. Place the PZR level programmer in manual IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the PZR LCS and the fol-lowing systems:
1 K1.01 CVCS.................................................... 3.6 3.9 K1.02 RCS..................................................... 3.7 3.8 K1.03 PZR PCS.... ................................... ........ 3.7 4.0 K1.04 RPS............................................. ....... 3.8 3.9 '
K1.05 Reactor regulating system............................... 3.47 3.5?
K2 Knowledge of bus power supplies to the following:
' - K2.01 Charging pumps.......................................... 3.1 3.2 K2.02 P Z R h e a t e r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 .1 3.2
. K2.03 Level channels and controllers.......................... 2.4* 2.4 K3 Knowledge of the effect that a loss of the PZR LCS will have on the following:
K3.01 CVCS.................................................... 3.2* 3.4
- ' K3.02 RCS..................................................... 3.5 3.7 i
K3.03 PZR PCS................................................. 3.2 3.7 i
K4 Knowledge of PZR LCS design feature (s) and/or inter-lock (s) which provide for the following:
- K4.01 Operation of PZR heater cutout at low PZR level......... 3.3 3.7 K4.02 PZR level controller.................................... 3.3 3.4 K4.03 Density compensation of PZR level....................... 2.6 2.9 ;
K4.04 PZ R l e v e l i n p u t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.0 3.3 K4.05 PZR level inputs to RPS................................. 3.7* 4.1*
j K4.06 Letdown isolation....................................... 3.3 3.7
- K4.07 Cold-calibrated channe1................................. 2.9 3.2 K5 Knowledge of the following theoretical concepts as they j apply-to the PZR LCS:
i / .
!l l
a i
t K/A catalog 3.2-21
SYSTEM: 011 Pressurizer Level Control System (PZR LCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.01 Theory of operation of bellows-type level detector...... 1.9 2.2 K5.02 Principle of operation for the charging pump electric pneumatic flow control valve..... ...................... 2.0* 2.2*
K5.03 Principle of operation of the charging flow sensor.. ... 1.7 1.9 K5.04 Reasons for not allowing coolant to flash into steam in the letdown piping. .................. ......... .. .... 2.5 2.9 K5.05 Interrelation of indicated charging flow rate with volume of water required to bring PZR level back to programmed level hot / cold................... ... ... .. 2.8 3.1 K5.06 Indicated charging flow: seal flow plus actual charging flow................................. .................. 2.9 3.2 K5.07 Definition of flow rate................... .. .... ..... 1.9 2.1*
K5.08 Relative flow rate through letdown subsystem as a func-tion of flow contro1..................... .............. 2.3 2.5*
K5.09 Reason for manually controlling PZR level........ ...... 2.6 2.7*
K5.10 Indications of reactor vessel bubble..... .............. 3.7 4.0 K5.11 Reasons for selecting " manual" on letdown control valve controller................... .... . ................. 2.5* 2.8*
K5.12 Criteria and purpose of PZR level program. . . . . . . . . . . . . . . 2.7 3.3 K5.13 Impact of high/ low PZR level on interrelated system..... 3.2* 3.4 K5.14 Sizing of the PZR for maximum insurge/outsurge.......... 1.9 2.2 K5.15 PZR level indication when RCS is saturated.............. 3.6 4.0 K6 Knowledge of the applicable performance and design attributes of the following PZR LCS components:
K6.01 Reasons for starting chargirg pump while increasing letdown flow rate....... . ........................... 2.8* 3.2*
K6.02 Relationship of makeup flow rite to throttle valve position..............................................2.2 2.5*
K6.03 Relationship between PZR level and PZR heater control circuit................................................. 2.9 3.3 K6.04 Operation of PZR level controllers...................... 3.1 3.1 K6.05 Function of PZR level gauges as postaccident monitors... 3.1 3.7 K6.06 Correlation of demand signal indication on charging pump flow valve controller to the valve position........ 2.5* 2.8*
K6.07 Correlation of demand signal indication with letdown PVC position............................................ 2.4 2.6*
K6.08 Va1ves.................................................. 2.1 2.4 K6.09 Sensor and detectors........................ ........... 2.4 2.6 K6.10 Controllers and positioners............................. 2.3 2.6 K6.11 Pumps..................... ................... ........ 1.9 2.1 K6.12 Motors............................... .................. 1.8 1.9 K6.13 Breakers, relays, and disconnects....................... 1.9 2.0 K/A catalog 3.2-22
(N SYSTEM: 011 Pressurizer Level Control System (PZR LCS)
( )
TASK MODE: 000 Generic r Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including:
A1.01 PZR level and pressure.................................. 3.5 3.6 A1.02 Charging and letdown flows.............................. 3.3 3.5 A1.03 VCTleve1..............................................2.8 3.2 A1.04 T-ave................................................... 3.1 3.3 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Excessive 1etdown....................................... 3.2 3.1 A2.02 Excessive charging...................................... 3.2 3.2
-s A2.03 Loss of PZR 1evel.............. ........................ 3.8 3.9
( h A2.04 Loss of one, two or three charging pumps................ 3.5 3.7
'x_,) A2.05 Loss of PZR heaters..................................... 3.3 3.7 A2.06 Inadvertent PZR spray actuation......................... 3.7 3.9 A2.07 I so l a t i o n o f 1 e tdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 0 3.3 A2.08 Loss of level compensation.............................. 2.6 2.8 A2.09 High ambient reflux boiling temperature effect or indi-cated PZR 1evel......................................... 2.9? 3.5?
A2.10 Failure of PZR level instrument - high.................. 3.4 3.6 A2.11 Failure of PZR level instrument - low................... 3.4 3.6 A2.12 Operation of auxiliary spray............................ 3.3 3.3 A3 Ability to monitor automatic operation of the PZR LCS, including:
A3.01 Boration/ dilution....................................... 2.8* 2.8 A3.02 R e a c t o r p ow e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6* 2.8*
A3.03 Charging and letdown.................................... 3.2* 3.3 A4 Ability to manually operate and/or monitor in the control room: i A4.01 Charging pump and flow controls......................... 3.5 3.2 l A4.02 Movement of the pressure control valve, using manual l c o n t ro 1 1 e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4 3.1 A4.03 PZR heaters............................................. 3.3 3.1
, / A4.04 Transfer of PZR LCS from automatic to manual control.... 3.2 2.9 ll A4.05 Letdown flow controller................................. 3.2 2.9 l <
K/A catalog 3.2-23
SYSTEM: 011 Pressurizer Level Control System (PZR LCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.2 3.6
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.7
- 3. Knowledge of which events related to system operati>n/ status should be reported. 2.7* 3.8
- 4. Knowledge of system purpose and/or function. 3.4 3.7
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.8 3.9
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9 3.2
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.4 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for technical speci-fications. 3.3 4.2
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.4
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.2 4.4
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 3.2 3.2 No rma l p l a n t o p e ra t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.2 Plant heatup and startup....................................... 3.3 3.2 Plant shutdown and cooldown.................................... 3.2 3.2 O
K/A catalog 3.2-24
r
[ \
\
!' )
V SYSTEM: 013 Engineered Safety Features Actuation System (ESFAS)
TASK MODE: 000 Generic TASK: Monitor the ESFAS What if safety injection (cold-leg injection) flow is not sufficient?
Manually initiate ESF Perform the design basis accident sequence test Reset the ESF Bypass the ESF Perform the integrated ESF test Perform the ESF equipment response time test Perform the ESF equipment performance test IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledje of the physical connections and/or cause-U fect relationships between the E FAS and the follow-Ino systems:
Kl.01 Initiation signals for ESF circuit lo 4.4 g Kl.02 RCP..................................gic................4.2 ................... 3.2 3.6 K1.03 CC5.....................................................
V)
(
Kl.04 Kl.0S RPS injection...........................................
C55.....................................................
3.8 3.97 4.1 4.1 4.3?
4.4 Kl.06 ECCS.................................................... 4.2 4.4 Kl.07 A FW S y s t e m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 . 1 4.4 K1.08 CCWS.................................................... 3.6 3.8 l K1.09 CIRS.................................................... 3.3* 3.7*
K1.10 CP5..................................................... 2.8* 3.1* l Kl.11 CVCS.................................................... 3.3 3.8 l K1.12 ED/G....................................................4.1 4.4 Kl.13 HVAC....................................................2.8 3.1 i Kl.14 K1.15 IAS.....................................................
MFW System.............................................. 3.4 3.1* 3.4*
3.8 Kl.16 MRSS.................................................... 2.9* 3.4*
Kl.17 K1.18 LRS..................................................... 2.6 3.0 Premature reset of ESF actuation........................ 3.7 4.1 K1.19 WGDS.................................................... 2.6 3.0 K2 Knowledge _of bus power supplies __to the following:
K2.01 ESFAS/ safeguards equipment contro1...................... 3.6* 3.8 K3 Knowledge of the effect that a loss of the ESFAS will Eavn on__the following:
K3.01 Fue1.................................................... 4.4 4.7 (Av) K3.02 RCS..................................................... 4.3 4.5 K3.03 Containment............................................. 4.3 4.7 K/A catalog 3.2-25
SYSTEM: 013 Engineered Safety Features Actuation System (ESFAS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K4 Knowledge of ESFAS design feature (s) and/or inter-lock (s) which provide for the following:
K4.01 SIS reset............................................... 3.9 a.3 K4.02 Containment integrity system reset...................... 3.9 4.2 K4.03 Main Steam Isolation System............................. 3.9 4.4 K4.04 Auxiliary feed actuation signal . . . . . . . . . . . . . . . . . . . . . . . . . 4.3* 4.5*
K4.05 Core spray actuation signal reset...................... . 4.0* 4.2*
K4.06 Recirculation actuation system reset.................... 4.0* 4.3*
K4.07 Power supply 10ss....................................... 3.7 4.1 K4.08 Redundancy.............................................. 3.1 3.4 K4.09 Spurious trip protection................................ 2.7 3.1*
K4.10 Safeguards equipment control reset...................... 3.3 3.7 K4.11 Vital power load control................................ 3.2 3.8 K4.12 Safety injection b1ock.................................. 3.7 3.9 K4.13 1R/ isolation / reset..................................... 3.7 3.9 K4.14 Upper head injection accumulator isolation.............. 3.7* 4.0*
K4.15 Continuous testing...................................... 2.6 3.2 K4.16 Avoidance of PTS........................................ 3.8 4.2 K4.17 Reason for stopping air coolers on train being tested... 2.9* 2.9*
K4.18 Reason for jumping containment high-high pressure signal to containment spray pump on train being tested.. 3.3* 3.5*
K4.19 Reason for opening breaker on high-head injection pump.. 3.0* 3.4*
K4.20 Reason for stopping CCW pump on train being tested...... 3.1* 3.3*
K4.21 Reason for starting an additional service water booster pump for train not being tested and stopping the pump on train under test..................................... 3.1* 3.3*
K4.22 Reasun for shut safety injection pump discharge valve of train to be tested................................... 2.9* 3.1*
K4.23 Reason for disabling of ED/G during ESF sequencer test.. 2.6* 2.9*
K4.24 Reason for disabling of BIT so it will not function during ESF sequencer test............................... 3.0* 3.1*
K5 Knowledge of the following theoretical concepts as they ap[pj((othe_ESFAs:
K5.01 Definitions of safety train and ESF channel............. 2.8 3.2 K5.02 Safety system logic and reliability..................... 2.9 3.3 K6 1erformance and desig~n Knowledge of the ap(glicable attributes _of__the oRowing_$$F $ components:
K6.01 Sensors and detectors................................... 2.7* 3.1*
K6.02 Control le rs and pos i tioners . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2 2.6 K6.03 Breakers, relays, and disconnects....................... 2.4 2.9 K6.04 Trip setpoint calculators............................... 2.4* 2.7*
K/A catalog 3.2-26
/~' SYSTEM: 013 Engineered. Safety Features Actuation System (ESFAS)
( ,)/ TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO Al Ability to predict and/or monitor changes in param-eters (to prevent exceeding design limits) associated with operating the ESFAS controls including:
A1.01 RCS pressure and temperature............................ 4.0 4.2 A1.02 Containment pressure, temperature, and humidity......... 3.9 4.2 A1.03 Feedwater header differential........................... 2.6* 2.6*
A1.04 S/G 1evel............................................... 3.4 3.6 A1.05 Main steam pressure............................... ..... 3.4 3.6 A1.06 RWST 1evel.............................................. 3.6 3.9 A1.07 Containment radiation................................... 3.6 3.9 A1.08 Containment sump level.................................. 3.7 3.8 A1.09 T-hot................................................... 3.4 3.7 A1.10 T-co1d.................................................. 3.4 3.7 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct,
.[-b control, or mitigate the consequences of those mal-
\s_,/ functions or operations:
A2.01 L0CA.................................................... 4.6 4.8 A2.02 Excess steam demand..................................... 4.3 4.5 A2.03 Rapid depressurization.................................. 4.4 4.7 A2.04 Loss of instrument bus.................................. 3.6 4.2 A2.05 Lo s s o f de co ntrol powe r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7 4.2 A2.06 Inadvertent ESFAS actuation............................. 3.7* 4.0 A3 Ability to monitor automatic operation of the ESFAS including:
A3.01 Input channels and logic................................ 3.7* 3.9 A3.02 Operation of actuated equipment......................... 4.1 4.2 A3.03 Continuous testing feature................ ............. 2.4* 2.7*
A4 Ability to manually operate and/or monitor in the control room:
A4.01 ESFAS-initiated equipment which fails to actuate........ 4.5 4.8 A4.02 Reset of ESFAS channels................................. 4.3 4.4 A4.03 ESFAS initiation........................................ 4.5 4.7 SYSTEM GENERIC K/As
( ,) 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.8 4.0 K/A catalog 3.2-27
SYSTEM: 013 Engineered Safety Features Actuation System (ESFAS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 3.0* 3.9
- 3. Knowledge of which events related to system operation / status should be reported. 2.9* 4.0
- 4. Knowledge of system purpose and/or function. 3.8 4.1
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.2 4.2
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.3* 3.7
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.9 4.3
- 8. Ability.to recognize indications for system operating param-eters, which are entry level conditions for technical speci-fications. 3.6 4.4
- 9. Ab'111ty to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.9 4.1
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.4 4.7
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4.6
- 12. Ability to perform specific system and integrated plant operations during:
Controlled plant load change... ... . . ..... .... . . .. 2.6* 2.5 Normal plant operations. ...... ... . . . ..... .. .. ... 2.6* 2.6 Plant heatup and startup.. .. .... . . .... . .... ..... 3.2* 3.3 Plant shutdown and cooldown.... .. ..... .. . .. .. . .. 3.4 3.4 O
K/A catalog 3.2-28
SYSTEM: 000 Emergency Plant Evolutions
' TASK MODE: 022 Loss of Reactor Coolant Makeup IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the loss of reactor coolant makeup emergency task:
EK1.01 Consequences of thermal shock to RCP seal s. . . . . . . . . . . . . . 2.8 3.2*
EK1.02 Relationship of charging flow to pressure differential ,
between charging and RCS................................ 2.7 3.1 )
EK1.03 Relationship between charging flow and PZR level........ 3.0 3.4 EK1.04 Reason for changing from manual to automatic control of charging flow valve controller.......................... 2.9 3.0 EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 2.4 2.4 EK2.02 Sensors and detectors....... ........................... 1.9 2.1 EK2.03 Controll ers and posi tioners. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2 2.3 EK2.04 Pumps................................................... 2.3 2.3 N EK2.05 Motors.................................................. 2.1 2.1 EK2.06 Heat exchangers and condensers.......................... 1.9 2.1 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Adjustment of RCP seal backpressure regulator valve to obtain normal flow...................................... 2.7 3.1 EK3.02 Actions contained in SOPS and E0Ps for RCPs, loss of makeup, loss of charging, and abnormal charging......... 3.5 3.8 EK3.03 Performance of lineup to establish excess letdown after d e te rm i n i n g n e e d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 .1
- 3.3*
EK3.04 Isolating letdown....................................... 3.2 3.4 EK3.05 Need to avoid plant transients.......................... 3.2 3.4 EK3.06 RCP thermal ba rrier crol ing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2 3.3 EK3.07 Isolating charging......... ............................ 3.0* 3.2 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 CVCS letdown and charging....... ....................... 3.4 3.3 EA1.02 CVCS charging low flow alarm, sensor, and indicator..... 3.0 2.9 EA1.03 PZ R l e v e l t re n d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2 3.2 EA1.04 Speed demand controller and running indicators (positive displacement pump)................'...................... 3.3* 3.2*
K/A catalog 3.2-29
SYSTEM: 000 Emergency Plant Evolutions TASK MODE: 022 Loss of Reactor Coolant Makeup IMPORTANCE K/A NO. ABILITY RC SRO EA1.05 RCP seal back pressure regulator valves and flow indicators.... .... .. .... ... . . .... ... ... . ... 2.9* 2.8*
EA1.06 CVCS charging pump ammeters and running indicators.... . 2.9 2.7 EA1.07 Excess letdown containment isolation valve switches and indicators........... ...... . . . .......... . ... 2.8* 2.7*
EA1.08 VCT level. .............. ........ ........... ........ 3.4 3.3 EA1.09 RCP seal flows, temperatures, pressures, and vibrations. 3.2 3.3 EA2 Ability to determine or interpret:
EA2.01 Whether charging line leak exists. . ... . . . . 3.2 3.8 EA2.02 Charging pump problems. .. .. .. ....... . . .... . 3.2 3.7 EA2.03 Failures of flow control vaive or controller.. .... ... 3.1 3.6 EA2.04 How long PZR level can be maintained within limits. ... 2.9 3.8 EPE GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.8
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.6 3.7
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.8 3.3
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.2 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for technical speci-fications. 3.3 4.1
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.6
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.8 4.3
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.1 4.4 K/A catalog 3.2-30
/ SYSTEM: 000 Emergency Plant Evolutions
( TASK MODE: 028 Pressurizer (PZR) Level Malfunction IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they apply to the PZR level malfunction emergency task:
EK1.01 PZR reference leak abnormalities. . . . . . . . . . . . . . . . . . . . . . . . 2.8* 3.1*
EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 2.2 2.2 EK2.02 Sensors and detectors................................... 2.6 2.7 EK2.03 Controllers and positioners............................. 2.6 2.9 EK2.04 Pumps................................................... 2.3 2.4 EK2.05 Heat exchangers and condensers.......................... 1.9 2.1 EK2.06 Motors.................................................. 1.8 2.1 EK2.07 Breakers, relays, and disconnects....................... 1.8 2.2 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Relationship between the letdown flow rate and capacity ra t i n g o f o ri f i c e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4 2.8 EK3.02 Relationships between PZR pressure increase and reactor
[s ma keup/l etdown i mba l a n ce . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.2 s EK3.03 False indication of PZR level when PORV or spray valve i s open and RCS saturated. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5 4.1 EK3.04 Change in PZR level with power change, even though RCS T-ave constant, due to loop size difference........ 2.9* 3.0*
EK3.05 Actions contained in E0P for PZR level malfunction...... 3.7 4.1 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 PZR level reactor protection bistables.................. 3.8* 3.9*
EA1.02 CVCS.................................................... 3.4 3.4 EA1.03 RCP and seal water system............................... 2.9 2.9 EA1.04 Regenerative heat exchanger and temperature limits...... 2.7 2.8' EA1.05 Initiation of excess letdown per the CVCS............... 2.8 2.9 EA1.06 Chec ki ng o f RCS 1 ea ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3 3.6 EA1.07 Charging pumps maintenance of PZR level (including manual backup).......................................... 3.3 3.3 EA1.08 Selection of an alternate PZR level channel if one has failed.................................................. 3.7 3.6 EA2 Ability to determine or interpret:
EA2.01 PZR level indicators and alarms......................... 3.4 3.6 PZR level as a function of power level or T-ave. includ-
.g()g EA2.02 ing interpretation of malfunction....................... 3.4 3.8 K/A catalog 3.2-31
SYSTEM: 000 Emergency Plant Evolutions TASK MODE: 028 Pressurizer (PZR) Level Malfunction IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.03 Charging subsystem flow indicator and controller........ 2.8 3.3 EA2.04 Ammeters and running indicators for CVCS charging pumps. 2.6 3.1 EA2.05 Flow control valve isolation valve indicator............ 2.6 2.7 EA2.06 Letdown flow indicator.................................. 2.7 2.8 q EA2.07 Seal water flow indicator for RCP....................... 2.6 2.9 EA2.08 PZR level as a function of power level.................. 3.1 3.5 EA2.09 Charging and letdown flow capacities.................... 2.9 3.2 EA2.10 Whether the automatic mode for PZR level control is Efunctioning improperly, necessity of shift to manual modes................................................... 3.3 3.4 EA2.11 Leak in PZR............................................. 3.2 3.6 EA2.12 Cause for PZR level deviation alarm: controller mal-function or other instrumentation malfunction. . . . . . . . . . . 3.1 3.5 EA2.13 The actual PZR level, given uncompensated level with an appropriate graph....................................... 2.9 3.2 EA2.14 The effect on indicated PZR levels, given a change in ambient pressure and temperature of reflux boiling. . ... . 2.6 2.8 EPE GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.8
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.9 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.7 2.9
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.4 4.0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.4 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.8
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.2
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.1 4.3 K/A catalog 3.2-32
O C
8I v>
I b'l RCS Pressure Control Systems It and Malfunctions E-lO <
e-(m '
SYSTEM: 010 Pressurizer Pressure Control System (PZR PCS)
TASK MODE: 000 Generic TASK: Control PZR pressure in individual manual mode (using heaters or spray manually)
Test PORV operability Control PZR pressure in master manual model Heat up the PZR with the PZR heaters Perform lineup on the PZR pressure relief system Transfer from manual to automatic pressure control Monitor PZR pressure Monitor the PZR pressure relief system IMPORTANCE K/A NO. KNOWLEDGE R0 SRO 2
K1 Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems:
K1.01 RPS...................................... .............. 3.9 4.1 K1.02 ESFAS................................................... 3.9 4.1
/'~'N K1.03 RCS..................................................... 3.6 3.7
\ ' ,) K1.04 K1.05 AFW..................................................... 2.4 2.7 PRTS.................................................... 3.4 3.6 K1.06 CVCS.................................................... 2.9 3.1 K1.07 Containment............................................. 2.9 3.1 K1.08 PZRLCS.................................................3.2 3.5 K2 Knowledge of bus power supplies to the following:
K2.01 PZR heaters.................... ........................ 3.0 3.4 K2.02 Controller for PZR spray valve. . . . . . . . . . . . . . . . . . . . ... . . . 2. 5 2.7 K2.03 Indicator for PORV position..................... ....... 2.8* 3.0*
K2.04 Indicator for code safety position..... ... ............ 2.7* 2.9*
i K3 Knowledge of the effect that a loss of the PZR PCS will have on the following:
K3.01 RCS..................................................... 3.8 3.9 K3.02 RPS............................................... ..... 4.0 4.1 K3.03 ESFAS................................................... 4.0 4.2 K4 Knowledge of PZR PCS design feature (s) and/or inter-lock (s) which provide for the following:
K4.01 Spray valve warmup...................................... 2.7 2.9 7'~5s K4.02 Prevention of uncovering PZR heaters.................... 3.0 3.4 g ) K4.03 Over pressure control................................... 3.8 4.1 O
K/A catalog 3.3-1
SYSTEM: 010 Pressurizer Pressure Control System (PZR PCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5 Knowledge of the following theoretical concepts as they apply to the PZR PCS:
K5.01 Determination of condition of fluid in PZR, using steam tables..............................................3.5 4.0 K5.02 Constant enthalpy expansion through a valve.... . ..... 2.6 3.0*
K6 Knowledge of the applicable performance and design attributes of the following PZR PCS components:
K6.01 Pressure detection systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7 3.1 K6.02 PZR..................................................... 3.2 3.5 K6.03 PZR sprays and heaters.................................. 3.2 3.6 K6.04 PRT........................ ....... .................... 2.9 3.2 K6.05 Valves..................... ...... .. .................. 2.3 2.4 K6.06 Sens. ors and detectors.................. ................ 2.3 2.4 K6.07 Control l ers and pos i tioners. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 3 2.5 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including:
s A1.01 PZR and RCS boron concentrations........................ 2.8 2.9*
A1.02 Spray and surge line flow rates......................... 2.4 2.6*
A1.03 PRT pressure and temperature......................... .. 2.9 3.2 A1.04 Effects of temperature change during solid operation.... 3.6 3.8 A1.05 Pressure effect on level......................... ...... 2.8 2.9 A1.06 RCS heatup and cooldown effect on pressure........... . . 3.1 3.2 A1.07 RCS pressure. ... .................... . ..... ... .... 3.7 3.7 A1.08 Spray nozzle AT........... ... ..... ................... 3.2 3.3 A1.09 Tail pipe temperature and acoustic monitors............. 3.4 3.7 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Heater failures............. ....... ... ......... .. 3.3 3.6 A2.02 Spray valve failures......... ......... ............. . 3.9 3.9 A2.03 PORV failures.... ...... ....... .. ...... . .. ... 4.1 4.2 O
K/A catalog 3.3-2
p)
(v SYSTEM:
TASK MODE:
010 000 Pressurizer Pressure Control System (PZR PCS)
Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO ,
A3 Ability to monitor automatic operation of the PZR PCS, including:
A3.01 PRT temperature and pressure during PORV testing........ 3.0 3.2 A3.02 PZR pressure............................................ 3.6 3.5 A4 Ability to manually operate and/or monitor in the control room: '
A4.01 PZR spray valve......................................... 3.7 3.5 A4.02 PZR heaters............................................. 3.6 3.4 A4.03 PORV and block va1ves................................... 4.0 3.8 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.3 3.8 O 2. Knowledge of system status criteria which require the notifi-i cation of plant supervisors or off plant personnel. 2.9 3.8
- 3. Knowledge of which events related to system operation / status should be reported. 2. 7 3.8
- 4. Knowledge of system purpose and/or function. 3.6 3.7
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.9 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.1 3.2
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.4 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.6 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.5 3.9
- 10. Ability to recognize abnormal indications for system operating p parameters, which are entry-level conditions for emergency and g abnormal operating procedures. 4.0 4.4 K/A catalog 3.3-3
SYSTEM: 010 Pressurizer Pressure Control System (PZR PCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.3 4.4
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 3.2 3.3 Normal plant operations........................................ 3.2 3.3 Plant heatup and startup....................................... 3.3 3.4 Plant shutdown and cooldown.................................... 3.3 3.3 9
O 1
1 l
l O
j K/A catalog 3.3-4
p b
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 008 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the PZR vapor space accident emergency task:
EK1.01 Thermodynamics and flow characteristics of open or leak-ing valves.............................................. 3.2 3.7 EK1.02 Change in leak rate with change in pressure........ .... 3.1 3.7 EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 2.7* 2.7 EK2.02 Sensors and detectors................................... 2.7* 2.7 EK2.03 Controllers and positioners............................. 2.5 2. 4 EK2.04 Pumps................................................... 1.9 2.0 p EK3 Knowledge of the bases or reasons for the following:
EK3.01 Why PZR level may come back on scale if RCS is saturated. 3.7 4.4 EK3.02 Why PORV or code safety exit temperature is below RCS or PZR temperature...................................... 3.6 4.1 EK3.03 Actions contained in E0P for PZR vapor space accident /
L0CA.................................................... 4.1 4.6 EK3.04 RCP tripping requirements............................... 4.2 4.6 EK3.05 ECCS termination or throttling criteria. . . . . . . . . . . . . . . . . 4.0 4.5 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 PZR spray block valve and PORV block valve.............. 4.2 4.0 EA1.02 HPI pump to control PZR level / pressure.................. 4.1 3.9 EA1.03 Turbine bypass in manual control to maintain header pressure................................................ 2.8 2.6 EA1.04 Feedwater pumps......................................... 2 8* 2.5 EA1.05 LPI System.............................................. 3.4 3.3 EA1.06 Control of PZR 1evel.................................... 3.6 3.6 EA1.07 Reseating of code safety and P0RV. . . . . . . . . . . . . . . . . . . . . . . 4. 0 4.2 EA1.08 PRT level pressure and temperature...................... 3.8 3.8 EA2 Ability to determine or interpret:
EA2.01 RCS pressure and temperature indicators and alarms...... 3.9 4.2 EA2.02 PZR spray valve position indicators and acoustic moni-tors.................................................... 3.9 4.1 K/A catalog 3.3-5
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 008 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)
IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.03 PORV position indicators and acoustic monitors.......... 3.9 3.9 EA2.04 High-temperature computer alarm and alarm typer....... . 3.2 3.4 EA2.05 PORV isolation (block) valve switches and indicators.. . 3.9 3.9 EA2.06 PORV logic control under low pressure conditions.. .... 3.3 3.6 EA2.07 Feedwater flow indicators and pump controllers.......... 2.4 2.4 EA2.08 Rod position indicators..... .. . .............. . . . . . . 2.1 2.2 EA2.09 PZR spray block valve controls and indicators.... ...... 3.6 3.7 EA2.10 High pressure injection valves and controllers.... ... 3.6 3.6 EA2.11 Turbine bypass header pressure indicators............ .. 2.3 2.4 EA2.12 PZR level indicators......... .... ..................... 3.4 3.7 EA2.13 High pressure safety injection pump flow indicator, Eammeter, and controller. . .............. . .. . ...... 3.8 3.9 EA2.14 Saturation temperature monitor......... .......... .... 4.2 4.4 EA2.15 ESF control board, valve controls, and indicators. . . . 3. 9 4.2 EA2.16 RCS in-core thermocouple indicators; use of plant com-puter for interpretation..... ........ . ............ 3.8 4.1 EA2.17 Steam dump valve controller (position).. ............... 2.5 2.7*
E/,2.18 Computer indications for RCS temperature and pressure... 3.0 3.0*
EA2.19 PZR spray valve failure, using plant parameters......... 3.4 3.6 EA2.20 The effect of an open PORV on code safety, based on observation of plant parameters............. ..... .... 3.4 3.6 EA2.21 The feed flow of different channels, using the feed regulator valve controller and indicators.. ............ 2.1 2.2*
EA2.22 Consequences of loss of pressure in RCS; methods for eval uati ng pres s ure l os s. . . . . . . . . . . . . . . . . . . . . . . . . . 3. 8 4.2 EA2.23 Criteria for throttling high pressure injection after a small LOCA..... . ..... .. ....... .. .................. 3.6 4.3 EA2.24 Value at which turbine bypass valve maintains header pressure after a reactor trip.................. ........ 2.6 2.6*
EA2.25 Expected leak rate from open PORV or code safety........ 2.8 3.4 EA2.26 Probable PZR steam space leakage paths other than PORV or code safety... ... ... ... .. ............... .... 3.1 3.4 EA2.27 Effects on indicated PZR pressure and/or level of sens-ing line leakage.. ...... . ........... ............... 2.9 3.2 EA2.28 Safety parameter display system indications....... ..... 3.3* 3.9 EA2.29 The effects of bubble in reactor vessel........... ..... 3.9 4.2 EA2.30 Inadequate core cooling..................... ........... 4.3 4.7 EPE GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.8 K/A catalog 3.3-6
000 Emergency Plant Evolutions
[]
g SYSTEM:
EPE MODE: 008 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)
IMPORTANCE EPE GENERIC K/As R0 SR0
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.0 4.0
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.6 2.6
- 7. Ability to locate, explain, and apply all limits and precautions. 3.5 3.9
- 8. Ability to recognize _ indications for systen operating param-eters, which are entry level conditions for Technical Speci-fications. 3.4 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3. 7 3.8
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.3
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.2 4.2 i
l i
r
\
i K/A catalog 3.3-7
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 009 Small 8reak LOCA IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the small break LOCA emergency task:
EK1.01 Natural circulation and cooling, includin reflux boiling..................................g ............... 4.2 4.7 EKl.02 Use of steam tables..................................... 3.5 4.2 EK2 Knowledge of the following components:
EK2.01 Valves......................... .............. ........2.2 2. 3 EK2.02 Pumps................................................... 2.3 2.6*
EK2.03 S/Gs........... ......................... ............. 3.0 3.3*
EK2.04 Sensors and detectors................................. . 2.3 2.6 EK3 Knowledge of the bases or reasons for the following:
EK3.01 CCW System automatic isolation on high delta flow /
temperature to RCP thermal barrier...................... 3.1* 3.6*
EK3.02 Opening excess letdown isolation valve.................. 2.8* 3.2*
EK3.03 Reactor trip and safety initiation... .......... ..... . 4.1 4.4 EK3.04 Starting additional charging pumps............. ........ 4.1 4.3 EK3.05 CCWS radiation alarm.................................... 3.4 3.8 EK3.06 RCS i nve nto ry bal a nce. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 9 4.0 EK3.07 Increasing indication on CCWS process monitor: indi-cates in-leakage of radioactive liquids................. 3.3 3. 6 EK3.08 PTS limits on RCS pressure and temperature - NC and FC.. 3.6 4.1 EK3.09 Closing CCW surge tank vent.. ............. ............ 3.1* 3.4*
EK3.10 Observation of PZR level................................ 3.4 3.6 EK3.11 Dangers associated with inadequate core cooling. ....... 4.4 4.5 EK3.12 Letdown isolation......... ........................ . 3.4 3.7 EK3.13 Stoppi ng the a f fected RCP. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 4 3.7 EK3.14 Moni toring RCP lower bearings. . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3. 2 EK3.15 Closing of RCP thermal barrier outlet valves............ 3.2 3. 2 EK3.16 Containment temperature, pressure, humidity and level limits............. ...................................3.8 4.1 EK3.17 Automatic isolation of containment...... ..... ... ..... 4.0 4.3 EK3.18 Monitoring containment radiation levels..... ...... . .. 3.9 4.3 EK3.19 Operator initiation of containment vent isolation /
indication..................... ........................ 3.6? 3.9?
EK3.20 Tech-Spec leakage limits..... ...... ........ ... ..... 3.5 4.3 EK3.21 Actions contained in E0P for small break LOCA/ leak... .. 4.2 4.5 EK3.22 Maintenance of heat sink.. ......... ........... ....... 4.4 4.5 EK3.23 RCP tripping requirements........... ................... 4.2 4.3 EK3.24 ECCS throttling or termination criteria.. ..... .. ..... 4.1 4.6 EK3.25 Monitoring of in-core T-cold.. ....... ................ . 3.6 3.9 EK3.26 Maintenance of RCS subcooling. . . . . . . . . . . . . . . . . . . . . . . . . 4. 4 4.5 K/A catalog 3.3-8
i i SYSTEM: 000 Emergency Plant Evolutions
\s_ / EPE MODE: 009 Small Break LOCA IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK3.27 Manual depressurization or HPI recirculation for sus-tained high pressure.................................... 3.6 3.8 EK3.28 Manual ESFAS initiation requirements.................... 4.5 4.5 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 RCS pressure and temperature............................ 4.4 4.3 EA1.02 RB sump level........................................... 3.8 3.8 EA1.03 Low pressure SWS activity monitor....................... 3.2* 3.2*
EA1.04 CVCS.................................................... 3.7* 3.5 EA1.05 CCWS.................................................... 3.4* 3.4 EA1.06 Plant computer.......................................... 3.0* 3.3 EA1.07 CCS..................................................... 3.7 3.9 EA1.08 Containment isolation system............................ 4.0 4.1 EA1.09 RCP..................................................... 3.6 3.6 EA1.10 Safety parameter display system. . . . . . . . . . . . . . . . . . . . . . . . . 3.8* 3.9*
EA1.11 A FW/M FW . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1 4.1 e~'s EA1.12 RPS..................................................... 4.2 4.2 f
i EA1.13 ESFAS................................................... 4.4 4.4
\ EA1.14 Secondary pressure control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 4 3.4 EA1.15 PORV and PORV block valve............................... 3.9 4.1 EA1.16 Subcooling margin monitors.............................. 4.2 4.2 EA1.17 PRT..................................................... 3.4 3.4 EA1.18 Balancing of HPI loop flows............................. 3.4* 3.2*
EA1.19 LRS..................................................... 2.3 2.4 EA2 Ability to determir,e or interpret:
EA2.01 Actions to be taken, based on RCS temperature and pressure, saturated and superheated..................... 4.2 4.8 EA2.02 Pos si bl e l ea k paths . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5 3.8 EA2.03 CCWS high radiation alarm............................... 3.4 3.8 EA2.04 PZ R 1 e v e l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.8 4.0 EA2.05 The time available for action before PZR is empty, given the rate of decrease of PZR leve1....................... 3.4* 3.9 EA2.06 Whether PZR water inventory loss is imminent. . . . . . . . . . . . 3.8 4.3 EA2.07 CCWS surge tank vent isolation valve indication......... 2.7* 3.1*
EA2.08 Letdown isolation valve position indication............. 2.9* 2.9*
EA2.09 Low pressure SWS activity monitor....................... 2.8* 3.3*
EA2.10 Airborne activity....................................... 3.1 3.7 EA2.11 Containment temperature, pressure, and humidity......... 3.8 4.1 EA2.12 Charging pump ammeter................................... 2.8 2.7 EA2.13 Charging pump flow indication........................... 3.4 3.6
/ EA2.14 Actions to be taken if PTS limits are violated.......... 3.8 4.4
( EA2.15 RCP parameters.......................................... 3.3 3. 4 K/A catalog 3.3-9
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 009 Small Break LOCA IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.16 CCW suction pressure gauge.............. .. ..... .... 2.3* 2.4 EA2.17 Total flow meter. . . . . . . .. .. ............... .. .. . 3.3? 3.9?
EA2.18 CCW temperature indication for RCP oil coolers... ... . 2.3 2.6*
EA2.19 Containment air cooler run indication. . ........ . . . 2.7 3.1 EA2.20 Containment vent damper position indicator............ . 2.6 2.9 EA2.21 Containment radiation trend recorder.... ....... . . ... 3.4 3.9 EA2.22 Charging flow trend recorder....... .. ......... .. ... 3.0* 3.3*
EA2.23 RCP operating parameters and limits. ..... ..... .. . 2.8 3.3 EA2.24 RCP temperature setpoints.. ...... .. .. . .......... 2.6 2.9 EA2.25 Reactor trip setpoints... . . ... ....... . .... . 3.9 4.1 EA2.26 Activi ty waste tank level gauges. . . . . . . . . . . . . . . . . . . . 2. l* 2.5*
EA2.27 Activity waste tank trend recorder...... ......... .. . 2.l* 2.4*
EA2.28 Leak rate, from change in reactor coolant drain tank level.... .... ... .. . .... . ..... . ............ .. 2.8 3.1*
EA2.29 CVCS pump indicating lights for determining pump status. 3.2 3.4 EA2.30 Tech-Spec limits for plant operation with less taan four loops. ..... ..... .... . ....... ..... .. ....... 2.5* 3.5*
EA2.31 Tech-Spec limits for plant operation with an idle loop.. 2.5* 3.5*
EA2.32 SDM.... ........... ........ .... . ...... ..... .. .. 3.2* 3.6*
EA2.33 RCS water inventory balance and Tech-Spec limits... .... 3.3 3.8 EA2.34 Conditions for throttling or stopping HPI.... .......... 3.6 4.2 EA2.35 Conditions for throttling or stopping reflux boiling spray................... ... ........... . . ... ...... 3.4* 4.1*
EA2.36 Difference between overcooling and LOCA indications..... 4.2 4.6 EA2.37 Existence of adequate natural circulation..... ... ... 4.2 4.5 EA2.38 Existence of head bubble. . . . . . . . ....... .... ... 3.9 4.3 EA2.39 Adequate core cooling... ... ....... ..... . ..... ... 4.3 4.7 EPE GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.8
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.9
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.0 4.1 C. Ability to locate and operate components, using local controls (outside the control room). 3.0 3.3
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.5 4.0 O
K/A catalog 3.3-10
g SYSTEM: 000 Emergency Plant Evolutions Q EPE MODE: 009 Small Break LOCA IMPORTANCE EPE GENERIC K/As R0 SR0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.4 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.6 3.7
- 10. Ability to recognize abnormal indications for system operat-ing parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.2 4.4
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.3 4.3 s
O K/A catalog 3.3-11
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 011 Large Break LOCA IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the emergency loss-of-coolant-accident (LOCA)
(large break) emergency task:
EK1.01 Natural circulation and cooling, including reflux boiling.............. .................................. 4.1 4.4 EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 2.4 2.4 EK2.02 Pumps................................................... 2.6* 2.7*
EK3 Knowledge of the bases or reasons for the following:
EK3.01 Verifying main steam isclation valve position.. ........ 3.4* 3.5*
EK3.02 Feedwatcr isolation............................. .. .... 3.5* 3.7*
EK3.03 Starting auxiliary feed pumps and flow, ED/G, and service water pumps..................................... 4.1 4.3 EK3.04 Placing cos.tainment fan cooler damper in accident position................................................ 4.0* 4.3 EK3.05 Inj ecti on i nto col d l eg. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 0* 4.1 EK3.06 Actuation of Phase A and 8 during LOCA initiation....... 4.3* 4.3*
EK3.07 Stopping charging pump bypass flow...................... 3.5* 3.6*
EK3.08 Flowpath for sump recirculation......................... 3.9 4.1 EK3.09 Maintaining D/Gs available to provide standby power..... 4.2 4.5 EK3.10 PTS limits on RCS pressure and temperature.............. 3.7 3.9 EK5.11 NC and PC. .... ......................................3.3? 3.4?
EK3.12 Actions contcinec,in E0P for emergency LOCA (large break) 4.4 4.6 EK3.13 Hc t-leg injection /recircalation. . . . . . . . . . . . . . . . . . . . . . . . . 3.8 4.2 Ek3.14 RCP tripping requirement............ ................... 4.1 4.2 EK's .15 Criteria for Si f tir.g to recirculation mode. . . . . . . . . . . . 4.3 4.4 ABILITY EAl Ability to operate and monitor the following:
EA1.01 Cartrol of RCS pressure and t.emperature to avoid violat-ing PTS liic!+,s. ....... .............................. . 3.7* 3.8*
Eh].0E Refluy boil'r.J somp level indicators.................... 3.8 4.1 EA1.0? Securing o.' RCPs. ... . . ......................... . 4.0 4.0 EA1.04 ESF v.tuation oystem ir. manual.......................... 4.4 4.4 EA1.05 Hanoas ar.d/or autorrmtic transfer of suction of charging purps te beated source......... ....................... 4.3 3.9 EA1.06 D/Us........ . .... ............................. ... 4.2 4.2 EAL O7 Contaiarent irolation system............ ............... 4.4 4.4 al.08 Valves to prevent wat7r hammer......... ........ .... . 2.7* 2.6*
K/A catalag 3.3-12
p I SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 011 Large Break LOCA
- V IMPORTANCE K/A NO. ABILITY R0 SRO EA1.09 Core flood tank initiation.............................. 4.3 4.3 EA1.10 A FW a nd SWS p ump s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1 3.8 EA1.11 Long-term cooling of core............................... 4.2 4.2 EA1.12 Long-term containment of radioactivity.................. 4.1 4.4 EA1.13 Safety injection components............................. 4.1* 4.2 EA1.14 Subcool i ng margi n moni tors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 9 4.1 EA1.15 RCS temperature and pressure............................ 4.2 4.2 EA1.16 Balancing of HPI loop flows............................. 3.5* 3.5*
EA1.17 Safety parameter display system......................... 3.5* 4.1*
EA2 Ability to determine or interpret:
EA2.01 Actions to be taken, based on RCS temperature and pressure - saturated and superheated.................... 4.2 4.7 EA2.02 Consequences to RHR of not resetting safety injection... 3.3* 3.7*
EA2.03 Consequences of managing LOCA with loss of CCW.......... 3.7 4.2 EA2.04 Significance of PZR readings............................ 3.7 3.9 EA2.05 Signi ficance of charging pt.mp operation. . . . . . . . . . . . . . . . . 3. 3 3.7*
EA2.06 That fan is in slow speed and dampers are in accident mode during LOCA......... .............................. 3.7* 4.0*
EA2.07 That equipment necessary for functioning of critical (O
j EA2.08 pump water seals is operable............................
Conditions necessary for recovery when accident reaches 3.2? 3.4*
s ta b l e p h a s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 4
- 3.9*
EA2.09 Existence of adequate natural circulation............... 4.2 4.3 EA2.10 Verification of adequate core cooling................... 4.5 4.7 EA2.11 Conditions for throttling or stopping HFI............... 3.9 4.3 EA2.12 Conditions for throttling or stopping reflux boiling s p ray . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _ . . . 3.6* 3.8*
EA2.13 Difference between overcooling and LOCA indications..... 3.7* 3.7*
EA2.14 Actions to be taken if limits for PTS are violated..... . 3.6* 4.0 EPE GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant. supervisors or off plant personnel. 2.8* 3.8
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.8
- 5. Knowledge of the Technical Specification bases and definitions '
related to limiting conditions for operations and safety limits. 3.3 4.2
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.3* 3.5
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.7 4.2 K/A catalog 3.3-13
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 011 Large Break LOCA IMPORTANCE EPE GENERIC K/As R0 SR0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3. 5 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.7 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions f)r amergency and abnormal operating procedures. 4.3 4.5
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4.5 O
l l
9 K/A catalog 3.3-14
(~~N SYSTEM: 000 Emergency Plant Evolutions
! 1 EPE MODE: 027 Pressurizer Pressure Control System (PZR PCS) Malfunction Q
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the PZR PCS malfunction emergency task:
EK1.01 Definition of saturation temperature.................... 3.1 3.4 EK1.02 Expansion of liquids as temperature increases........... 2.8 3.1 EK1.03 Latent heat of vaporization / condensation. . . . . . . . . . . . . . . . 2. 6 2.9 EK2 Knowledge of the following components:
EK2.01 Valves..................................................2.1 2.2 EK2.02 Sensors and detectors................................... 2.4 2.6 EK2.03 Controllers and positioners............................. 2.6 2.8 EK2.04 Pumps................................................... 1.9 2.1 EK2.05 Motors.................................................. 1.8 2.0 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Isolation of PZR spray following loss of PZR heaters.... 3.5* 3.8 EK3.02 Verification of alternate transmitter and/or plant computer prior to shifting flow chart transmitters...... 2.9* 3.0
-[ EK3.03 Actions contained in E0P for PZR PCS malfunction........ 3.7 4.1
(_ ,)' EK3.04 Why, if PZR level is lost and then restored, that pressure recovers much more slowly...................... 2.8 3.3 ABILITY EA1 Ability to operate and monitor the following:
i EA1.01 PZR heaters, sprays, and P0RVs.......................... 4.0 3.9 EA1.02 SCR-controlled heaters in manual mode................... 3.1* 3.0 EA1.03 Pressure control when on a steam bubble................. 3.6 3.5 EA1.04 Pressure recovery, using emergency-only heaters. . . . . . . . . 3.9* 3.6*
EA1.05 Transfer of heaters to backup power supply.............. 3.3* 3.2*
EA2 Ability to determine or interpret:
EA2.01 Conditions which will cause an increase in PZR level.... 3.4 3.8 EA2.02 Normal values for RCS pressure.......................... 3.8 3.9 EA2.03 Effects of RCS pressure changes on key components in plant................................................... 3.3 3.4 EA2.04 Tech-Spec limits for RCS pressure....................... 3.7 4.3 EA2.05 PZR heater setpoints.................................... 3.2 3.3 EA2.06 Conditions requiring plant shutdown..................... 3.5 3.9 EA2.07 Makeup flow indication.................................. 3.1 3.1 EA2.08 Letdown flow indication................................. 3.2 3.2 EA2.09 R e a c to r p owe r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5 3.6 b('~'s K/A catalog 3.3-15
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 027 Pressurizer Pressure Control System (PZR PCS) Malfunction IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.10 PZR heater energized /de-energized condition....... ..... 3.3 3.6 EA2.11 RCS pressure..... ... ............. .................... 4.0 4.1 EA2.12 PZR level.... . ........... ..... . . ... .. . ...... 3.7 3.8 EA2.13 Seal return flow.................... . ...... . ..... 2.8 2.9 EA2.14 RCP injection flow.. ............ ... .. .. ... .. .. . 2.8 2.9 EA2.15 Actions to be taken if PZR pressure instrument fails high................... ......... . ............ . ..... 3.7 4.0 EA2.16 Actions to be taken if PZR pressure instrument fails low................ .................... ..... . ...... 3.6 3.9 EA2.17 Allowable RCS temperature difference vs. reactor power.. 3.1 3.3 EA2.18 Operable control channel.. . ...... ............ . ... 3.4 3. 5 EPE GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.8
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.8
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 4.0
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.7 3.1
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.6 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.4 4.2
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.6 3.6
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.? 4.3
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.3 4.2 O
K/A catalog 3.3-16
(~] SYSTEM: 000 Emergency Plant Evolutions 5
EPE MODE: 037 Steam Generator (S/G) Tube Leak IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the S/G tube leak emergency task:
EKl.01 Use of steam tables..................................... 2.9* 3.3 EKl.02 Leak rate vs. pressure drop............................. 3.5 3.9 EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 2.1 2.0 EK2.02 Sensors and detectors................................... 2.4 2.4 EK2.03 Controllers and positioners............................. 2.3 2.2 EK2.04 Pumps................................................... 2.1 2.1 EK2.05 Motors.................................................. 1.9 1. 9 EK2.06 Heat exchangers and condensers.......................... 2.4 2.5 EK2.07 Breakers, relays, and disconnects....................... 1.9 2.0 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Collection of condensate in air ejector monitor due to its failure............................................. 2.3 2.6 i]/
/
EK3.02 EK3.03 Reset and check of condensate air ejector exhaust monitor.................................................
Comparison of makeup flow and letdown flow for various 3.2 3.5 modes of operation...................................... 3.1 3.3 EK3.04 Use of " feed and bleed" process......................... 2.5 2.9 EK3.05 Actions contained in procedures for radiation monitor-ing, RCS water inventory balance, S/G tube failure, and plant shutdown...................................... 3.7 4.0 EK3.06 Normal operating precautions to preclude or minimize SGTR.................................................... 3.6 4.1 EK3.07 Actions contained in E0P for S/G tube leak.............. 4.2 4.4 EK3.08 Criteria for securing RCP............................... 4.1 4.3 EK3.09 Maximum load change capability of facility.............. 2.7* 3.1*
EK3.10 Automatic actions associated with high radioactivity in S/G sample 1ines........................................ 3.3* 3.7*
ABILITY EAl Ability to operate and monitor the following:
EA1.01 Maximum controlled depressurization rate for affected S/G..................................................... 3.7 3.6 EA1.02 Condensate exhaust system............................... 3.1* 2.9 EA1.03 Loop isolation valves................................. . 3.0* 2.9 EA1.04 Condensate air ejector exhaust radiation monitor and failure indicator... .................................3.6 3.9 p}EA1.05
- Radiation monitor for auxiliary building exhaust proc-l b esses........................................... ....... 3.3 3.5 l K/A catalog 3.3-17 I
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 037 Steam Generator (S/G) Tube Leak IMPORTANCE K/A NO. ABILITY R0 SRO EA1.06 Main steam line rad monitor meters...................... 3.8* 3.9*
EA1.07 CVCS letdown flow indicator............................. 3.1 3.2 EA1.08 Cha rgi ng fl ow i ndi cato r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3 3.1 EA1.09 RCS loop pressure indicators................. .......... 3.3 3.2 EA1.10 CVCS makeup tank l evel indicator. . . . . . . . . . . . . . . . . . . . . . . . 2.9 3.1 EA1.11 PZR level indicator..................................... 3.4 3.3 EA1.12 Control panel power range channel recorders............. 2.3* 2.5*
EA1.13 S/G blowdown radiation monitors......................... 3.9 4.0 EA2 Ability to determine or interpret:
EA2.01 Unusual readings of the monitors; steps needed to verify readings................................................ 3.0 3.4 EA2.02 Agreement / disagreement among redundant radiation moni-tors.................................................... 3.4 3.9 EA2.03 That the expected indication on main steam lines from the S/Gs should show increasing radiation levels........ 3.4 3.9 EA2.04 Comparison of RCS fluid inputs and outputs, to detect 1eaks................................................... 3.4 3.7 EA2.05 Past history of leakage with current problem. . . . . . . . . . . . 2.8 3.3 EA2.06 S/G tube failure......................... .............. 4.3 4.5 EA2.07 Flowpath for dilution of ejector exhaust air............ 3.1 3.6 EA2.08 Failure of condensate air ejector exhaust monitor....... 2.8 3.3 EA2.09 System status, using independent readings from redundant condensate air ejector exhaust monitor.. ............... 2.8* 3.4*
EA2.10 Tech-Spec limits for RCS leakage........................ 3.2 4.1 EA2.11 When to isolate one or more S/Gs........................ 3.8 3.8*
EA2.12 F l ow ra t e o f l e a k. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3 4.1 EA2.13 Which S/G is leaking.............. ..................... 4.1 4.3 EA2.14 Actions to be taken if S/G goes solid and water enters steam lines.................. .......................... 4.0 4.4 EA2.15 Magnitude of atmospheric radioactive release if cool-down must be completed using steam dump or atmospheric reliefs................................................. 3.4* 4.2 EA2.16 Pressure at which to maintain RCS during S/G'cooldown... 4.1 4.3 EPE GENERIC K/As
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 3.1* 3.9
- 3. Knowledge of which events related to system operation / status should be reported. 2.9* 3.9
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 4.0 K/A catalog 3.3-18
-~
SYSTEM: 000 Emergency Plant Evolutions 037 Steam Generator (S/G) Tube Leak (s}EPEMODE:
IMPORTANCE EPE GENERIC K/As R0 SRO
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.3* 3.7
- 7. Ability to locate, explain, and apply all limits and precautions. 3.7 4.1 i
- 8. Ability to recognize indications for system operating parameters, which are entry level conditions for Technical 4 Specifications. 3.6 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.5 3.8 l
i 10. Ability to recognize abnormal indications for system operat-
- ing pararneters, which are entry-level conditions for emergency and abnormal operating procedures. 4.2 4.4 j 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.3 4.3
'O 1
4 9
i i-1 i
.i j
4O i
i K/A catalog 3.3-19 i
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 038 Steam Generator (S/G) Tube Rupture IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they apply to the S/G tube rupture emergency task:
EKl.01 Use of steam tables..................................... 3.1 3.4 EKl.02 Leak rate vs. pressure drop............................. 3.2 3.5 EKl.03 Natural circulation..................................... 3.9 4.2 EKl.04 Reflux boiling.......................................... 3.1* 3.3 EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 2.2* 2.2 EK2.02 Sensors and detectors................................... 2.4 2.5 EK2.03 Controllers and positioners............................. 2.1 2.2 EK2.04 Pumps.......................... ........................ 2.3* 2.4 EK2.05 Motors.................................................. 2.1 2.2 EK2.06 Heat exchangers and condensers.......................... 2.1 2.4 EK2.07 Breakers, relays, and disconnects................... . . 2.1* 2.3 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Equalizing pressure on primary and secondary sides of ruptured S/G............................................ 4.1 4.3 EK3.02 Prevention of secondary PORV cycling.................... 4.4 4.5 EK3.03 Automatic actions associated with high radioactivity in S/G sample lines........................................ 3.6* 4.0*
EK3.04 Automatic actions provided by each PRM.................. 3.9 4.1 EK3.05 Normal operating precautions to preclude or minimize SGTR.................................................... 4.0 4.3 EK3.06 Actions contained in E0P for RCS water inventory bal-ance, S/G tube rupture, and plant shutdown procedures... 4.2 4.5 EK3.07 RCS loop isolation va1ves............................... 3.4* 3.8 EK3.08 Cri te ri a for securi ng RCP. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1 4. 2 EK3.09 Criteria for securing / throttling ECCS................... 4.1 4.5 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 S/G 1evels, for abnormal increase in any S/G............ 4.5 4.4 EA1.02 Steam and feedwater flow, for mismatched condition...... 4.2 4.1 EA1.03 SWS to the turbine building............................. 1.9* 2.0 EA1.04 PZR spray, to reduce coolant system pressure............ 4.3 4.1 EA1.05 Maximum controlled depressurization rate for affected S/G...................................... .............. 4.1 4.3 EA1.06 Cleanup of a contaminated S/G........................... 2.1* 2.5*
EA1.07 PRT tank temperature, pressure, and setpoints........... 2.5* 2.6*
EA1.08 Core cooling monitor.................................... 3.7* 3.8*
EA1.09 PZR tank level / pressure indicators, gauges, and recorder. 3.2 3.3 K/A catalog 3.3-20
l SYSTEM: 000 Emergency Plant Evolutions
! [/m}
Q EPE MODE: 0?3 Steam Generator (S/G) Tube Rupture IMPORfANCE K/A NO. ABILITY R0 SR0 EA1.10 Control room radiation monitoring indicators and alarms. 3.7* 3.7 EA1.11 S/G level indicators.................................... 3.8 3.9 EA1.12 S/G blowdown line radiation monitors.................... 4.3 4.3 EA1.13 Steam flow indicators................................... 3.7* 3.6 EA1. M AFW pump control and flow indicators.................... 4.1 3.9 EA1.15 AFW source level and capacity (chart)................... 3.9 3.9 EA1.16 S/G atmospheric relief valve and secondary PORV controllers and indicators.............................. 4.4 4.3 l
.EA1.17 S/G sample isolation valve indicators................... 3.2* 3.2 s S/G blowdown valve indicators........................... 4.0 3.9
- _EA1.18 EA1.19 MFW System status indicator............................. 3.4 3.4 EA1.20 AFW flow control valve reset switches and indicators.... 3.8* 3.6*
EA1.21 Charging pump ammeter and running indicator............. 3.4* 3.1*
RHR operating pump ammeter and indicators...............
EA1.22 2.7* 2.6 l EA1.23 Boric acid pumps........................................ 2.6* 2.5*
EA1.24 Safety injection pump ammeter and indicators............ 3.6* 3.4 EA1.25 CCW pump ammeter and indicators......................... 2.6* 2.4 i EA1.26 High-head safety injection mini-flow valves and position '
i n d i ca to r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 6 3.4
,m EA1.27 Steam dump valve status lights and indicators........... 3.9 3.9 )
(b
\
i EA1.28 EA1.29 EA1.30 Interlock between MSIV and bypass valve. . . . . . . . . . . . . . . . .
CVCS tank indicators and water ciiarging sources. . . . . . . . .
Safety injection and containment isolation systems......
3.6*
- 3. 5*
4.0 3.5 3.3 3.8 EA1.31 Reactor trip breaker and safety injection interlock. . . . . 4.1 4.0 EA1.32 Isolation of a ruptured S/G............................. 4.6 4.7 EA1.33 Use of S/G for natural circulation cooldown............. 4.4 4.3 EA1.34 Obtaining shutdown with natural circulation............. 4.2 4.3 EA1.35 Steam dump condenser.................................... 3.5 3.6 EA1.36 Cooldown of RCS to specified temperature................ 4.3 4.5 EA1.37 Controlling of thermal shock during PZR spray operation. 3.5* 3.4 EA1.38 PZR heaters............................................. 3.3* 3.3 EA1.39 Drawing S/G into the RCS, using the " feed and bleed" method.................................................. 3.6* 3.7*
EA1.40 Adding boron, to raise its ppm to the required shutdown concentration........................................... 4.0 4.0 EA1.41 Venting of the S/G to the atmosphere.................... 3.4* 3.4*
EA1.42 Shutting of high-head safety injection mini-flow valves. 3.3* 3.3*
EA1.43 Manual isolation of steam dump valves................... 3.6* 3.5*
EA1.44 Level operating limits for S/Gs......................... 3.4* 3.4 '
EA1.45 Safely parameter display system......................... 3.9* 4.0*
EA2 Ability to determine or interpret:
EA2.01 When to isolate one or more S/Gs........................ 4.1 4.7 EA2.02 Existence of an S/G tube rupture and its potential O consequences............................................ 4.5 4.8 h EA2.03 EA2.04 Which S/G is Radiation levels (MREM /hr)..............................
ruptured................................... 4.4 3.9 4.6 4.2*
K/A catalog 3.3-21
1 l
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 038 Steam Generator (S/G) Tube Rupture IMPORTANCE K/A NO. ABILITY R0 SRO EA2.05 Causes and consequences of shrink and swell in S/Gs..... 2.8* 2.9 EA2.06 Shutdown margins and required boron concentrations...... 3.8 4.4 EA2.07 Plant conditions, from survey of control room indica-tions..................................................4.4 4.8 EA2.08 Viable alternatives for placing plant in safe condition when condenser is not available......................... 3.8 4.4 EA2.09 Existence of natural circulation, using plant parameters. 4.2 4.2 EA2.10 Flowpath for charging and letdown flows. . . . . . . . . . . . . . . . . 3.1 3.3 EA2.11 Local radiation reading on main steam lines............. 3.7* 3.9*
EA2.12 Status of MSIV activating system........................ 3.9* 4.2 EA2.13 Magnitude of rupture.................................... 3.1* 3.7 EA2.14 Magnitude of atmospheric radioactive release if cooldown must be completed using steam dumps or if atmospheric reliefs 1ift............................................ 3.3* 4.6 EA2.15 Pressure at which to maintain RCS during S/G cooldown... 4.2 4.4 EA2.16 Actions to be taken if S/G goes solid and water enters steam line.............................................. 4.2 4.6 EA2.17 RCP restart criteria... ................................ 3.8 4.4 EPE GENERIC K/As
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 3.0* 3. 9
- 3. Knowledge of which events related to system operation / status should be reported. 3.1* 3.9
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.3 4.0
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.4* 3.4
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.8 4.1
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.7 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.9 3.9
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.5 4.5 K/A catalog 3.3-22 1
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 038 Steam Generator (S/G) Tube Rupture IMPORTANCE EPE GENERIC K/As R0 SRO
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4.5 l
l K/A catalog 3.3-23
O l RCS Heat Transport Systems l and Malfunctions W
.b w
I a
i a
r l
l O
m (O).
SYSTEM: 003 Reactor Coolant Pump System (RCPS)
TASK MODE: 000 Generic TASK: Start an RCP Monitor the operation of the RCPS Perform a normal RCP shutdown Vent RCP seals Adjust flushing flow to RCP seals IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems:
K1.01 RC P l u b e 01 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 2.8 K1.02 RCP motor cooling and ventilation....................... 2.6 2.8 K1.03 RCP seal system......................................... 3.3 3.6 K1.04 CVCS.................................................... 2.6* 2.9*
Kl.05 CCS..................................................... 2.2 2.4*
K1.06 SWS..................................................... 1.9 2.1 1 Kl.07 RCP vibration moni toring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4 2.9 N,_,/ K1.08 Containment isolation................................... 2.7* 3.0* .
K1.09 RCS drain tank.......................................... 2.0 2.2 '
K1.10 RCS..................................................... 3.0 3.2 K1.11 Sound monitoring........................................ 2.3 2. 5 Kl.12 CCWS.................................................... 3.0 3.3 Kl.13 RCP bearing lift oil pump............................... 2.5 2.5 l l
K2 Knowledge of bus power supplies to the following:
K2. 0 . RCPS...................................................3.1 3.1 K2. 2 C CW p u mp s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 . 5
- 2.6*
K2.03 RCP lube oil pumps...................................... 2.2 2.2 K2.04 Containment isolation valves for RCP cooling water...... 2.3 2.4 K2.05 RCP bearing lift oil pump............................... 2.1 1.9 K3 Knowledge of the effect that a loss of the RCPS will have on the following:
K3.01 RCS..................................................... 3.7 4.0 K3.02 S/G..................................................... 3.5 3.8 K3.03 Feedwater and emergency feedwater....................... )
2.8 3.1 K3.04 RPS..................................................... 3.9 4.2 K3.05 1C5..................................................... 3.6* 3.7*
K3.06 MRSS.................................................... 2.2 2.4 K/A catalog 3.4-1
SYSTEM: 003 Reactor Coolant Pump System (RCPS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K4 Knowledge of RCPS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Minimizing power peaking................................ 2.1 2.3 K4.02 Prevention of cold water accidents or transients........ 2.5 2.7*
K4.03 Adequate lubrication of the RCP......................... 2.5 2. 8 K4.04 Adequate cooling of RCP motor and seals....... .. ...... 2.8 3.1 K4.05 Prevention of reverse rotation........................ . 2.3 2.7*
K4.06 Handling axial thrust (thrust bearing)............. .... 2.1 2.4 K4.07 Minimizing RCS leakage (mechanical seals)............... 3.2 3.4 K4.08 Anchoring the RCP and its associated piping...... ...... 1.6 1.9 K4.09 Seal and pump venting............................ .... 2.2 2.4 K4.10 Increasing pump inertia (flywheel). . . . . . . . . . . . . . . . . . . . . . 2. 3 2.5 K4.11 Isolation valve interlocks. ........... ............... 3.0* 3.0*
K5 Knowledge of the following theoretical concepts as they apply to the RCPS:
K5.01 The relationship between the RCPS flow rate and the nuclear reactor core operating parameters (quadrant power tilt, imbalance, DNB rate, local power density, difference in loop T-hot pressure)........ ... . .. 3. 3 3.9 K5.02 Effects of RCP coastdown on RCS parameters........ ..... 2.8 3.2 K5.03 Effects of RCP shutdown on T-ave., including the reason for the unreliability of T ave. in the shutdown loop.. . 3.1 3.5 K5.04 Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow, and feed flow............ 3.2 3.5 K5.05 The dependency of RCS flow rates upon the number of operating RCPs..................................... .. 2.8* 3.0*
K5.06 Enthalpy increase associated with RCPs, and its effect upon calorimetric calculation of power. . . . . . . . . . . . . . . . . 2. 2 2.6 K5.07 The reason for " jogging" RCPs during venting or when starting under unusual conditions....................... 2.4 2.6 K5.08 RCP current or supply voltage changes and cold versus hot operation........................................... 2.2 2.4*
K5.09 Effects of RCP operation on AP, especially at lower temperatures....... ........... ........................ 2.3 2.6*
K6 Knowledge of the applicable performance and design at-tributes of the following RCPS components:
K6.01 RCP performance characteristics.. ...................... 1. 9 2.4 K6.02 RCP seals and seal water supply............. .. ... .... 2.7 3.1 K6.03 RCP lift oil pump, lube oil pumps....................... 2.4 2.6 K6.04 Containment isolation valves affecting RCP operation.. . 2. 8 3.1 K6.05 Impeller................................................ 1.6 1.9 K/A catalog 3.4-2
1 l
l 7ssi SYSTEM: 003 Reactor Coolant Pump System (RCPS) i TASK MODE: 000 Generic Ad Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6.06 Thermal barrier......................................... 2.3 2.4 K6.07 Thrust and radial beari ng. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 8 2.1 K6.08 Anti-reverse rotation devi ce. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.4 K6.09 RC P el ec tri c mo to r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.1 K6.10 Pumps................................................... 1.8 2.1 K6.11 Motors.................................................. 1.6 1.9 K6.12 Sensors and detectors................................... 1.7 2.1 K6.13 Breakers, relays, and disconnects....................... 1.6 1.8 K6.14 Starting requirements................................... 2.6 2.9 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including:
A1.01 RCP vibration........................................... 2.9 2.9 A1.02 RCP pump and motor bearing temperatures................. 2.9 2.9 p) t A1.03 LA1.04 RCP motor stator winding temperatures...................
RCP oil reservoi r l evel s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.6
- 2. 6 2.6 2.5
- # A1.05 RCS flow................................................ 3.4 3.5 A1.06 PZR spray flow.......................................... 2.9 3.1 A1.07 RCS temperature and pressure............................ 3.4* 3.4 A1.08 Seal water temperature.................................. 2.5 2.6 A1.09 Seal flow and D/P....................................... 2.8 2.8 A1.10 RCP standpipe levels.................................... 2.5 2.7 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, con trol, or mitigate the consequences of those malfunctions or operations:
A2.01 Problems with RCP seals, especially rates of seal leak-off.....................................................3.5 3.9 A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP........ 3.7 3.9 A2.03 Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems................................................ 2.7 3.1 A2.04 Effects of fluctuation of VCT pressure on RCP seal i nj e c t i o n f l ow. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4 2.8 A2.05 Effects of VCT pressure on RCP seal leakoff flows....... 2.5 2.8
[\ A3 Ability to monitor automatic operation of the RCPS, including:
K/A catalog 3.4-3
SYSTEM: 003 Reactor Coolant Pump System (RCPS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A3.01 Seal injection flow..................................... 3.3 3.2 A3.02 Motor current........................................... 2.6 2.5 A3.03 Seal D/P................................................ 3.2 3.1 A3.04 RCS f10w................................................ 3.6 3.6 A3.05 RCP lube oil and bearing lift pumps..................... 2.7* 2.6 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Seal injection.......................................... 3.3 3.2 A4.02 RCP motor parameters.................................... 2.9 2.9 A4.03 RCP lube oil and li f t pump motor controls. . . . . . . . . . . . . . . 2.8 2.5 A4.04 RCP seal differential pressure instrumentation.......... 3.1 3.0 A4.05 RCP seal leakage detection instrumentation.............. 3.1 3.0 A4.06 RCP parameters.......................................... 2.9* 2.9 A4.07 RCP seal bypass......................................... 2.6* 2.6 A4.08 RCP cooling water supplies.............................. 3.2 2.9 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.1 3.5
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.9* 3.6
- 3. Knowledge of which events related to system operation / status should be reported. 2.6* 3.7
- 4. Knowledge of system purpose and/or function. 3.5 3.6
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.9 3.9
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.6 2.7
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.5 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.5 4.2
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.5 3.8 K/A catalog 3.4-4
1
-~s. SYSTEM: 003 Reactor Coolant Pump System (RCPS) g TASK MODE: 000 Generic
(
Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.4 Ability to perform those actions, without reference to proce-
- 11. ;
dure, for all casualties which require immediate operation of system components or controls. 4.3 4.4
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.5 2.6 Normal pl ant ope rati o ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3. 0 Plant heatup and startup....................................... 3.3 3.2 Plant shutdown and cooldown.................................... 3.2 3.2
\s K/A catalog 3.4-5
"!p)
V SYSTEM: 005 Residual Heat Removal System (RHRS)
TASK MODE: 000 Generic TASK: Perform lineups of the RHRS (shutdown cooling system)
Perform decay heat removal system valves automatic closure and interlock verification Fill and vent the RHRS Perform shutdown cooling return header valve test What if the RHR pump is not operating properly?
Start up the RHRS Perform the RHRS MOV cycling test Operate an RHRS heat exchanger Perform operability check of core cooling system What if the RHR cooldown rate is exceeded?
Perform purification of the RHRS during shutdown cooling Operater RHRS with the fuel pool cooling system Monitor the RHRS Shut down the RHRS Drain the RHRS Fill the refueling cavity / transfer canal using the RHRS Drain the refueling cavity and/or dryer-separator using the RHRS
[/)
N,_- K/A NO. KNOWLEDGE IMPORTANCE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the RHRS and the follow ing systems:
Kl.01 CCWS.................................................... 3.2 3.4 K1.02 PZR..................................................... 2.2 2. 4 K1.03 Spent fuel pool cooling................................. 2.2 2.3 K1.04 CVCS.................................................... 2.9 3.1 K1.05 RCPS.................................................... 2.1 2.2 K1.06 ECCS.................................................... 3.5 3.6 K1.07 Borated water storage tank.............................. 2.9 2.9 K1.08 SWS..................................................... 2.7 2.8 Kl.09 RCS0.................................................... 3.6 3.9 K1.10 C5S..................................................... 3.2 3.4*
K1.11 RWST.................................................... 3.5 3.6 K1.12 Safeguard pumps......................................... 3.1 3.4 K1.13 S15..................................................... 3.3 3.5 K2 Knowledge of bus power supplies to the following:
K2.01 R H R p ump s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.0 3.2 s, K2.02 Containment isolation va1ves............................ 2.4 2.6
, 7 K2.03 RCS pressure boundary motor-operated valves. . . . . . . . . . . . . 2.7* 2.8*
K/A catalog 3.4-7
SYSTEM: 005 Residual Heat Removal System (RHRS)
TASK MODE: 000 Generic Tasks as noted previously.
NE K/A NO. KNOWLEDGE R0 SRO K3 Knowledge of the effect that a loss of the RHRS will have on the following:
K3.01 RCS..................................................... 3.9 4.0 K3.02 RCPS.................................................... 2.1 2.1 K3.03 CVCS.................................................... 2.2 2.4 K3.04 PZR..................................................... 2.1* 2.2*
K3.05 ECCS.................................................... 3.7* 3.8*
K3.06 C55..................................................... 3.1* 3.2*
K3.07 Refueling operations.................................... 3.2* 3.6*
K3.08 CCWS.................................................... 2.1 2.2 K4 Knowledge of RHRS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Overpressure mitigation system.......................... 3.0 3.2 K4.02 Modes of operation...................................... 3.2 3.5*
K4.03 RHR heat exchanger bypass flow control.................. 2.9 3.2 K4.04 Need for contents of liquid waste holdup tanks to be low enough before draining RHR system................... 2.0 2.3 K4.05 Relation between RHR flowpath and refueling cavity...... 2.5 2.9 K4.06 Function of RHR pump miniflow recirculation. . . . . . . . . . . . . 2.7 3.0 K4.07 System protection logics, including high pressure inter-lock, reset controls , and valve interlocks. . . . . . . . . . . . . . 3. 2 3.5 K4.08 Lineup for " piggy-back" mode with high pressure injec-tion.................................................... 3.1* 3.5*
K4.09 Vortexi ng whi l e draini ng. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2 2.5 K4.10 Control of RHR heat exchanger outlet flow. . . . . . . . . . . . . . . 3.1 3.1 K4.11 Lineup for low head recirculation mode (external and internal)............................................... 3.5* 3.9*
K4.12 Lineup for piggyback mode with C5S...................... 3.1* 3.7*
K5 Knowledge of the following theoretical concepts as they apply to the RHRS:
K5.01 Nil ductility transition temperature (brittle fracture). 2.6 2. 9 K5.02 Need for adequate subcooling............................ 3.4 3.5 K5.03 Reactivity effects of RHR fill water.................... 2.9* 3.1*
K5.04 Calculation of heat load on the RHR heat exchanger...... 2.1 2.3*
K5.05 Plant response during " solid plant": pressure change due to the relative incompressibility of water.......... 2.7* 3.1*
K5.06 Special concerns regarding the use of water chemistry... 1.9* 2.6*
K5.07 Relationship between PZR level, VCT level, and charging flow............ ....................................... 2.2 2.4*
K5.08 PTS..................................................... 2.4* 2.5*
K5.09 Dilution and boration considerations.................... 3.2 3.4 K/A catalog 3.4-8
SYSTEM: 005 Residual Heat Removal System (RHRS)
/ s TASK MODE: 000 Generic
( )
Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K6 Knowledge of the applicable performance and design at_
tributes of the following RHRS components:
K6.01 RHR pump performance characteristics. . . . . . . . . . . . . . . . . . . 2.4 2.6 K6.02 "Packless" va1ves....................................... 1.8* 1.9*
K6.03 RHR heat exchanger...................................... 2.5 2.6 K6.04 Va1ves.................................. . . . . . . . . . 1. 9 2.1 K6.05 Pumps................................ . . . . . . . . . . . 1. 9 2.1 K6.06 Motors............................... ................1.8 1.8 K6.07 Sensors and detectors................................... 2.1 2.3 K6.08 Controllers and positioners............................. 2.2 2.4 K6.09 Demineralizers and ion exchangers....................... 1.6 1.9 K6.10 Breakers, relays, and disconnects....................... 1.7 1.8 K6.11 RHR heat exchanger and outlet flow control . . . . . . . . . . . . . . 2.3 2.7*
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with
- n) operating the RHRS controls including
\J A1.01 Heatup/cooldown rates................................... 3.5 3.6 A1.02 RHR flow rate........................................... 3.3 3.4 A1.03 Closed cooling water flow rate and temperature.......... 2.5 2.6 A1.04 Relationship between RWST level and level in the spent fuel poo1............................................... 2.1* 2.3 A1.05 Detection of and response to presence of water in RHR emergency sump.......................................... 3.3* 3.3*
A1.06 Relationship (dependence) of time available to perform system isolation surveillance test to time for decay heat to reach high limit................................ 2.7 3.1*
A1.07 Determination of test acceptability by comparison of re-corded valve response times with Tech-Spec requirements. 2.5 3.18 A2 Ability to (a) predict the impacts of the following mal-functions or operations on the RHRS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation. . . . . . . . . . . . . 2.7 2.9*
A2.02 Pressure transient protection during cold shutdown...... 3.5 3.7 A2.03 RHR pump / motor mal function. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.1 (n) v A2.04 RHR valve malfunction................................... 2.9 2.9 K/A catalog 3.4-9
SYSTEM: 005 Residual Heat Removal System (RHRS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A3 Ability to monitor automatic operation of the RHRS, including:
A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Controls and indication for RHR pumps................... 3.6* 3.4 A4.02 Heat exchanger bypass flow control...................... 3.4* 3.1 A4.03 RHR temperature, PZR heaters and flow, and nitrogen..... 2.8* 2.7*
A4.04 Controls and indication for closed cooling water pumps.. 3.1* 2.9 A4.05 Position of RWST recirculation valve (locked when not in use, continuously monitored when in use)............. 2.8* 2.8*
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.2 3.6
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 3.1* 3.9
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.8
- 4. Knowledge of system purpose and/or function. 3.6 3.9
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.0 4.0
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9 3.1
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.5 3.8
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.3 4.2
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.0 4.3 K/A catalog 3.4-10
SYSTEM: 005 Residual Heat Removal System (RHRS)
TASK MODE: 000 Generic ;
Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls, 4.3 4.3
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.4 2.5 Normal plant operations........................................ 2.3 2.5*
Plant heatup and startup....................................... 3.2 3.3 Plant shutdown and coo 1down.................................... 3.3 3.4 K/A catalog 3.4-11
I i
i i
t l
l L
I (A) v i
i SYSTEM: 035 Steam Generator System (S/GS)
TASK MODE: 010 Startup/ Shutdown TASK: Perform lineups on the S/GS Perform S/G hydrostatic test for leaking tubes Fill the S/G Recirculate the S/G during wet layup Remove S/G from wet layup recirculation Add chemicals to the S/G Monitor S/G operation Drain the S/G IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the S/GS and the follow-ing systems:
K1.01 MFW/AFW systems......................................... 4.2 4.5 K1.02 MRSS.................................................... 3.2 3.4 K1.03 B10wdown................................................ 2.4 2.6
/'~')
(s_,/
K1.04 Kl.05 Condenser hotwe11.......................................
Nitrogen................................................
2.2*
1.7 2.3 1.7 Kl.06 Sampling................................................ 1.7 1.8 K1.07 S/G recirculation....................................... 1.9 1.9 Kl.08 Chemical addition....................................... 1.8 2.2 K1.09 RCS..................................................... 3.8 4.0 K1.10 ARM system.............................................. 2.4 2. 5 Kl.11 PRM system.............................................. 3.1 3.1 K1.12 RPS..................................................... 3.7 3.9 K1.13 Condensate system....................................... 2.7 2.8 Kl.14 ESF..................................................... 3.9 4.1 K2 Knowledge of bus power supplies to the following:
K2.01 S/G level control system................................ 2.2* 2.3 K3 Knowledge of the effect that a loss of the S/GS will have on the following:
K3.01 RCS..................................................... 4.4 4.6 K3.02 ECCS.................................................... 4.0 4.3 K3.03 Secondary systems....................................... 3.0* 3.1*
K4 Knowledge of S/GS design feature (s) and/or interlock (s) which provide for the following:
( ,,/ K4.01 S/G 1evel contro1....................................... 3.6 3.8 K4.02 S/G 1evel indication.................................... 3.2 3.5 K/A catalog 3.4-13
SYSTEM: 035 Steam Generator System (S/GS)
TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K4.03 Automatic blowdown and sample line isolation and reset.. 2.6* 2.8*
K4.04 Radiation high-level isolation while draining S/G sec-onda ry to mai n condens e r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8* 3.1*
K4.05 Amount of reserve water in S/G................ ......... 2.9 3.2 K4.05 S/G pressure............................................ 3.1 3.4 K4.06 Pre / post-blowdown system............... ................ 2.3* 2.3*
K4.07 AFW pump operation as it relates to hydrotest............ 1. 9* 2.1*
K4.08 Maintenance of hydrostatic pressure by throttling AFW control valve........................................... 1.7* 1.9*
K5 Knowledge of the following theoretical concepts as they apply to the S/GS:
K5.01 Effect of secondary parameters, pressure, and tempera-ture on reactivity...................................... 3.4 3.9 K5.02 Chemistry control....................................... 2.2 2.9*
K5.03 Shrink and swell concept................................ 2.8 3.1 K5.04 Purpose of using nitrogen blanket in S/G................ 2.0 2.3 K5.05 Relationship between AFW pump speed and discharge pres-sure during hydrotest................................... 1.7* 2.0*
K6 Knowledge of the applicable performance and design at-tributes of the following S/GS components:
K6.01 MSIVs................................................... 3.2 3.6 K6.02 Secondary P0RV.......................................... 3.1 3.5 K6.03 S/G 1evel detector...................................... 2.6 3.0 K6.04 Pumps................................................... 1.6 1.9 K6.05 Motors.................................................. 1.4 1.6 K6.06 Valves................................... .............. 1.9* 2.1*
K6.07 Sensors and detectors................................... 2.2 2.2 K6.08 Controllers and positioners............................. 1.9 2.1 K6.09 Heat exchangers and condensers.......................... 2.2* 2.3*
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the S/GS controls including:
A1.01 S/G wide and narrow range level during startup, shut-down, and normal operations............................. 3.6 3.8 A1.02 S/G pressure............................................ 3.5 3.8 A1.03 Feed flow / steam flow while going into wet layup......... 2.2 2.3 K/A catalog 3.4-14
SYSTEM: 035 Steam Generator System (S/GS)
[ T TASK MODE: 010 Startup/ Shutdown V
Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2 Ability to (a) predict the impacts of the following mal-functions or operations on the S/GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2. 01_ Faulted or ruptured S/Gs................................ 4.5 4.6 A2.02 Reactor trip / turbine trip............................... 4.2 4.4 A2.03 Pressure / level transmitter failure...................... 3.4 3.6 A2.04 Steam flow / feed mismatch................................ 3.6 3.8 A2.05 Unbalanced flows to the S/Gs............................ 3.2 3.4 A2.06 Small break L0CA........................................ 4.5 4.6 A3 Ability to monitor automatic operation of the S/G in-cluding:
A3.01 S/G water level contro1................................. 4.0 3.9 A3.02 MAD va1ves.............................................. 3.7? 3.5?
<~~g A3.03 Components used to conduct a secondary side hydrostatic l test (e.g., AFW pump)................................... 1.9* 1.8*
- i. \ s ) A3.04 Components used to conduct S/G tube hydrostatic test.... 1.9 1.9 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Shift of S/G controls between manual and automatic con-trol, by bumpless transfer.............................. 3.7 3.6 A4.02 Fill of dry S/G......................................... 2.7 2.8 A4.03 Layup to operating conditions........................... 2.2 2.3 A4.04 Operating to layup conditions........................... 2.2 2.4 l
A4.05 Level control to enhance natural circulation. . . . . . . . . . . . 3.8 4.0 A4.06 S/G isolation on steam leak or tube rupture / leak........ 4.5 4.6 A4.07 Adjustment of cooling water flow rate from blowdown hea t exc h a n ge r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 0 2.0 A4.08 Recognition that increasing radiation levels in sec-i ondary systems may mean leaking and possibly ruptured S/G tubes............................................... 4.1 4.4 A4.09 Reason for using timed flow in filling top of S/G while going into wet layup.................................... 2.1* 2.0 l A4.10 Need for frequent S/G level verification during wet l 1ayup................................................... 2.0* 2.0 t
SYSTEM GENERIC K/As n
(s 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.1 3.5 K/A catalog 3.4-15 l
l I
SYSTEM: 035 Steam Generator System (S/GS)
TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 2.9* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.7
- 4. Knowledge of system purpose and/or function. 3.7 3.9
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 4.0
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9 3.2
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.5 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.4 4.2
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.5 3.8
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.5
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.4 4.5
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 3.2 3.2 Normal plant operations........................................ 3.2 3.3 Plant heatup and startup....................................... 3.1 3.1 Plant shutdown and coo 1down.................................... 3.1 3.1 O
K/A catalog 3.4-16
f (3) v SYSTEM: 000 Emergency Plant Evolutions EPE MODE: Reactor Coolant Pump (RCP) Malfunctions:
015 RCP Motor Malfunction 017 Partial Loss of Reactor Coolant Flow IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the RCP malfunctions emergency tasks:
EK1. 01 Natural circulation in a nuclear reactor power plant.... 4.4 4.6 EK1.02 Consequences of an RUPS failure......................... 3.7 4.1 EK1.03 The basis for operating at a reduced power level when one RCP is out of service............................... 3.0* 4.0*
EK1.04 Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow... 2.9 3.1*
EK1.05 Effects of unbalanced RCS flow on in-core average tem-perature, core imbalance, and quadrant power tilt....... 2.7 3.3 EK2 Knowledge of the following components:
(~'N EK2.01 Valves.................................................. 1.5 1.6
\'" ) EK2.02 Sensors and detectors................................... 2.0 2.1 EK2.03 Controllers and positioners............................. 1.7 1. 7 EK2.04 Pumps................................................... 2.0 2.1 EK2.05 Motors.................................................. 1.9 2.0 EK2.06 Breaker, relays , and disconnects. . . . . . . . . . . . . . . . . . . . . . . . 1. 6 1.7 EK2.07 RCPseals...............................................2.9 2.9 EK2.08 CCWS....................................................2.6 2.6 EK2.09 R C P f l yw h e e 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2 2.2 EK2.10 RCP indicators and control s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8* 2.8 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Potential damage from high winding and/or bearing temperatures............................................ 2.5 3.1 EK3.02 CCW lineup and flow paths to RCP oil coolers............ 3.0 3.1 EK3.03 Sequence of events for manually tripping reactor and RCP as a result of an RCP malfunction................... 3.7 4.0 EK3.04 Reduction of power to below the steady state power-t o - f l ow l i m i t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 .1* 3.2*
EK3.05 Shift of T-ave. sensors to the loop with the highest flow.................................................... 2.8* 3. 0*
EK3.06 Performance of a core power map, calculations of quad-rant power tilt, monitoring of core imbalance........... 2.4 3.1*
EK3.07 Ensuring that S/G 1evels are controlled properly for (A
LJ 1
natural circulation enhancement......................... 4.1 4.2 K/A catalog 3.4-17
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: Reactor Coolant Pump (RCP) Malfunctions:
015 RCP Motor Malfunction 017 Partial Loss of Reactor Coolant Flow IMPORTANCE K/A N0. ABILITY R0 SR0 EA1 Ability to operate and monitor the following:
EA1.01 RCP lube oil system..................................... 2.4* 2.4 EA1.02 RCP oil reservoir level and alarm indicators............ 2.8 2.7 EA1.03 Reactor trip alarms, switches, and indicators........... 3.7* 3.8 EA1.04 RCP ventilation cooling fan run indicators.............. 2.5 2.5 EA1.05 RCS f1ow................................................ 3.8 3.8 EA1.06 CCWS.................................................... 3.1 2.9 EA1.07 RCP seal water injection subsystem...................... 3.5 3.4 EA1.08 S/G LCS................................................. 3.0* 2.9 EA1.09 RCS temperature detection subsystem..................... 3.1 3.2 EA1.10 RCP ammeter and trip a1 arm.............................. 2.7 2.6 EA1.11 RCP on/off and run indicators........................... 2.5 2.4 EA1.12 Reactor coolant loop flow meters........................ 2.8* 3.1 EA1.13 Reactor power level indicators.......................... 3.4* 3.4*
EA1.14 Power range remote flux meter........................... 2.9* 3.0*
EA1.15 High power / low-flow reactor trip block status lights.... 3.5* 3.6*
EA1.16 Low power reactor trip block status lights.............. 3.2* 3.5*
EA1.17 Station auxiliary transformer volt-amp meters........... 2.2* 2.2 EA1.18 Station auxiliary power supply breakers and indicators.. 2.3* 2.4 EA1.19 Power transfer confirm 1 amp............................. 2.9* 3.0*
EA1.20 RCP bearing temperature indicators...................... 2.7 2.7 EA1.21 Development of natural circulation flow................. 4.4 4.5 EA1.22 RCP seal failure / malfunction............................ 4.0 4.2 EA1.23 R C P v i b ra ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.2 EA2 Ability to determine or interpret:
EA2.01 Cause of RCP failure.................................... 3.0 3.5*
EA2.02 Abnormalities in RCP air vent flow paths and/or oil cooling system.......................................... 2.8 3.0 EA2.03 Temperature differential across the RCP oil cooler. . . . . . 2.2 2.2 EA2.04 Temperature differential across the RCP air cooler...... 1.9 2.1 EA2.05 Relationship between RCP ammeter readings and RCS aver-age temperature......................................... 1.9 2.2 EA2.06 Relationship between cooling air flow and oil reservoir temperature /l evel for RCP. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 8 2.3 EA2.07 Calculation of expected values of flow in the loop with RCP secured............................................. 2.1 2.9 EA2.08 When to secure RCPs on high bearing temperature......... 3.4 3.5 EA2.09 When to secure RCPs on high stator temperatures......... 3.4 3.5 EA2.10 When to secure RCPs on loss of cooling or seal injec-tion.................................................... 3.7 3.7 EA2.11 When to jog RCPs during 1CC............................. 3.4* 3.8*
K/A catalog 3.4-18
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: Reactor Coolant Pump (RCP) Malfunctions:
i V 015 017 RCP Motor Malfunction Partial Loss of Reactor Coolant Flow IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 3.0* 3.8 i
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.8
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.9 4.0 1 6. Ability to locate and operate components, using local controls (outside the control room). 2.7 2.8 4
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.5 4.1
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications.' 3.5 4.3
- 9. Ability to verify system alarm setpoints and operate controls s identified in the alarm response manual. 3.8 3.8
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.2 4.5
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.4 4.4 0 .
K/A catalog 3.4-19
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 025 Loss of Residual Heat Removal System (RHRS)
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the loss of RHR$ emergency task:
EK1.01 Loss of RHRS during all modes of operation. . . . . . . . . . . . . . 3.9 4.3 EK2 Knowledge of the following components:
EK2.01 RHR heat exchangers..................................... 2.9 2.9 EK2.02 LPI or Decay Heat Removal /RHR pumps..................... 3.2* 3.2 EK2.03 Service water or closed cooling water pumps. . . . . . . . . . . . . 2.7 2.7 EK2.04 Raw water or sea water pumps............................ 2.4 2.4 EK2.05 Reactor building sump................................... 2.6 2.6 EK2.06 Va1ves..................................................2.2 2.1 EK2.07 Sensors and detectors................................... 2.1 2.2 EK2.08 Controllers and positioners............................. 2.2 2.2 EK2.09 Pumps...................................................2.2 2.2 EK2.10 Motors.................................................. 1.8 1. 7 EK2.11 Heat exchangers and condensers.......................... 2.1* 2.1 EK2.12 Breakers, relays, and disconnects....................... 1.7 1.8 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Shift to alternate f10wpath............................. 3.1 3.4 EK3.02 Isolation of RHR low pressure piping prior to pressure increase above specified leve1.......................... 3.3 3.7 EK3.03 Immediate actions contained in E0P for Loss of RHRS..... 3.9 4.1 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 RCS/RHRS cooldown rate.................................. 3.6 3.7 EA1.02 RC S i nv e n to ry. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 8 3.9 EA1.03 LPIpumps...............................................3.4 3.3 EA1.04 Cl osed cool i ng water pumps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8* 2.6 EA1.05 Raw water or sea water pumps............................ 2.7 2.6 EA1.08 RHR cooler inlet and outlet temperature indicators...... 2.9* 2.9 EA1.09 LPI pump switches, ammeter, discharge pressure gauge, flow meter, and indicators.............................. 3.2 3.1 EA1.10 LPI pump suction valve and discharge valve indicators... 3.1* 2.9 EA1.11 Reactor building sump level indicators.................. 2.9 3.0 EA1.12 RCS temperature indicators.............................. 3.6 3. 5 EA1.13 SWS radiation monitors.................................. 2.5 2.6 EA1.14 Waste tank radiation monitors........................... 2.1* 2.1 EA1.15 Waste tank level gauges and recorders. . . . . . . . . . . . . . . . . . . 2.1 2.1 EA1.16 Service water pump manual switch, flow gauge, running lights, and ammeters.................................... 2.2 2.2 K/A catalog 3.4-20
SYSTEM: 000 Emergency Plant Evolutions
(~'} EPE MODE: 025 Loss of Residual Heat Removal System (RHRS)
IMPORTANCE K/A NO. ABILITY R0 SR0 EA1.17 Service water block valve indicators and flow valve controllers............................................. 2.1 2.0*
EA1.18 LPI header cross-connect valve controller and indicators. 2.6* 2.8*
EA1.19 Block orifice bypass valve controller and indicators.... 2.6* 2.4*
EA1.20 HPI pump control switch, indicators, ammeter running lights, and flow meter.................................. 2.6* 2.5*
EA1.21 Letdown flow indicator.................................. 2.3 2.5 EA1.22 Obtaining of water from BWST for LPI system............. 2.9* 2.8 EA1.23 RHR heat exchangers..................................... 2.8 2.9 EA2 Ability to determine or interpret:
EA2.01 Proper amperage of running LPI/ decay heat removal /RHR pump (s)................................................. 2.7 2.9 EA2.02 Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere........ 3.4 3.8 EA2.03 Increasing reactor building sump leve1.................. 3.6 3.8 EA2.04 Location and isolability of leaks. . . . . . . . . . . . . . . . . . . . . . . 3. 3* 3.6 EA2.05 Limitations on LPI flow and temperature rates of change. 3.1* 3.5*
EA2.06 Existence of proper RHR overpressure protection......... 3.2* 3.4*
O
>J EA2.07 Pump cavitation......................................... 3.4 3.7 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 3.1* 3.8
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.8
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 3.0 3.9
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9 3.4
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.5 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.4 4.2
- 9. Ability to verify system alarm setpoints and operate controls QI identified in the alarm response manual. 3.7 3.9 K/A catalog 3.4-21
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 025 Loss of Residual Heat Removal System (RHRS)
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.2 4.4
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.3 4.4 O
O K/A catalog 3.4-22
O SYSTEM:
EPE MODE:
000 074 Emergency Plant Evolutions Inadequate Core Cooling iv/
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they apply to the inadequate core cooling emergency task:
EKl.01 Methods of calculating subcooling margin. . . . . . . . . . . . . . . . 4.3 4.7 EKl.02 Potential consequences of uncovering the core........... 4.6 4.8 EK1.03 Processes for removing decay heat from the core. . . . . . . . . 4.5 4. 9 EK1.04 Use of steam tables, including subcooled saturated and superheated regions..................,...........,.... 3.7 4.1 EK1.05 Defini tion of saturated liquid. . . . . . . . . . . . . . . . . . . . . . . . . . 2.8 3.2 EKl.06 Defini tion of superheated steam. . . . . . . . . . . . . . . . . . . . . . . . . 3. 0 3.3 EK1.07 Defini tion of saturated steam. . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8 3.2 EKl.08 Definition of subcooled liquid.......................... 2.8 3.1 EK1.09 Calculation of volume of water added to the RCS, using tank level indicators................................... 3.1 3.6 l
EK2 Knowledge of the following components:
EK2.01 RCP..................................................... 3.6 3.8 EK2.02 EK2.03 P0RV..................................
A FW p ump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
3.9 4.0 EK2.04
.. 4.0 4.0 H P I p ump s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
O() EK2.05 EK2.06 L P I p u mp s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............... ..............
3.9 3.9 4.1 4.1 Turbine bypass and atmos EK2.07 Valves. . . . . . . . . . . . . . . . . . pheric dump va l ves. . . . . . . . . . . . 5* 3. .. 3.6 EK2.08 Sensors and detectors..........................
................................ 2.4* 2.5 EK2.09 2.5* 2.5 l Controllers and EK2.10 Pumps...........positioners............................. ......... 2.6* 2.6*
...................... ................. 2.2 2.3 EK2.11 EK2.12 Motors................................ ................ 1. 9 2.1 Heat exchangers and condensers. . . . . . . . . . . . . . . . . . . . . . . . . . 2.2 2.4 EK2.13 Breakers, relays, and disconnects....................... 2.0 2.1 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Maintaining cooldown rates within specified limits...... 3.4 EK3.02 4.2 Maintaining S/G level and pressure within specified
! EK3.03 limits..................................................3.7 Placing the plant in hot standb 4.2 EK3.04 Trippi ng RCPs . . . . . . . . . . . . . . . . . .y s tatus . . . . . . . . . . . . . . . . . 3. 4 3.8 EK3.05 Activating the HPI system............................... .................. 3.9 4.2 EK3.06 ....... 4.2 4.5 Confirming that the PORV cycles open at the specified EK3.07 setpoint................................................
Starting up emergency feedwater a 3.9 4.2 EK3.08 Securing RCPs................ 4.0 4.4 EK3.09 RCPs....................nd ....................... 4.1 4.2 Opening the cross-connect valve from the LPI to the HPI T EK3.10 suction.................................................
Isolating core flood tanks 4.4* 4.6*
~/ discharge..................to prevent inadvertant EK3.11 ............................. 3.5 3.8*
i Guidance contained in E0P for Inadequate Core Cooling... 4.0 4.4 i
! K/A catalog 3.4-23
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 074 Inadequate Core Cooling IMPORTANCE K/A N0. ABILITY R0 SR0 EA1 Ability to operate and monitor the following:
EA1.01 RCS water inventory..................................... 4.2 4.4 EA1.02 RCS cooldown rate....................................... 3.9 4.2 EA1.03 The alternate control station for turbine bypass valve operation...............................................3.9* 3.9*
EA1.04 Turbine bypass or atmospheric dump valves, to obtain and maintain the desired pressure. . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 9 4.1 EA1.05 P0RV....................................................3.9 4.1 EA1.06 RCPs.................................................... 3.6 3.9 EA1.07 AFW System.............................................. 4.2 4.3 EA1.08 HPI System.............................................. 4.2 4.2 EA1.09 CVCS....................................................3.7 3.8 EA1.10 Core flood system....................................... 4.0* 4.1*
EA1.11 Reactor building sump and its interlocks................ 3.6 3. 7 EA1.12 RCS temperature and pressure indicators................. 4.1 4.4 EA1.13 Subcooling margin indicators............................ 4.3 4.6 EA1.14 Alarm for loss of subcooling margin..................... 4.1 4.2 EA1.15 Hot-leg and cold-leg temperature recorders.............. 3.9 4.1 EA1.16 RCS in-core thermocouple indicators..................... 4.4 4.6 EA1.17 S/G pressure and level indicators....................... 4.0 4.1 EA1.18 AFW pump flow indicators and ammeter.................... 3.9 3.9 EA1.19 AFW supply tank level indicators........................ 3.7 3.8 EA1.20 ECCS pump flow meters, ammeters, and running lights..... 4.2 4.2 EA1.21 Condensate storage tank level gauge. . . . . . . . . . . . . . . . . . . . . 3. 7 3.7 EA1.22 AFW discharge control valve controllers, indicators, and lights..................................................3.9 3.9 EA1.23 PORV block valve indicators, switches, controls (for both RCS and S/G)....................................... 3.9 4.0 EA1.24 Turbine bypass valve hand / automatic controls, indicators, and setpoints........................................... 3.6 3.8 EA1.25 Atmospheric dump valve controllers and indicators....... 3.8 3.8 EA1.26 Reactor building emergency sump isolation valve control switches and indicators................................. 3.8* 3.8*
EA1.27 ECCS valve control switches and indicators.............. 4.2 4.2 EA1.28 Core flood tank isolation valve controls and indicators. 3.7* 3.9*
EA1.29 Quench tank temperature, pressure, and level instrumen-tation..................................................3.4 3.7 EA2 Ability to determine or interpret:
EA2.01 Subcooling margin....................................... 4.6 4.9 EA2.02 Availability of main or auxiliary feedwater............. 4.3 4.6 EA2.03 Availability of turbine bypass valves for cooldown...... 3.8 4.1 EA2.04 Relationship between RCS temperature and main steam p re s s u r e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.7 4.2 EA2.05 Trends in water levels of PZR and makeup stora0e tank caused by various sized leaks in the RCS................ 3.4 4.2 K/A catalog 3.4-24
l i SYSTEM: 000 Emergency Plant Evolutions
[Q EPE MODE: 074 Inadequate Core Cooling IMPORTANCE K/A NO. ABILITY R0 SRO EA2.06 Changes in PZR level due to PZR steam bubble transfer to the RCS during inadequate core cooling............... 4.0 4.6 EA2.07 The difference between a LOCA and inadequate core cooling, from trends and indicators..................... 4.1 4.7 EA2.08 The effect of turbine bypass valve operation on RCS temperature and pressure................................ 3.8 4.6*
SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 1.8 3. 9
- 3. Knowledge of which events related to system operation / status should be reported. 2.7 3.9
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 3.1 4.2
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.6 4.0
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.4 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.2 4.2
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.6 3. 7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.2 4.7
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4.6 l
l K/A catalog 3.4-25 i
O .
Secondary System Heat Transport Systems and Malfunctions d
il il a
'O
O)
(
v x SYSTEM: 039 Main and Reheat Steam System (MRSS)
TASK MODE: 000 Generic TASK: Perform a lineup of the MRSS Perform MSIV partial-stroke test Warm up and pressurize main steam leads l Perform MSIV full-stroke test i Perform a moisture separator / reheater cold start Perform a moisture separator / reheater hot start Perform an MSIV trip test Operate high pressure drains Perform hydrostatic test of reheaters Operate low pressure drains Monitor reheater operation Dump steam through the atmospheric relief / dump valves Monitor the MRSS l Shut down the MRSS l IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following s systems:
C K1.01 S/G..................................................... 3.1 3.2 K1.02 Atmospheric relief dump va1ves. . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3 3.3 K1.03 I n s t r ume n t t i r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 3 2.5 Kl.04 RCS temperature monitoring and contro1.................. 3.1 3.1 K1.05 T/G..................................................... 2.5* 2.6*
Kl.06 Condenser steam dump.................................... 3.1 3.0 K1.07 AFW..................................................... 3.4* 3.4*
Kl.08 MFW..................................................... 2.7* 2.9*
Kl.09 RMS..................................................... 2.7 2.7 K2 Knowledge of bus power supplies to the following:
K2.01 MRSS.................................................... 1.5 1.8 K2.02 Moisture separater reheater va1ves...................... 1.4 1.6 K3 Knowledge of the effect that a loss of the MRSS will have on the following:
K3.01 T/G..................................................... 2.3 2.6*
K3.02 C o n de n s e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 8 1.9 K3.03 AFW pumps............................................... 3.2* 3.5*
K3.04 MFW pumps............................................... 2.5* 2.6*
O K3.05 RCS..................................................... 3.6 3.7 K3.06 S05..................................................... 2.8* 3.1 K/A catalog 3.5-1
SYSTEM: 039 Main and Reheat Steam System (MRSS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K4 Knowledge of MRSS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Expected values of main steam temperature downstream of MSIVs during warmup..................................... 1.8 1. 8 K4.02 Utilization of T-ave. program control when steam dumping through atmospheric relief / dump valves, including T-ave.
limits.................................................. 3.1 3.2 K4.03 Main condenser, including steam dump valves, operating limits, controls, indications........................... 2.3 2.5 K4.04 Utilization of steam pressure program control when steam dumping through atmospheric relief / dump valves, includ-ing T-ave. limits....................................... 2.9 3.1 K4.05 Automatic isolation of steam line....................... 3.7 3.7 K4.06 Prevent reverse steam flow on steam line break.......... 3.3 3.6 K4.07 Reactor building i solation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4 3.7 K4.08 Interlocks on MSIV and bypass valves.................... 3.3 3.4 K5 Knowledge of the followinc theoretical concepts as they apply to the MRSS:
K5.01 Definition and causes of steam / water hammer............. 2.9 3.1 K5.02 Definition and causes of thermal stress................. 2.4 2.7 K5.03 Defiaition of, and reason for, steam blanketing on mois-ture separator reheater................................. 1.9 2.2 K5.04 Effect of condenser vacuum on plant efficiency.......... 2.1 2.1 K5.05 Bases for RCS cooldown limits........................... 2.7 3.1*
K5.06 Purpose of density compensation of main steam flow...... 2.2 2.4 K5.07 Latent heat of condensation applied to moisture separa-tors.................................................... 1.8 2.0 K5.08 Effect of steam removal on reactivity................... 3.6 3.6 K6 Knowledge of the applicable performance and design attributes of the following MRSS components:
K6.01 Valves.................................................. 2.1* 2.4*
K6.02 Sensors and detectors................................... 2.0 2.1 K6.03 Controllers and positioners............................. 1.9 2.2 K6.04 Pumps................................................... 1.4 1.7 K6.05 Motors.................................................. 1.3 1. 5 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MRSS controls including:
K/A catalog 3.5-2
l
(~3 SYSTEM: 039 Main and Reheat Steam System (MR5S)
TASK MODE: 000 Generic (d'
Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A1.01 Moisture separator reheater, from its temperature and pressure................................................ 1. 7 1.7 A1.02 Temperature heatup rate limit for m1in steam piping..... 2.2 2.3 A1.03 Primary system temperature indications, and required values, during main steam system warmup................. 2.6 2.7 A1.04 Low pressure turbine metal inlet temperature indications relative to the opening and shutting of steam vents for moisture separator reheater............................. 1.8 1.9 A1.05 R C S T- a v e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2* 3.3 A1.06 Main steam pressure..................................... 3.0 3.1 A1.07 Main steam temperature.................................. 2.4 2.6 A1.08 Reheater steam pressure................................. 1.8 1.9 A1.09 Main steam line radiation monitors...................... 2.5* 2.7*
A1.10 Air ejector PRM......................................... 2.9* 3.0*
A2 Ability to (a) predict the impacts of the following mal-functions or operations on the MRSS; and (b) based on those predictions, use procedures to correct, control, or
(,. '
mitigate the consequences of those malfunctions or opera-
, \ tions:
A2.01 Flow paths of steam during a L0CA....................... 3.1 3.2 A2.02 Decrease in turbine load as it relates to steam escap-ing from relief valves.................................. 2.4 2.7*
l A2.03 Indications and alarms for main steam and area radiation monitors (during SGTR).................................. 3.4 3.7 A2.04 Malfunctioning steam dump............................... 3.4 3.7
'A2.05 Increasing steam demand, its relationship to increases i n rea c to r p owe r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3 3.6 A3 Ability to monitor automatic operation of the MRSS, l including:
A3.01 Moisture separator reheater steam supply................ 1.9* 1. 7 A3.02 I sol ati on o f the MRSS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.5*
A4 Ability to manually operate and/or monitor in the control room:
A4.01 Main steam supply va1ves................................ 2.9* 2.8*
A4.02 Remote operators to auxiliary steam..................... 2.1 1.9 A4.03 MFW pump turbiner....................................... 2.8* 2.8*
A4.04 Emergency feedov.er pump turbines....................... 3.8 3.9
/ A4.05 Moisture separator reheater, checking its temperatures
\]7 and steam pressures relative to heatup limits and oper-atinglimits............................................ 1. 8 1. 6 K/A catalog 3.5-3
_ _ - . - _ - - - - - - - - - - _ - - - _ _ _ _ - - - - - - _ _ - - - - - - . . - - - . _ - - - - _ _ _ - - _ _ _ - - _ _ _ _ _ - - - - - - _ _ - - - - - - - _ _ _ _J
SYSTEM: 039 Main and Reheat Steam System (MRSS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A4.06 Main steam drains....................................... 1.9 1. 8 A4.07 Steam dump valves....................................... 2.8* 2.9 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.6 3.1
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 2.4* 3.4
- 3. Knowledge of which events related to system operation / status should be reported. 3.1 3.5
- 4. Knowledge of system purpose and/or function. 3.4 3.6
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 3.7*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.4 2.7
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.2 3.4
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.3 4.1
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 3.5
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.1
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.1 4.3
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change.............. ............ .... .. 3.1 2.9 Normal plant operations.. .. ....... .. .. .. 3.2 2.9 l Plant heatup and startup.......... ... . .................... 2.7 2.7 Plant shutdown and cooldown.................................... 2.8 2.7 K/A catalog 3.5-4
,m U) 1 SYSTEM: 041 Steam Dump System (SDS)/ Turbine 8ypass Control TASK MODE: 020 Normal Operations TASK: Energize the SDS Shift to alternate channel (power supply) of ICS Monitor the reactor regulating control system Shift to and from various modes of SDS Operate the SDS in various modes De-energize the SDS Perform feedwater block valve junction testing Perform lineups of the SDS ,
1 IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the SDS and the following I systems:
K1.01 Circulating water to the condenser...................... 2.2 2.5 l Kl.02 S/G 1evel............................................... 2.7 2.9 gss K1.03 Feed pumps.............................................. 2.1 2.1
( Kl.04 Feedwater block valves.................................. 2.0 2.0
\/ ) Kl.05 RCS..................................................... 3.5 3.6 Kl.06 Condenser............................................... 2.6 2.9 K2 Knowledge of bus power supplies to the following:
K2.01 ICS, normal and alternate power supply.................. 2.8* 2.9*
K2.02 ICS inverter breakers................................... 2.8* 2.8*
K3 Knowledge of the effect that a loss of the SDS will have on the following:
K3.01 S/G..................................................... 3.2* 3.3 K3.02 RCS..................................................... 3.8 3.9 K3.03 T/G..................................................... 2.2* 2.4*
K3.04 R e a c t o r p owe r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5 3.4 K4 Knowledge of SDS design feature (s) and/or interlock (s) which provide for the following:
K4.01 RRG/ICS system.......................................... 2.9* 3.3*
K4.02 Condenser............................................... 2.3 2.6 K4.03 Load change............................................. 2.3 2. 6 K4.04 Operation at power...................................... 2.1 2.3 7- s\ K4.05 Plant startup........................................... 2.4 2.7 l K4.06 MFW and AFW systems..................................... 2.1 2.4
-\s_-) K4.07 Relationship of vacuum level to condenser availability.. 2.4 2.7 K4.08 Control rod index....................................... 2.3* 2.6*
l l
K/A catalog 3.5-5
SYSTEM: 041 Steam Dump System (SDS)/ Turbine Bypass Control TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K4.09 Relationship of low / low T-ave. setpoint in SDS to pri-m a ry c o o l d ow n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 0 3.3*
K4.10 PZRLCS.................................................2.3 2.5*
K4.11 T-ave . /T- re f , p ro g ram. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8 3.1 K4.12 Reason for maintaining S/G in saturated condition dur-ing coo 1down............................................ 2.3 2.4 K4.13 Relationship of S/G pressure to steam flow.............. 2.2 2.4*
K4.14 Operation of loss-of-load bistable taps upon turbine loadloss............................................... 2. 5
- 2.8*
K4.15 " Measured variable" readings on ICS hand-automatic sta-tions and required action if reading is out of the ac-ceptable band........................................... 2.9* 2.9*
K4.16 Low main steam pressure................................. 2.6* 2.7*
K4.17 Re a c to r t r i p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7 3.9 K4.18 Tu rb i n e t r i p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 4 3.6 K5 Knowledge of the following theoretical concepts as they apply to the SDS:
K5.01 Relationship of no-load T-ave. to saturation pressure relief setting on valves................................ 2.9 3.2 K5.02 Use of steam tables for saturation temperature and pressure................................................2.5 2.8 K5.03 Flow AP relation for va1ves............................. 1.9 2.1 K5.04 Basis for plant cooldown rates.......................... 2.4 3.1 K5.05 Basis for RCS design pressure limits.................... 2.6 3.2*
K5.06 Effect of power change on fuel cladding................. 2.5 2.8*
K5.07 Reacti vi ty feedback ef fects. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1* 3.6 K6 Knowledge of the applicable performance and design attributes of the following SDS components:
K6.01 Condenser............................................... 2.1 2.4 K6.02 Valves, including main and bypass feedwater valves...... 2.2 2.6*
K6.03 Controller and positioners, including ICS, S/G, CRDS.... 2.7 2.9 K6.04 Main feed pumps, including effect on capacity of internal wear.................................................... 1.8 1.9 K6.05 Sensors and detectors................................... 1.6 1.7 K6.06 Breakers, relays, and disconnects....................... 1.4 1. 7 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SDS controls including:
K/A catalog 3.5-6
.. - -. . _. -~ _ - _ _ .- . - . _ - _ .
T
- l. i l
i t
1 SYSTEM: 041 Steam Dump System (SDS)/ Turbine Bypass Control
' -(~'N TASK MODE: 020 Normal Operations Tasks as noted previously.
1 IMPORTANCE
! .K/A NO. ABILITY R0 SR0 A1.01 T-ave., verification above low / low setpoint............. 2.9* 2.9 i A1.02 Steam pressure.......................................... 3.1 3.2 A2 Ability to (a) predict the impacts of the following mal-functions or operations on the SDS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Unbalanced feedwater flow.between two MFW pumps......... 2.1* 2.1 A2.02 Steam valve stuck open.................................. 3.6 3.9 A2.03 Lo s s o f I AS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8 3.1 i
A3 Ability to monitor automatic operation of the SDS,
- including
A3.01 RCS T-ave. meter (cooldown rate)........................ 3.2* 3.2 l #~ ,s A3.02 RCS pressure, RCS temperature, and reactor power........ 3.3 3.4
( A3.03 S te am f 1 ow. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7 2. 8
\ A3.04 Condenser vacuum........................................ 2.2 2.3 A3.05 Main steam pressure..................................... 2.9* 2.9 A4 Ability to manually operate and/or monitor in the control room:
A4.01 ICS voltage inverter.................................... 2.9* 3.1*
A4.02 Cooldown va1ves......................................... 2.7* 2.9*
A4.03 T- a v e . mode . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4* 2.5*
, A4.04 Pressure mode........................................... 2.7* 2.7-A4.05 Main steam header pressure.............................. 3.1 3.3 A4.06 Atmospheric relief valve controllers.................... 2.9* 3.1 A4.07 Remote gagging of stuck open-relief' valves.............. 2.9* 3.0*
A<4.08 Steam dump valves....................................... 3.0* 3.1*
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.9* 3.3
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 2.7* 3.4 l 3. Knowledge of which events related to system operation / status
/'~ should be reported. 2.7* 3.5 K/A catalog 3.5-7 i
SYSTEM: 041 Steam Dump System (SDS)/ Turbine Bypass Control TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0
- 4. Knowledge of system purpose and/or function. 3.5 3.6
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.8 3.5*
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.0* 3.1
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.1 3.4
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifica-tions. 3.2 4.1
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.6
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.3
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate oper-ation of system components or controls. 4.2 4.3
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.7* 2.7 Normal plant operations........................................ 2.7 2.7 Plant heatup and startup....................................... 3.1 3.1 Plant shutdown and coo 1down.................................... 3.1 3. 0 O
K/A catalog 3.5-8
r\
\v)
SYSTEM: 045 Main Turbine Generator (MT/G) System TASK MODE: 000 Generic TASK: Perform overspeed trip and backup overspeed trip test of the T/G Perform turbine auto stop functional test Perform turbine valve freedom test IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the MT/G system and the following systems:
K1.01 MRSS.................................................... 2.1 2.2 Kl.02 Condenser............................................... 2.1 2.2 K1.03 AC distribution system.................................. 2.3 2.5
, Kl.04 Extraction steam system................................. 1.8 1. 9 Kl.05 Generator cooling....................................... 1.9 2.1 Kl.06 RCS, during steam valve test............................ 2.6 2.6 K1.07 Secondary systems, when testing throttle and other valves.................................................. 2.1* 2.1 f~)
V K2 Knowledge of bus power supplies to the following:
K2.01 T/G jacking gear........................................ 1.7 1.7 K2.02 T/G lube oil pumps...................................... 1.9* 2.1 K3 Knowledge of the effect that a loss of the MT/G system will have on the following:
K3.01 Remainder of the plant.................................. 2.8 3.1*
K4 Knowledge of MT/G system design feature (s) and/or inter-lock (s) which provide for the following:
K4.01 Programmed controller for relationship between steam pressure at T/G inlet (impulse, first stage) and plant power level............................................. 2.7 2.9 K4.02 Automatic shut of reheat stop valves as well as main control valves when tripping turbine.................... 2.5* 2.9*
K4.03 Voltage regulation mode................................. 1.8 2.2 K4.04 Turbine load-following mode of operation................ 2.1 2.5*
K4.05 Acceptable loading rate for T/G......................... 1.7 2.2*
K4.06 Prevention of tie-in if phase difference (generator and system) i s beyond set l imi t. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 0 2.3*
K4.07 Electrohydraulic control for response to load changes... 2.4* 2. 5
,C) K4.08 The reactor bailey station and reactor diamond station
(/ in integrated control circuitry......................... 2.6* 3. 0*
K/A catalog 3.5-9 l 1
SYSTEM: 045 Main Turbine Generator (MT/G) System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K4.09 Generator capability, including power factor, VARs and hydrogen pressure....................................... 1.8 2.2*
K4.10 Programmed controller for T-ref. signal generation from first stage (impulse) pressure in turbine............... 2.4 2.7*
K4.11 T/G reactor trip........................................ 3.6 3.9 K4.12 Automatic turbine runback.................... .......... 3.3 3.6 K4.13 Overspeed protection.................................... 2.6* 2.8*
K4.14 Measurement of valve stroke times....................... 1.5 1. 7 K5 Knowledge of the following theoretical concepts as they apply to the MT/G system:
K5.01 Possible presence of explosive mixture in generator if hydrogen puri ty deteriorates. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8* 3.2*
K5.02 Effects of moisture in steam on the turbine..... ....... 2.1 2.4 K5.03 Purpose of extraction steam system...................... 1.8 1.9*
K5.04 Basic design of turbine b1ades.......................... 1.3 1. 5 K5.05 Effect of steam reheating, feedwater heating, and con-denser vacuum on plant efficiency....................... 1.9 2.1 K5.06 Understanding of the principle of operation of voltage regulator null meter.................................... 1.7 1. 8 K5.07 Reasons why rotation of synchroscope must be slowing in fast direction prior to connection to the grid.......... 1.8 2.1*
K5.08 Even heatup/ cool down of turbine. . . . . . . . . . . . . . . . . . . . . . . . . 1.8 2.1*
K5.09 Maneuveri ng l imi ts for T/G. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.2 K6 Knowledge of the applicable )erformance and design attributes of the following iT/G system components:
K6.01 Generator stator cooling (turbine building CCW)......... 2.0 2.1 K6.02 Breakers, relays, and disconnects....................... 1.7 1.9 K6.03 Valves.................................................. 1.6 1. 7 K6.04 Main ac electrical system mimic bus..................... 2.0 2.3 K6.05 Hydrogen purity analyzer................................ 1.7 1.9 K6.06 Generator amplidyne balance system. . . . . . . . . . . . . . . . . . . . . . 1. 6* 1.8*
K6.07 Hydrogen oil seal system on generator.............. .... 1.7 1.8 K6.08 Turbine lube oil system................................. 1.7 1.8 K6.09 Steam gland seal system on turbine...................... 1.6 1. 7 K6.10 Sensors and detectors................................... 1.6 1. 7 K6.11 Controllers and positioners. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.8 1. 9 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including:
K/A catalog 3.5-10
T' SYSTEM: 045 Main Turbine Generator (MT/G) System i TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY' R0 SR0 A1.01 Normal speed, sound, vibration, temperature, pressure, and flow characteristics of T/G......................... 2.1* 2.2 A1.02 Electrical parameters for the T/G. . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.1 A1.03 Use of sounding rod to monitor bearings for high vibra-tion.................................................... 1.7 1.7 A2 Ability to (a) predict the impacts of the following mal-functions or operations on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Condensate backing up in drains and reheaters........... 1.8 1. 9 A2.02 Generator stator cooling water screen becoming clogged.. 1.9 1.9
.A2.03 Mismatch between generator output and unit demand....... 2.1 2.1 A2.04 - Improperly operating steam and turbine drains. . . . . . . . . . . 1.7 1.8 A2.05 Changing extraction steaming rates...................... 1.6 1. 6 A3- Ability to monitor automatic operation of the MT/G sys-
- tem, including:
A3.01' Recognition of trends on main T/G output meter.......... 2.1* 1.9 A3.02 Interpretation of T/G output breaker indicating lights.. 2.2* 2.1 A3.03 Interpretation of T/G voltage regulation indication..... 1.9 1.9 A3.04: T/G t r i p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4 3.6 A3.05 Electrohydraulic control................................ 2.6 2.9
'A3.06 Turbine supervisory instrumentation..................... 2.1 ~ 2. 2 A4 Ability to manually operate and/or monitor in the control room:
A4.01 Turbine valve indicators (throttle, governor, control, stop, intercept), alarms, and annunciators.............. 3.1 2.9 A4.02 T/G controls, including breakers........................ 2.7 2.6*
A4.03 T/G speed indication for on-line and off-line operation. 1.9 1.9 A4.04 Exhaust hood spray system for temperature control....... 1.9 1.6 A4.05- Electrical (T/G) and steam system adjustments........... 2.2 1.9 A4.06 Turbine stop va1ves..................................... 2.8 2.7*
A4.07 Voltage regulator....................................... 1.9 1.9 A4.08 RCS parameters (temperature and pressure), while con-
' ducting valve freedom test.............................. 2.7* 2.6*
O K/A catalog 3.5-11
SYSTEM: 045 Main Turbine Generator (MT/G) Systen.
TASK MODE: 010 Startup/ Shutdown TASK: Start up the T/G to rated speed Perform generator excitation Operate generator voltage regulator Synchronize the T/G with output grid at minimum load Increase load on the T/G Monitor the T/G Unload the T/G electrically to minimum load Secure generator output and excitation Shut down the T/G Operate the turbine turning gear Operate the turbine bearing lift oil pumps IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the MT/G system and the following systems:
Kl.01 Moisture separator reheater (interface with low pressure turbine)................................................ 1.8 1.8 K1.02 MRSS and MFW system, as T/G load is varied.............. 2.1* 2.1 Kl.03 Condenser operation (vacuum, temperature flow) heater drains, CCW and CW operations........................... 1.9 1.8 Kl.04 Electrical system, including unit auxiliary transformer and service transformer................................. 2.3 2.4 K1.05 Load control system in "following mode"................. 2.1 2.1 K1.06 Load control circuit.................................... 2.0 2.1 K1.07 Bearing lift oil pump................................... 1.7 1.7 K1.08 Turning gear operation.................................. 1.7 1.7 K1.09 Vibration and eccentricity monitoring system............ 1.6 1.7 K1.10 Turbine latching (reset) controls....................... 1.9 2.0 K1.11 RPS..................................................... 3.6 3.7 K1.12 ESFAS.............................. .................... 3.4* 3.6*
K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the MT/G system will have on the following:
K3.01 Remai nde r o f p l a n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.2 K4 Knowledge of MT/G system design feature (s) and/or inter-lock (s) which provide for the following:
K4.01 Steam blanketing (atmospheric pressure) moisture separa-tor reheater to drive out air and non-condensables prior to starting up........ ................................. 1.6 1. 7 K4.02 Recognition of unusual sounds during startup of turbine (vibration monitoring).......... ....................... 1.9 2.1 K/A catalog 3.5-12
SYSTEM: 045 Main Turbine Generator (MT/G) System (n) TASK MODE: 010 Startup/ Shutdown G) ' Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K4.03 Relationship between governor and throttle valves....... 1.8 2.1 K4.04 Use of T/G balance voltmeter prior to placing voltage regulator in service.................................... 1.6 1.8 K4.05 Low-speed rotation by turbine turning gear to prevent
" set" in shaft.......................................... 1.7 1.9 K4.06 Quenching of steam at entrance to exhaust hood by sprays.................................................. 1.6 1.6 K4.07 Changeover from bearing oil pump to shaft pump as tur-bine speed increases.................................... 1.7 1.7 K4.08 Field excitation breakers in generator.................. 1.6 1.7 K4.09 Shift from manual to automatic voltage regulation when within limits (bumpless transfer)....................... 1.6 1.7 K4.10 Closure of motor-operated disconnects before closure of main generator breakers................................. 1.9* 2.1*
K4.11 Adjustment of electrohydraulic control to maintain mini-mum load on T/G when paralleled with system............. 2.1* 2.2 K4.12 Shifting of auxiliary buses between unit auxiliary transformer and service transformer during loading of p main T/G (function of reactor power).................... 2.1* 2.3*
K4.13 Calibrations of the nuclear instrumentation as flux (v) shifts during T/G load increase (permissives and admin-istrative holds)........................................ 2.6 2.9*
K4.14 Chemical and health physics sampling as power is reduced. 1.7* 2.3*
K4.15 Load sharing between high pressure and low pressure tur-bine (shifts to low pressure turbine as T/G load in-creases also affects interface with moisture separator reheater)............................................... 1.7 1. 9 K4.16 Time required to ef fect load changes. . . . . . . . . . . . . . . . . . . . 1. 9 2.1 K4.17 Operation of auto-synchronous system.................... 1.8 2.0 K4.18 Paralleling of generator to grid when one team of gener-ator breakers is closed................................. 1.7 1.9 K4.19 Preventing of breaker closure unless generator frequency is within required amount of grid frequency............. 1.8 1.9 K4.20 Operation of CRDS in manual mode at T/G power below 15%. 2.7 2.9 K4.21 Operation of reactor in the load-following mode above l 15% power............................................... 3.1 3.2 K4.22 T/G coastdown and connection to the turning gear at zero l T/G speed............................................... 1.6 1.8 K4.23 Automatic functions associated with turbine trip: reac-i tor trip, station power switche'd to offsite source, air l to extraction steam non-return valves removed........... 3.4* 3.6 K4.24 Lube oil pump being on before engagement of turning gear. 1.7 1.8 K4.25 Load l imi te rs/runbac k. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8 3.0 Og s K5 Knowledge of the following theoretical concepts as they f
(V) apply to the MT/G system:
K/A catalog 3.5-13 l
l L. _ __ . _ . _ _ _ . _ .,
SYSTEM: 045 Main Turbine Generator (MT/G) System TASK MODE: 010 startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.01 Reasons for different procedures in hot and cold starts (temperature differential limits).................. .... 1.7 1.9 K5.02 Purpose of turning gear................................. 1.7 1.8 K5.03 Role of field excitation in generator................... 1.6 1.7 K5.04 Reason for having generator voltage slightly higher than system voltage when paralleling.......... ......... 1.6 1.7 K5.05 Reason for reactive load adjustment after paralleling... 1.6 1.7 K5.06 Reason for paralleling both generator breaker circuits.. 1.6 1. 7 K5.07 Need for heat balance as T/G load increases. . . . . . . . . . . . . 2. 0* 2.2*
K5.08 Relationship between moderator temperature cofficient and boron concentration in RCS as T/G load increases.... 2.5* 2. 7*
K5.09 Purpose of low power reactor trips (limited to 25%
power)..................................................2.7 3.2*
K5.10 Reason for minimum T/G load (to cool low pressure tur-bine blade tips)........................................ 1.7 1.9*
K5.11 Effect of temperature on lube oil viscosity............. 1.6 1. 7 K5.12 Purpose of turbine lube oil lift pump (to hold T/G off main bearing at low rotation speeds).................... 1.6 1.6 K5.13 Operation of synchroscope............................... 1.7 1. 8 K5.14 Relationship between rod control and RCS boron concen-tration during T/G load increases....................... 2.7 2.8 K6 Knowledge of the applicable performance and design attri-butes of the following MT/G system components:
K6.01 Lube oil pump........................................... 1.6 1.6 K6.02 MFW, cooling water, heater drains, and demineralizers (unless automatic controls are provided, flows must be adjusted manually during power decrease)................ 1.7 1. 7 K6.03 Valves.................................................. 1.6 1. 6 K6.04 Sensors and detectors................................... 1.6 1. 7 K6.05 Controllers and positinners. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7 1. 7 K6.06 Breakers, relays, and disconnects....................... 1.6 1. 7 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including:
A1.01 Turbine vibration and expansion during rise to full load.................................................... 1.8 1. 9 O
K/A catalog 3.5-14
SYSTEM: 045 Main Turbine Generator (MT/G) System
('~')s g TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the MT/G system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Cold and hot starts..................................... 1.7 1.8 A2.02 Unsuccessful turbine latching........................... 1.7 1. 7 A3 Ability to monitor automatic operation of the MT/G sys-tem, including:
A3.01 Turbine stop/ governor valve closure on turbine trip..... 3.5 3.6 A4 Ability to manually operate and/or monitor in the control room:
4 A4.01 Turbine supervisory instruments during startup.......... 1.8 1.9
N A4.02 Startup T/G o n l oad l imi ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9* 2.0*
i A
U l
K/A catalog 3.5-15 l l
t- 1
SYSTEM: 045 Main Turbine Generator (MT/G) System TASK MODE: 050 What If/ Abnormal TASK: What if turbine fails to trip (during startup)?
What if turbine does not trip when required (during operation)?
What if auto-synchronous system out of service?
What if computer fails while performing calorimetric test?
Steam dump valves fail to shut Delta flux exceeds operating band What if control rods are below insertion limits?
Exciter breaker fails to open using control switch on main control board?
T/G voltage regulator failure to respond to control switch IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the MT/G system and the following systems:
K1.01 Protection system....................................... 3.4 3.6 K2 Knowledge of bus power supplies to the following:
K2.01 T/G lube oil pumps...................................... 1.9* 1.9 K2.02 T/G turning gear........................................ 1.7 1.7 K3 Knowledge of the effect that a loss of the MT/G system will have on the following:
K3.01 Remainder of plant...................................... 2.9 3.1 K4 Knowledge of MT/G system design feature (s) and/or inter-lock (s) which provide for the following:
K4.01 Avoidance of T/G critical speeds........................ 1.9 2.1*
K4.02 Lockout of command relay to generator breaker........... 1.6 1.6 K4.03 Operation of SDS (turbine bypass) in event of load loss or plant trip........................................... 2.8* 3.0*
K4.04 T-ave. program, in relation to SDS controller.... ...... 2.8 3.2*
K4.05 Impulse pressure mode control of steam dumps............ 2.5* 2.8*
K4.06 Operation of low pressure steam dump to prevent T/G overspeed............................................... 2.3* 2.5*
K4.07 Defeat of reactor trip by overspeed trip test lever..... 2.5 2.8*
K4.08 Turbine trip upon reactor trip..................... .... 4.0 4.3 K4.09 Trip of T/G and lube oil pumps by FPS................... 2.1* 2.3*
K5 Knowledge of the following theoretical concepts as they apply to the MT/G system:
K6 Knowledge of the applicable performance and design attri-butes of the following MT/G system components:
K/A catalog 3.5-16
l l
1 l
1
/'~h SYSTEM: 045- Main Turbine Generator (MT/G) System l What If/ Abnormal
(/ TASK MODE: 050 Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K6.01 Valves.................................................. 1.6 1.6 K6.02 Controllers and positioners............................. 1.7 1. 8 K6.03 Sensors and detectors................................... 1.6 1.7 K6.04 Breakers, relays, and disconnects....................... 1.4 1.6 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including:
A1.01 Expected response of primary plant parameters (tempera-ture and pressure) following T/G trip................... 3.8 4.1 A1.02 Expected response of secondary plant parameters follow-ing T/G trip............................................ 3.3 3.7 A2 Ability to (a) predict the impacts of the following
, ~s malfunctions or operations on the MT/G system; and
/ \ (b) based on those predictions, use procedures to cor-(/ rect, control, or mitigate tne consequences of those malfunctions or operations:
A2.01 Steam dumps are not cycling properly at low load, or stick open at higher load (isolate and use atmospheric reliefs when necessary)................................. 2.8 3.1*
A2.02 If exciter fails, trip the T/G.......................... 2.2* 2.4*
A2.03 Vol tage regulator mal function. . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 8 2.1* i A2.04 Control problems in primary, e.g., axial flux imbal-ance; need to reduce load on secondary.................. 2.4 2.9*
A2.05 Control rod insertion limits exceeded (stabilize second-ary)....................................................2.5 2.8*
A2.06 Opening of the steam dumps at low pressure.............. 2.1 2.5*
A2.07 Loss of condenser vacuum................................ 2.1 2.4*
A2.08 Turbine overspeed....................................... 2.2* 2.6*
A2.09 Turbine blade failure................................... 2.3* 2.4*
A2.10 Malfunction of-electrohydraulic control................. 2.7* 2.9*
A3 Ability to monitor automatic operation of the MT/G sys-tem, including:
A3.01 Determination from throttle and governor indicators of turbine trip: several indications, including CRDS trip alarm................................................... 3.3* 3.5*
f T A3.02 Comparison of incoming and running voltmeters. . . . . . . . . . . 1.9 2.0
\,_ / A3.03 Electrohydraulic control system......................... 2.2 2.5*
K/A catalog 3.5-17
SYSTEM: 045 Main Turbine Generator (MT/G) System TASK MODE: 050 What If/ Abnormal Tasks as noted previously.
IMPORTANCE K/A N0. ABILITY R0 SR0 A3.04 Voltage regulator....................................... 1.9 2.0 A3.05 G e n e ra to r t ri p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6* 2.9*
A4 Ability to manually operate and/or monitor in the control room:
A4.01 T/G output breaker controls; understanding of indica-ti o n s a n d al a rm s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4
- 2.3*
A4.02 Interpretation of electrohydraulic control indications.. 2.2 2.4*
A4.03 Governor and load limits................................ 2.1 2.2 A4.04 Voltage regulator....................................... 1.9 1.8 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.7 3.1
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.1*
- 3. Knowledge of which events related to system operation / status should be reported. 2.5* 3.3*
- 4. Knowledge of system purpose and/or function. 2.9* 3.1*
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.7 3.5*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.8* 2.9
- 7. Ability to locate, explain, and apply all limits and precau-tions. 2.9 3.3
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 2.8 3.6*
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 2.9 3.2
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.1 K/A catalog 3.5-18
. . -. . _ _-. - - = _ _ _ - . . . _ _ _ _ _ _ - __
SYSTEM: 045 Main Turbine Generator (MT/G) System TASK MODE: 050 What If/ Abnormal Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate oper-ation of
. system components or controls. 3.9 4.1
, 12. Ability to perform specific system and integrated plant opera-l tions during:
s Controlled plant load change................................... 2.9* 2.8*
Normal pl a nt op e rati o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9* 2.8*
Plant heatup and startup....................................... 2.4* 2.4 Plant shutdown and cooldown.................................... 2.4* 2.5 1
w i
i I
K/A catalog 3.5-19 i
i _ - . . . . . _ , _ _ _ . _ . - .. _ _ _ , . . . . . _ _ , _ _ _ _ _ _ _ _ _ . . _ , _ . _ _ __ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _
t
!O
... i V ,
i SYSTEM: 055 Condenser Air Removal System (CARS)
TASK MODE: 000 Generic TASK: Perform lineups of the CARS.
Conduct condenser air leakage check
- Monitor the CARS operation 1
Operate the mechanical vacuum pump l Operate steam s at air ejectors
- IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following i systems:
K1.01 Main turbine generator.................................. 1.6 1.7 K1.02 Main condenser.......................................... 2.0 2.1
! Kl.03 Condensate.............................................. 1.9 2.1
! Kl.04 S/G..................................................... 1.9 2.0 l'
Kl.05 Polishing demineralizers................................ 1.5 1.5
__ K1.06 PRM system.............................................. 2.6 2.6
('~'s K1. 07. WGDS.................................................... 1.9 1.9 i g K1.08 Containment............................................. 1.7 1.6 Kl.09 A ux i l i a ry s te am . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 6 1.6
- K2 Knowledge of bus power supplies to the.following
K2.01 Vacuum pump (s).......................................... 1.6 1.7 K2.02' Exhaust fan (s).......................................... 1.5 1. 5 K3 Knowledge of the effect that a loss of the CARS will have on the following:
K3.01 Main condenser.......................................... 2.5 2.7 K3.02 T/G..................................................... 1.7 1.9 K3.03 MT/G.................................................... 1.6 1.9 K3.04 MFW pumps (steam driven)................................ 1.7 2.0*
K3.05 S0S............................................... ..... 2.3 2.6 4 '
K4 Knowledge of CARS design feature (s) and/or interlock (s)
}- which provide for the following:
< K4.01 Turbine startup......................................... 1.9 2.3*
l ,
K4.02 Effluent control and monitoring......................... 2.4 2.6*
K5 Knowledge of the following theoretical concepts as they
~
apply to the CARS:
1 i K/A catalog 3.5-21 i
,- .,n----, , - - - - - - - - - - - , - . , , - - - - - - - -, --
SYSTEM: 055 Condenser Air Removal System (CARS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.01 Measures of pressure and vacuum......................... 1.6 1.7 K5.02 Venturi effects......................................... 1.4 1.5 K5.03 Relationship between pressure and temperature........... 1.6 1.6 K5.04 S/G chemistry........................................... 1.6 1.9 K6 Knowledge of the applicable performance and design attri-butes of the following CARS components:
K6.01 Air ejectors............................................ 1.7 1.7 K6.02 Vacuum pumps............................................ 1.6 1.8 K6.03 Heat exchangers......................................... 1.3 1.4 K6.04 F l ow s e n s o r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 3 1.4 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CARS controls including:
A1.01 Condenser vacuum gauge.................................. 1.7 2.0*
A1.02 Pressure and temperature sensors........................ 1.6 1.7 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CARS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those mal-functions or operations:
A2.01 Loss of circulating cooling water system................ 2.1 2.2 A2.02 Loss of gland seal / gland exhaust....... ................ 2.1 2.1
- A2.03 Loss of air ejector cooling water....................... 1.8* 2.0*
A2.04 Ai r i n l e a ka g e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.2 l
A3 _ Ability to monitor automatic operation of the CARS, including:
A3.01 Air removal pump........................................ 1.8 1.9 A3.02 Steam to CARS........................................... 1.9 1.9 A3.03 Automatic diversion of CARS exhaust..................... 2.5* 2.7*
A4 Ability to manually operate and monitor in the control room:
A4.01 Sealing steam........................................... 1.8 1.9 A4.02 Vacuum pumps............................................ 1.8 1.9 A4.03 Steam to CARS........................................... 1.8 1.8 K/A catalog 3.5-22
SYSTEM: 055 Condenser Air Removal System (CARS)
TASK MODE: 000 Generic
[V] ' Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.1 2.4*
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.2* 2.7*
- 3. Knowledge of which events related to system operation / status should be reported. 2.2* 2.7*
- 4. Knowledge of system purpose and/or function. 2.4* 2.6
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.3 3.3*
- 6. Ability to locate and operate components, using local controls (outside the control room). 1.9 2.1
- 7. Ability to locate, explain, and apply all limits and precau-
.n tions. 2.6 2.8*
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 2.7* 3.5*
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 2.6 2.9*
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.2* 3.4*
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.3* 3.3*
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 1.9 2.0 Normal pl ant operati o ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.2 Plant heatup and startup....................................... 2.1* 2.1*
Plant shutdown and coo 1down.................................... 1.9 1.9 V
K/A catalog 3.5-23
g i i V
SYSTEM: 056 Condensate System TASK MODE: 000 Generic TASK: Perform lineups on the condensate system Operate the condensate pumps in different combinations IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the condensate system and the following systems:
K1.01 Feedwater cleanup system................................ 1.8 1. 8 K1.02 Main vacuum and gland seal systems...................... 1.6 1.6 K1.03 MFW..................................................... 2.6* 2. 6 K1.04 Condenser............................................... 1.7 1.6 K1.05 Secondary sealing water................................. 1.5 1.5 Kl.06 H e a t e r d ra i n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 4 1. 5 K1.07 Glandseals............................................. 1. 5 1. 5 K1.08 CARS.................................................... 1.6 1.6 K1.09 Extraction steam........................................ 1.6 1.6
-~s K1.10 Chemical treating....................................... 1.7 1. 7 K1.11 e t a to r c o o l i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.5
('s -) K1.12 Secondary plant component cooling. . . . . . . . . . . . . . . . . . . . . . .
- 1. 5
- 1. 6 1.6
.3 AFW..................................................... 2.4* 2.4*
K2 Knowledge of bus power supplies to the following:
- K2.01 Condensate pumps and booster pumps...................... 1.6 1.7*
K3 Knowledge of the effect that a loss of the condensate system will have on the following:
K4 Knowledge of condensate system design feature (s) and/or interlock (s) which provide for the following:
K4.01 Feedwater heating at low, intermediate, and high pres-sure.................................................... 1.6 1. 9 K4.02 Condensate demineralizer resin regenerative process..... 1.7 1.9 K5 Knowledge of the following theoretical concepts as they apply to the condensate system:
K5.01 Principle of vacuum drag................................ 1.5 1.5 K5.02 Energies associated with fluid flow (kinetic, potential, p re s s u r e ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 4 1.6 K5.03 Water hammer and methods of prevention.................. 2.2 2.6*
f- s\ K5.04 Function of lubricating oil and its application to pump ss _sl
[
and motor bearings...................................... 1.7 1. 8 K/A catalog 3.5-25
SYSTEM: 056 Condensate System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.05 Understanding of working properties of water (enthalpy, entrophy, pressure, temperature, specific volume)....... 1.7 2.0*
K5.06 Purpose of a condensate demineralizer................... 1.7 1.9 K6 Knowledge of the applicable performance and design at-tributes of the following condensate system components:
K6.01 Condensate pumps........................................ 1.7 1.9 K6.02 B o o s t e r p um p s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7 1. 9 K6.03 Main feed pumps......................................... 2.1 2.4*
K6.04 Va1ves.................................................. 1.6 1. 6 K6.05 Sensors and detectors................................... 1.4 1. 5 K6.06 Controllers and positioners............................. 1.4 1. 5 K6.07 Heat exchangers and condensers.......................... 1.4 1.7 K6.08 Breakers, relays, and disconnects....................... 1.3 1. 5 K6.09 Demineralizers.......................................... 1.7 1.9 K6.10 Pumps................................................... 1.4 1. 6 K6.11 Motors.................................................. 1.4 1.6 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the condensate system controls including:
A1.01 Pressure, flow and amps for condensate, booster, and main feed pumps......................................... 2.1* 2.4*
A2 Ability to (a) predict the impacts of the following mal-functions or operations on the condensate system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences af those malfunctions or operations:
A2.01 Loss of condenser pressure.............................. 1.8 2.0 A2.02 Bad chemistry........................................... 1.8 2.3*
A2.03 Demineralizer D/P....................................... 1.8 2.0*
A2.04 Los s o f co nden s ate p umps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 2.8*
A2.05 Condenser tube leakage.................................. 2.1 2.5*
A3 Ability to monitor automatic operation of the condensate system, including:
A3.01 Automatic hotwell level control......................... 1.8 1. 8 O
K/A catalog 3.5-26
i.
I '
r SYSTEM: 056 Condensate System TASK MODE: 000 Generic
. Tasks as noted previously.
IMPORTANCE I K/A NO. KNOWLEDGE R0 SRO A4 Ability to manually operate and/or monitor in the control
- i. room:
i ,
i A4.01 Condensate pump controls................................ 1.9 1.8 ;
! A4.02 Condensate demineralizer bypass valve and precoat bypass i valve................................................... 2.0 1.9 1
A4.03 Hotwell high level dump................................. 2.1* 2.1 1
1 1 ;
i i
i l l
I i
i i
i i
i j
1
- i. 1 4
I
- i l
l
! \
l, i
l\ l i i 1
l i l l K/A catalog 3.5-27 !'
I 4
,-,v,_ -,---~.,e n,,,. . . , , - . . -,-,n,. an _.n- - _ - - - - -.- . , - - , _ -
SYSTEM: 056 Condensate System TASK MODE: 010 Startup/ Shutdown TASK: Perform lineups on the condensate system De-aerate the condensate system prior to startup Fill the condenser hotwell Fill the condensate system Place the condensate system in high pressure cleanup operation Start up the condensate system Shut down the condensate system Operate the low pressure heaters Operate the high pressure heaters IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the condensate system and the following systems:
K1.01 Demineralizer water makeup system....................... 1.7 1.9 K1.02 Hotwell pumps, booster pumps, and main feed pumps....... 2.1 2.1 K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the condensate system will have on the following:
K4 Knowledge of condensate system design feature (s) and/or interlock (s) which provide for the following:
K4.01 Restricting hotwell level range......................... 1.7 1. 7 K4.02 Moving condensate to and from storage tank and hotwell.. 1.7 1.8 K4.03 Securing steam seals on main turbine during shutdown.... 1.5 1. 6 K4.04 Proper sequencing of hotwell pumps and condensate pol-ishing demineralizer bypass valves...................... 1.5 1.6 K4.05 Cooling condensate pump seals, using makeup water....... 1.5 1.7 K4.06 Venting condensate pump sea 1s........................... 1.4 1.5 K4.07 Feedwater pump turbine windmill protection.............. 1.8 1. 9 K4.08 Flow control valve for the gland exhaust condenser...... 1.5 1. 6 K4.09 Bypass of heater stream................................. 1.7 2.0 K4.10 Condensate minimum flow recirculation valve............. 1.6 1.6 K4.11 Condensate pump runout capacity......................... 1.7 1.7 K4.12 MFW pump NPSH........................................... 2.2 2.6*
K4.13 Booster pump starting interlock......................... 1.9 2.1*
K5 Knowledge of the following theoretical concepts as they apply to the condensate system:
K5.01 Purpose and principle of de-aeration, and oxygen removal (from condensate)....................................... 1.7 1.9 K5.02 Chemistry specs for secondary system dissolved oxygen (corrosion contro1)..................................... 1.9 2.4 KS.03 Water quality requirements for demineralizer water...... 1.7 2.0 K/A catalog 3.5-28
C'y SYSTEM: 056 Condensate System
( TASK MODE: 010 Startup/ Shutdown x
Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.04 Effects of leaks (on plant efficiency and as personnel hazard)................................................. 1.8 2.0 K5.05 Reasons for venting all high points in condensate system. 1.5 1.7 K5.06 Reasons and methods for breaking main condenser vacuum before removing main turbine seals...................... 1.6 1.7 K5.07 Purpose of low pressure cleanup valve. . . . . . . . . . . . . . . . . . . 1. 5 1.6 K5.08 Purpose of valve between upper surge tank and hotwell... 1.7* 1.7*
K5.09 Stabilization of piping system parameters after changes in chemistry............................................ 1.6 1. 8 K5.10 Limits of condensate pump ability to feed S/G........... 2.0* 2.3*
K6 Knowledge of the applicable performance and design at-tributes of the following condensate system components:
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the condensate system controls including:
A1.01 Hotwell level alarms.................................... 1.6 1.6 A1.02 Normal sequence of alarms on startup of condensate pumps, including low suction pressure alarm............. 1.6 1. 6 A2 Ability to (a) predict the impacts of the following mal-functions or operations on the condensate system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Abnormal hotwell pump discharge pressure................ 1.6 1.7 A2.02 Removal of a condensate demineralizer from service...... 1.7 1.9 A3 Ability to monitor automatic operation of the condensate system, including:
A3.01 Hotwell and condensate storage tank level indicators.... 1.9 2.1 A3.02 Upper surge tank f1owmeter.............................. 1.7* 1.6*
A3.03 Condensate flow, header pressure, pump amperage and run-ning indicators, and related alarms and annunciators.... 1.8 1.7 A4 Ability to manually operate and/or monitor in the control room:
j A4. '11 Cleanup valve........................................... 1.8 1. 7 A4.02 Valve between upper surge tank and hotwell . . . . . . . . . . . . . . 1.8* 1.7*
l K/A catalog 3.5-29 1
SYSTEM: 056 Condensate System TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A4.03 Condensate demineralizer bypass valve controller........ 1.8 1.8*
A4.04 H o tw e l l p ump s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7 1.7 A4.05 Condensate automatic makeup valve controller............ 1.7 1. 5 A4.06 Demineralizer flow control va1ve........................ 1.9* 1.7*
A4.07 Low pressure and high pressure cleanup valves........... 1.7* 1.6*
A4.08 Setpoints on polish demineralizer bypass valve controllers............................................. 1. 6 1.6 A4.09 Condensate pump, including verification of proper start-up from parameter readings.............................. 1.7 1.7 A4.10 Alarms associated with booster pump operation........... 1.7 1.7 A4.11 Auxiliary oil pumps for bocster pumps. . . . . . . . . . . . . . . . . . . 1. 6 1.6 A4.12 Turbine and feedwater pump turbine exhaust hood temper-atures during shutdown.................................. 1.6 1. 5 A4.13 Heater unit controls and control valves during heater startup/ shutdown........................................ 1.5 1.5 A4.14 Hotwell high-level dump valve........................... 1.9 1.7 O
O K/A catalog 3.5-30
i i
O SYSTEM: 056 020 Condensate System Normal Operations Q TASK MODE:
TASK: Operate the condensate pumps in different combinations Operate the condensate booster pumps in different combinations Operate the hotwell pumps Manually operate the condensate hotwell makeup and dump system Monitor condensate system operate Operate the low pressure heaters i Operate the high pressure heaters 1 Operate the condensate pump and air ejector recirculation subsystem l What if high water level exists in the low pressure feedwater '
heater during turbine operations?
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 i
K1 Knowledge of the physical connections and/or cause- -
effect relationships between the condensate system and the following systems:
K1.01 Demineralizer bypass valve (prevent water impact on resin beds during pump startup)......................... 1.8 1.8 K1.02 Feed system, the polishing demineralizer system, and the condensate strainer operation........................... 1.9 2.1*
r
/ K2 Knowledge of bus power supplies to the following:
\
K3 Knowledge of the effect that a loss of the condensate system will have on the following:
K3.01 MFW..................................................... 2.4* 2.4*
K3.02 CARS.................................................... 1.6 1. 7 K3.03 MFW pumps............................................... 2.2* 2.3 K3.04 Heater drain pumps...................................... 1.6 1. 6 K3.05 Extraction steam........................................ 1.6 1.6 K3.06 Gland steam system...................................... 1.5 1. 6 K3.07 Stator coolant.......................................... 1.7 1.6 K3.08 Hydrogen coolers........................................ 1.6 1.6 K4 Knowledge of condensate system design feature (s) and/or interlock (s? which provide for the following:
K4.01 Low-level and high-level heaters........................ 1.6 1.7 K4.02 Adjustment of automatic setpoint on polish demineralizer bypass valves........................................... 1.6 1.7 K4.03 Interlocks between booster pumps and auxiliary oil pumps. 1.5* 1.7 K4.04 Setpoints and trip levels for condensate pump and booster pump operations................................. 1.9 1.9 l K4.05 Flow rate linits of condensate piping system............ 1.6 1.7 g K4.06 Operation of hotwell pump and air ejector recirculation line isolati:n valve to maintain header pressure........ 1.5* 1.7*
(
V) K4.07 Feed pump ana booster pump NPSH protection. . . . . . . . . . . . . . 2.1 2.4*
K/A catalog 3.5-31
1 SYSTEM: 056 Condensate System TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K5 Knowledge of the following theoretical concepts as they apoly to the condensate system:
K5.01 Principles and mechanisms of S/G water level control.. .. 2.2* 2.3*
K6 Knowledge of the applicable performance and design at-tributes of the following condensate system components:
K6.01 Valves.................................................. 1.4 1. 6 K6.02 Sensors and detectors................................... 1.4 1.5 K6.03 Controllers and positioners............................. 1.5 1. 6 K6.04 Pumps................................................... 1.6 1. 7 K6.05 Heat exchangers and condensers.......................... 1.6 1.7 K6.06 Demineralizers and ion exchangers....................... 1.7 1.9 K6.07 Breakers, relays, and disconnects....................... 1.2 1. 5 K6.08 Motors.................................................. 1.4 1. 6 ABILITY Al Ability to predict and/or monitor changes in parameters
{to prevent exceeding design limits) associated with operating the condensate system controls including:
A1.01 Hotwell level alarms and flow indicators................ 1.6 1. 7 A1.02 Differential pressure indicators and limits imposed (across pumps, demineralizers).......................... 1.6 1. 7 A1.03 Heater parameters (temperature, pressure, flow level) and their effects on condensate flow.................... 1.7 1.8 A1.04 S/G level under transient induced by feed rate change (pumps on and off)...................................... 2.1 2.3*
A1.05 MFW pump suction pressure............................... 2.3 2.6*
A2 Ability to (a) predict tropacts of the following mal-functions or operatigt, p .'le condensate system; and (b) based on those Jr < ct .1s, use procedures to cor-rect, control, or n iga k lie consequences of those~~
malfunctions or operations:
A2.01 Feedwater heater tube leak.............................. 1.6 1. 8 A2.02 Feedwater l evel high or l ow. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 6 1. 7 A2.03 Decreased effectiveness of condensate demineralizer due to increased flow through it............................ 1.5 1.7 A2.04 Approximate time necessary to regenerate one cbadensate demineralizer resin bed................................. 1.6 1.8*
K/A catalog 3.5-32
SYSTEM: 056 Condensate System TASK MODE: 020 Normal Operations J Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A2.05 Opening of the heater string bypass valve............... 1.8 2.1*
A2.06 -Opening of the condensate recirculation valve........... 1.7 1. 8 A2.07 Opening of the condensate spill valve. . . . . . . . . . . . . . . . . . . 2. 0 2. 2 A3 Ability to monitor automatic operation of the condensate system, including:
A3.01 Verification (from multiple indicators) that condensate pumps are operating..................................... 2.1 2.1 A3.02 Monitoring of steam jet air ejector air flow............ 1.7 1.8*
A3.03 Remote and local feedwater heater level indicators...... 1.7 1.6 A3.04 Determination whether the differential pressure of the condensate demineralizer is within limits............... 1.6 1. 7 A3.05 Flow through stator coolant and hydrogen coolers........ 1.6 1. 5 A3.06 Automatic protection of MFW pump low suction pressure... 2.2 2.4*
A4 Ability to manually operate and/or monitor in the control room:
b O
A4.01 Hotwell level alarms and flow indicators................ 1.9 1.7 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.2 2.6*
~
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.1 2.7*
- 3. Knowledge of which events related to system operation / status should be reported. 2.1 2.7*
, 4. Knowledge of system purpose and/or function. 2.6* 2.8*
l
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.4* 3.0*
- 6. Ability to locate and operate components, using local controls (outside the control room). 1.9 2.1
- 7. Ability to locate, explain, and apply all limits and precau-tions. 2.4 2.7*
- 8. Ability to recognize indications for system operating param-O eters, which are entry level conditions for technical specifica-tions. 2. 5 3.2*
K/A catalog 3.5-33
SYSTEM: 056 Condensate System TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0 i 9. Ability to verify system alarm setpoints and operate controls l identified in the alarm response manual. 2.6 2.6
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.2* 3.2*
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.2* 3.2*
- 12. Ability to perform specific sy.etem and integrated plant opera-tions during: ,
Controlled plant load change................................... 2.1 2. 2 Normal plant operations........................................ 2.2 2.4 Plant heatup and startup....................................... 2.2* 2.4*
Plant shutdown and cooldown.................................... 2.1 2.2 O
O K/A catalog 3.5-34 1
/ T (v/
SYSTEM: 059 Main Feedwater (MFW) System TASK MODE: 000 Generic TASK: Perform initial lineup of the MFW system Perform feedwater isolation valve functional test Fill the MFW system Perform MFW pump turbine tachometer overspeed trip test Start up the MFW system Operate the MFW pumps in different combinations Operate the feedwater regulating system in manual and automatic modes ,
Operate / test MFW pump lube oil pump monitor MFW system operations Shut down the MFW system What if the automatic S/G water level control does not respond properly?
j IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 l
K1 Knowledge of the physical connections and/or cause-effect relationships between the MFW system and the fol-lowing systems:
in\ Kl.01 Condensate.............................................. 2.3* 2.3
(__,) K1.02 AFW system.............................................. 3.4* 3.4 K1.03 S/GS.................................................... 3.1 3.3 Kl.04 S/G water level control system.......................... 3.4 3.4 K1.05 RCS..................................................... 3.1* 3.2 K1.06 Chemical treatment...................................... 1.9 2.1*
K1.07 1CS..................................................... 3.2* 3.2*
K1.08 Heater drains........................................... 1.6 1. 6 K1.09 Secondary cool i ng wate r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7 1. 8 K1.10 Extraction steam........................................ 1.7 1. 7 K2 Knowledge of bus power supplies to the following:
K2.01 MFW system pumps........................................ 2.2* 2.3*
K2.02 M0Vs.................................................... 2.0* 2.1 K3 Knowledge of the effect that a loss of the MFW system j will have on the following:
K3.01 Condensate system....................................... 1.8 1.8 K3.02 AFW system.............................................. 3.6 3.7 K3.03 S/GS.................................................... 3.5 3.7 K3.04 RCS..................................................... 3.6 3.8 1 1
K4 Knowledge of MFW system design feature (s) and/or inter- i lock (s) which provide for the following:
['~}
x,'
.% K/A catalog 3.5-35
SYSTEM: 059 Main Feedwater (MFW) System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K4.01 MFW and startup feedwater valve coordination............ 2.4 2.6*
K4.02 Automatic turbine / reactor trip runback.................. 3.3 3.5 K4.03 Adequate condensate flow................................ 2.1 2.3*
K4.04 Heating of feedwater.................................... 1.9 2.2 K4.05 Control of speed of MFW pump turbine.................... 2.5* 2.8*
K4.06 Comparison of actual D/P, between main steam and MFW pump discharge pressure, to programmed D/P when placing MFW pump in automatic mode.............................. 2.2* 2.4*
K4.07 Ciosing MFW pump drains................................. 1.6* 1.7*
K4.08 Feedwater regulatory valve operation (on basis of steam flow, feed flow mismatch)............................... 2.5 2.7 K4.09 Controlling MFW pump lube oil system.................... 1.7 1. 8 K4.10 Bearing oil signal to the turning gear start sequence... 1.7 1.8 K4.11 " Porting oil"........................................... 1.8? 1. 9?
K4.12 Sources of cooling water for MFW pump lube oil cooler... 1.8 1. 9 K4.13 Feedwater fill for S/G upon loss of RCPs. . . . . . . . . . . . . . . . 2. 9 2.9 K4.14 S ta rt pe rm i s s i ve s fo r MFW p ump . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.3*
K4.15 Automatic starts for MFW pumps.......................... 2.2* 2.4*
K4.16 Automatic trips for MFW pumps........................... 3.1* 3.2*
K4.17 Increased feedwater flow following a reactor trip....... 2.5* 2.8*
K4.18 Automatic feedwa'er t reduction on plant trip............. 2.8* 3.0*
K4.19 Automatic isolation of the MFW.......................... 3.2 3.4 K4.20 Automatic feed pump recirculation flow.................. 1.9 2.2*
K5 Knowledge of the following theoretical concepts as they apply to the MFW system:
K5.01 Variation of flow with discharge pressure............... 2.1 2.1 K5.02 S h r i n k and swel 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4 2.6*
K5.03 Reason for maintenance of minimum D/P between main steam and MFW pump turbine discharge pressure........... 2.1 2.2 K5.04 Definition of water hammer.............................. 2.3* 2.6*
K5. 06 Reason for balancing MFW pump loads..................... 2.0 2.2*
K5.06 Characteristics of level, flow, and pressure indications. 1.8 2.1*
K5.07 Relationship between feedwater pump speed and feedwater regulating valve position............................... 1.8 2.1*
K5.08 Reason for matching steam flow and feedwater flow. . . . . . . 2.4 2.6*
K5.09 Effects of low temperature and high viscosity on oil syster operations....................................... 1.6 1.7 K5.10 Theory of film-riding oil in a journal bearing.......... 1.4 1.6 K5.11 Definition o f " turbine windmilling". . . .'. . . . . . . . . . . . . . . . . 1. 6 1. 7 KS.12 Increased MTW pump discharge with increased turbine speed................................................... 2.2* 2.5*
K5.13 Reasons for monitoring feedwater pump suction flow /
pressure...... ......................................... 2.3 2.6*
K5.14 Q ua d ra n t p owe r t i l t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.4*
K/A catalog 3.5-36
t
< / \
SYSTEM: 059 Main Feedwater (MFW) System t
O' TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6 Knowledge of the applicable performance and design at-tributes of the following MFW system components:
K6.01 Valvcs.................................................. 1. 9 2.1*
K6.02 Sensors and detectors.................... .............. 1.9 1.9 K6.03 Controllers and positioners............................. 1.9 2.1*
K6.04 Pumps................................................... 1.9 2.1*
K6.05 Motors.................................................. 1.7 1.9*
K6.06 Heat exchangers and condensers.......................... 1.6 1.8 K6.07 Breakers , relays , and disconnects. . . . . . . . . . . . . . . . . . . . . . . 1.4 1.7 K6.08 S/G controller logic for MFW regulating valve. . . . . . . . . . . 2.3* 2.5*
l K6.09 MFW pump speed and flow-regulating valves (reason for adjusting positions of both). . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4* 2.6*
K6.10 Feedwater isolation valve travel time................... 1.9 2.1*
K6.11 High and low feedwater discharge header pressure........ 1.9 2.1*
ABILITY O
h Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW system controls including:
A1.01 Location, limits, and normal ranges for level, pressure, flow, temperature, and rpm measurements associated with the MFW system.......................................... 2.4* 2.5*
A1.02 MFW pump oil temperatures and MFW pump vibrations....... 1.8 1.9
! A1.03 Power level restrictions for operation of MFW pumps and
- va1ves..................................................2.7* 2.9*
A1.04 Main s*eam pressure..................................... 2.2* 2.2*
l A1.05 S/G 1evel, comparison with normal values................ 2.4* 2.6 l A1.06 Abnormal noises or vibrations of MFW pump............... 1.8 2.0*
A1.07 Feed pump speed, including minimum control speed for ICS. 2.5* 2.6*
A1.08 Oil pressure indications for MFW pumps.................. 1.7 1.8 l A1.09 Feedwater pump bearing temperatures..................... 1.7 1.8 l A1.10 Feedwater pump seal leakoff temperature................. 1.6 1.6 A1.11 Feedwater regulating valve D/P.......................... 2.2* 2. 2 A2 Ability to (a) predict the impacts of the following mal-functions or operations on the MFW system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or
/~'N operations:
' !'j A2.01 Automatic actuation of AFW system....................... 3.4* 3.6*
A2.02 Loss of feedwater heater................................ 2.2* 2.5*
K/A catalog 3.r-37 l
t
SYSTEM: 059 Main Feedwater (MFW) System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2.03 Overfeeding event....................................... 2.7* 3.1*
A2.04 Feeding a dry S/G....................................... 2.9* 3.4*
A2.05 Rupture in MFW suction or discharge line................ 3.1* 3.4*
A2.06 Loss of steam flow to MFW system........................ 2.7* 2.9*
A2.07 Tripping MFW pump turbine............................... 3.0* 3.3*
A2.08 Extremely low MFW pump control lube oil or bearing oil pressure................................................ 1.9 2.2*
A2.09 Overspeed on turning gear............................... 1.6 1.8 A2.10 Secondary cooling water................................. 1.7 1.8 A2.11 Failure of feedwater control system..................... 3.0* 3.3*
A2.12 Failure of feedwater regulating valves.................. 3.1* 3.4*
A2.13 Loss of condensate / heater drain flow.................... 2.1* 2.1*
A3 Ability to monitor automatic operat. ion of the MFW sys-tem, including:
A3.01 Valve timer display..................................... 2.0* 2.1*
A3.02 Programmed levels of the S/G............................ 2.9 3.1 A3.03 Feedwater pump suction flow pressure.................... 2.5 2.6*
A3.04 Turbine-driven feed pump................................ 2.5* 2.6*
A3.05 Starts and stops on the main feed pumps................. 2.4* 2.7*
A3.06 Feedwater isolation..................................... 3.2* 3.3 A3.07 1CS..................................................... 3.4* 3.5*
A4 Ability to manually operate and/or monitor in the control room:
A4.01 MFW turbine trip indication............................. 3.1* 3.1*
A4.02 Null-out of MFW pump D/P differences.................... 2.3* 2.4*
A4.03 Feedwater flow control during power increase and decrease................................................ 2.9* 2.9 A4.04 Reset MFW overspeed trip................................ 2.2* 2.3*
A4.05 MFW pump oil cooler, cooling-water outlet valve con-troller................................................. 1.7 1.8 A4.06 MFW pump turbine reset switch........................... 2.4* 2.3*
A4.07 Valve timer reset pushbutton............................ 2.0* 1.9*
A4.03 Feed regulating valve controller........................ 3.0* 2.9 A4.09 Remote determination of operating feedwater pump turn-ing gear................................................ 2.1* 2.0*
A4.10 1C5..................................................... 3.S* 3.8*
A4.11 Recovery from automatic feedwater isolation. . . . . . . . . . . . . 3.1 3.3 A4.12 Initiation of automatic feedwater isolation............. 3.4 3.5 O
K/A catalog 3.5-38
O SYSTEM:
TASK MODE:
059 000' Generic Main Feedwater (MFW) System Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.9* 3.3
- 2. Knowledge of system status criteria which require the notifi-
- cation of plant supervisors or off plant personnel. 2.4* 2.9*
- 3. Knowledge of which events related to system operation / status should be reported. 2.4* 3.2*
- 4. Knowledge of system purpose and/or function. 3.1* 3.3*
- 5. Knowledge of the Technical Specification bases and definitions l related to limiting conditions for operations and safety limits. 2.8* 3.5*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.3* 2.5
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.0 3.4
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-2.9* 3.7*
cations.
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.0 3.3
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.7 4.0
! 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.8 3.9 3
- 12. Ability to perform specific system and integrated plant opera-tions during:
i
- Controlled plant load change................................... 2.7* 2.9*
i Normal plant operations........................................ 2.7* 2.7*
Plant heatup and startup....................................... 2.7* 2.9*
Plant shutdown and cooldown.................................... 2.4 2.6*
.t .
i K/A catalog 3.5-39
/
(
V SYSTEM: 061 Auxiliary / Emergency Feedwater (AFW) System TASK MODE: 000 Generic TASK: Perform lineups of the AFW system Perform AFW system operability demonstration What if the AFW system did not operate properly automatically?
Fill and vent the AFW system Auxiliary feed pump failure due to improper valve lineup Start up the AFW system Perform AFW automatic actuation test Feed steam generators with AFW system Perform S/G auxiliary feed pumps test Operate motor-driven AFW pumps Perform S/G auxiliary feed pump flow capacity test Operate turbine-driven AFW pumps Perform testing of AFW check valves Shift auxiliary feed pump suction Perform exercise of AFW MOVs test Overspeed test the auxiliary feed pump turbine Shut down the AFW system Drain the AFW pump turbine and steam supply header (3 !
s IMPORTANCE k/ K/A NO. KNOWLEDGE R0 SR0
_ K1 Knowledge of the physical connections and/or cause-effect relationships between the AFW system and the fol-lowing systems:
K1.01 S/G system.............................................. 4.1 4.2 K1.02 MFW system.............................................. 3.4 3.7 K1.03 Main steam system....................................... 3.5 3.9 K1.04 RCS..................................................... 3.9 4.1 Kl.05 Condensate system....................................... 2.6* 2.8*
K1.06 Cooling water........................................... 2.4* 2.6*
Kl.07 Eme rge ncy wa te r s o u rce. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 6 3.8 kl.08 Chemical treatment...................................... 2.1 2.3*
Kl.09 PRMS.................................................... 2.6* 2.8*
K1.10 D i e s e l f u e l 0 i 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6
- 2.7*
K1.11 AFW turbine exhaust / drains.............................. 2.7 2.8*
K2 Knowledge of bus power supplies to the following:
K2.01 AFW system M0Vs......................................... 3.2* 3.3 K2.02 AFW electric-driven pumps............................... 3.7* 3.7 K2.03 AFW d i e s e l -d ri ven p ump. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 0* 3.8*
C
- K3 Knowledge of the effect that a loss of the AFW system k will have on the following
K/A catalog 3.5-41
SYSTEM: 061 Auxiliary / Emergency Feedwater (AFW) System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K3.01 RCS..................................................... 4.4 4.6 K3.02 S/G..................................................... 4.2 4.4 K4 Knowledge of AFW system design feature (s) and/or inter-lock (s) which provide for the following:
K4.01 Water sources and priority of use....................... 3.9 4.2 K4.02 AFW automatic start upon loss of MFW pump, S/G level, bl ackout , or safety i njection. . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 5 4.6 K4.03 Automatic blowdown / sample isolation........ ...........2.7 2.9*
K4.04 Prevention of AFW runout by limiting AFW flow........... 3.1 3.4 K4.05 Prevention of MFW swapover to AFW if AFW suction pres-sure is low............................................. 3.5* 3.7*
K4.06 AFW startup pe rmi s si ve s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 0* 4.2*
K4.07 Turbine trip, including overspeed....................... 3.1* 3.3*
K4.08 AFW recirculation....................................... 2.7 2.9 K4.09 Crossties between mul ti-unit stations. . . . . . . . . . . . . . . . . . . 3.7* 4.1*
K4.10 Reset of MFW reactor trip logic......................... 2.6 2.9*
K4.11 Automatic level control................................. 2.7* 2.9*
K4.12 Natural ci rcul ati on f10w. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5* 3.7 K4.13 Initiation of cooling water and lube oi1................ 2.7 2.9 K4.14 AFW automati c i s ol ati on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5* 3.7*
K5 Knowledge of the following theoretical concepts as they apply to the AFW system:
K5.01 Relationship between AFW flow and RCS heat transfer..... 3.6 3.9 K5.02 Decay heat sources and magnitude........................ 3.2 3.6 K5.03 Pump head effects when control valve is shut............ 2.6 2.9*
K5.04 Reason for warming up turbine prior to turbine startup.. 2.3 2.5*
K5.05 Feed li ne voidi ng and water hammer. . . . . . . . . . . . . . . . . . . . . . 2. 7 3.2 K6 Knowledge of the applicable performance and design at-tributes of the following AFW system components:
K6.01 Controllers and positioners. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5 2.8*
K6.02 Pumps................................................... 2.6 2.7 K6.03 Motors.................................................. 2.0 1.9 K6.04 Breakers, relays, and disconnects....................... 1.7 1.9 K6.05 Valves.................................................. 2.3* 2.5*
K6.06 Sensors and detectors................................... 2.1 2.4*
K6.07 Pump lube oil system and cooling........................ 2.0 2.2 K6.08 Bearing oil supply for turbine-driven pumps............. 2.1 2.3 9
K/A catalog 3.5-42
(O
'O j SYSTEM:
TASK MODE:
061 000 Auxiliary / Emergency Feedwater (AFW) System Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW system controls including:
A1.01 S /G 1 e v e l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.9 4.2 A1.02 S/G pressure............................................ 3.3* 3.6*
A1.03 Interactions when multi-unit systems are cross-tied..... 3.1* 3.6*
A1.04 AFW s o urce tank l ev e1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 9 3.9 A1.05 AFW flow / motor amps..................................... 3.6 3.7 4
A1.06 S/G hydrotest parameters................................ 1.7 1.7 i A2 Ability to (a) predict the impacts of the following mal-functions or operations on the AFW system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
f'~'sI A2.01 Startup of the MFW pump during AFW operation............ 2.5 2.6*
A2.02 Loss of air to steam supply va1ve....................... 3.2* 3.6*
l
( A2.03 Loss of de power........................................ 3.1 3.4 A2.04 Pump failure or improper operation...................... 3.4 3.8 A2.05 Automatic control mal function. . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1* 3.4*
A2.06 B ac k l e a kage o f M FW. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7 3.0 A2.07 Air or MOV failure...................................... 3.4 3.5 A2.08 Flow rates expected from various combinations of AFW pump discharge valves................................... 2.7* 2.9*
A3 Ability to monitor automatic operation of the AFW sys-tem, including:
A3.01 AFW startup and flows................................... 4.2 4.2 A3.02 RCS cooldown during AFW operations...................... 4.0 4.0 A3.03 AFW S/G level control on automatic start................ 3.9 3.9 A3.04 Automatic AFW isolation................................. 4.1 4.2 A3.05 Recognition of leakage, using sump level changes........ 2.5* 2.5 A3.06 S/G blowdown / sampling isolation......................... 2.2* 2.3 A4 Ability to manually operate and/or monitor in the control room:
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, i test, and surveillance activities. 3.7 4.0 V
K/A catalog 3.5-43
SYSTEM: 061 Auxiliary / Emergency Feedwater (AFW) System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 3.0* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.8
- 4. Knowledge of system purpose and/or function. 4.0 4.0
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditiom ior operations and safety limits. 3.3 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 3. 5 3.6
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.6 4.1
- 8. Ability to recognize indications for system operating param-eters, whic' are entry level conditions for Technical Specifi-cations. 3.7 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.6 3.9
- 10. Ability to recognize abnormal indications for system operating parameters, which a:e entry-level conditions for emergency and abnormal cperating procedures. 4.4 4.5
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operatirn of system components or controls. 4.4 4.4
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change............... .. .............. 2.4 2.5 Normal plant operations............................... ...... 2.4 2.5 Plant heatup and startup....................................... 3.1 3.2 Plant shutdo'.. and coo 1down.................................... 3.1 3.2 O
K/A catalog 3.5-44
,~"
! )
'J SYSTEM: 076 Service Water System (SWS)
TASK MODE: 000 Generic TASK: Perform lineups of the SWS Perform the SWS valve test Fill and vent the SWS Perform a service water pump test Start up the SWS Monitor the SWS Operate service water pumps in various combinations Operate heat exchangers in different combinations (two-train SWS)
Isolate service water from individual components Shut down the SWS IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems:
Kl.01 CCW system.............................................. 3.4 3.3
,_s K1.02 Turbine lube oil system................................. 1.8 1.8
/ 3 K1.03 Relationship of SWS to raw water filtrating (RWF) sys-( '~'
/ tem and location of SWS supply pump to RWF system....... 1.9* 1.9*
K1.04 Relationship of domestic water to lube water for SWS pumps................................................... 1.8* 1.9*
Kl.05 0/G..................................................... 3.8* 4.0*
K1.06 Switch gear room coolers................................ 2.1* 2.0*
K1.07 Secondary closed cooling water.......................... 2.5* 2.3 Kl.08 R H R sy s t e m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5* 3.5*
K1.09 Reactor building closed cooling water................... 3.0* 3.1*
K1.10 Turbine building closed cooling water................... 2.1* 2.1 Kl.11 Domestic water and raw water............................ 1.7 1. 6 K1.12 Intake screen system.................................... 1.9 2.1 Kl.13 LRS..................................................... 2.3* 2.3*
Kl.14 Condenser circulating water................ ............ 2.1 2.1 Kl.15 FPS..................................................... 2.5 2.6 K1.16 ESF..................................................... 3.6 3.8 Kl.17 PRMS.................................................... 3.6* 2.7 Kl.18 SWS no rma l hea t l oad s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.2 K1.19 SWS emergency heat loads................................ 3.6* 3.7 Kl.20 AFW..................................................... 3.4* 3.4*
Kl.21 Auxiliary backup SWS.................................... 2.7* 2.9*
Kl.22 Water treatment......................................... 1.8 1.8 Kl.23 Spent fuel pool makeup.................................. 2.1* 2.2*
Kl.24 Chemical addition....................................... 1.8 1.9 Kl.25 Heat sink pond makeup................................... 2.4* 2.3*
K1.26 Flood alarm system...................................... 2.2* 2.2*
('~'}J
\
v K/A catalog 3.5-45
SYSTEM: 076 Service Water System (SWS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K2 Knowledge of bus power supplies to the following:
K2.01 Service water........................................... 2.7* 2.7 K2.02 Closed cooling water.................................... 2.2* 2.2*
K2.03 Secondary closed cooling water.......................... 2.1* 2.0*
K2.04 Reactor building closed cooling water................... 2.5* 2.6*
K2.05 Turbine building closed cooling water................... 2.0* 2.0*
K2.06 RHR components, controls, sensors, indications and alarms, including radiation monitors.................... 2.2* 2.4*
K2.07 Cooling tower fans...................................... 2.2* 2.1*
3.1* 3.3*
K2.08 ESF-actuated M0Vs.......................................
K2.09 Traveling screens....................................... 1.8 2.2*
K3 Knowledge of the effect that a loss of the SWS will have on the following:
K3.01 Closed cooling water.................................... 3.4* 3.6*
K3.02 Secondary closed cooling water. . . . . . . . . . . . . . . . . . . . . . . . . . 2.5* 2.8*
K3.03 Reactor building closed cooling water................... 3.5* 3.9*
K3.04 Turbine building closed cooling water................... 2.2* 2.4*
K3.05 RHR components, controls, sensors, indicators, and alarms, including rad monitors.......................... 3.0* 3.2*
K3.06 Turbine lube oil system................................. 1.7 1.8 K3.07 ESFloads...............................................3.7 3.9 K3.08 Radioactive liquid waste discharges..................... 2.3 2.9*
K3.09 Normal process heat loads............................... 1.9 2.1 K4 Knowledge of SWS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Conditions initiating automatic closure of closed cool-ing water auxiliary building header supply and return valves.................................................. 2.5* 2.9*
K4.02 Automatic start features associated with SWS pump controls................................................ 2.9 3.2 K4.03 Automatic opening features associated with SWS isolation valves to CCW heat exchanges. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9* 3.4*
K4.04 River i ntake water level recorders. . . . . . . . . . . . . . . . . . . . . . 2. 2* 2.5*
K4.05 Service water train flow and discharge pressure when service water flow to heat exchanger for closed cooling water is throttled...................................... 2.3* 2.6*
K4.06 Service water train separation.......................... 2.8 3.2 K5 Knowledge of the following theoretical concepts as they apply to the SWS:
K/A catalog 3.5-46
n SYSTEM: 076 Service Water System (SWS) !
TASK MODE: 000 Generic (v) Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6 Knowledge of the applicable performance and design at-tributes of the following SWS components:
K6.01 Va1ves.................................................. 1.9 2.0 K6.02 Sensors and detectors................................... 1.7 1. 9 K6.03 Controllers and positioners............................. 1.9 2.0 K6.04 Pumps................................................... 2.1 2.2*
K6.05 Motors.................................................. 1.7 1.8 K6.06 Heat exchangers and condensers.......................... 2.2 2.4*
K6.07 Breakers, relays, and disconnects....................... 1.7 1.9 K6.08 Cooling towers.......................................... 1.7* 1.8*
K6.09 Traveling screens....................................... 1.6 1.7 K6.10 Strainers............................................... 1.5 1.6 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including:
A1.01 Line losses in SWS, by comparing SWS pump discharge and turbine building gauge.................................. 1.9 1.9 A1.02 Reactor and turbine building closed cooling water tem-peratures............................................... 2.6* 2.6*
A2 Ability to (a) predict the impacts of the following mal-functions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or opdrations:
A2.01 L o s s o f SW S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5* 3.7*
A2.02 Service water header pressure........................... 2.7 3.1 A3 Ability to monitor automatic operation of the SWS, in-cluding:
A3.01 Normal process heat loads............................... 2.4 2.5 A3.02 Emergency heat loads.................................... 3.7 3.7 A4 Ability to manually operate and/or monitor in the control room:
A4.01 SWS p ump s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9 2.9 2.6 (G A4.02 SWS v a 1 v e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6 K/A catalog 3.5-47
SYSTEM: 076 Service Water System (SWS)
TASK MODE: 000 Generic Tasks as ncted previously IMPORTANCE K/A NO. ABILITY R0 SRO A4.03 Normal process heat 1oads............................... 2.3 2.4 A4.04 Emergency heat loads.................................... 3.5* 3.5 A4.05 Traveling water screens system.......................... 2.0 2.1 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.8 3.2
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.6* 3.3*
- 3. Knowledge of which events related to system operation / status should be reported. 2.5* 3.3*
- 4. Knowledge of system purpose and/or function. 3.1* 3.3
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.6 3.7*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.3 2.7
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.0 3.4*
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.3 3.9 9 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.1 3.4
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.7* 4.0
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9* 4.0*
O K/A catalog 3.5-48
1 1
}
i % SYSTEM: 076 Service Water System (SWS)
- . TASK MODE
- 000 Generic Tasks as noted previously.
i' IMPORTANCE I
SYSTEM GENERIC K/As R0 SRO 1
- 12. Ability to perform specific system and integrated plant opera-
- tions during
! Controlled pl ant load change. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 3* 2.2 Normal plant operations........................................ 2.4* 2.4 Plant heatup and startup....................................... 2.4* 2.3 Plant shutdown and coo 1down.................................... 2.4* 2.3 0
4 a
1 i
l 4
i i
i
.i I
- i i
4 1
l l
i i
i
! K/A catalog 3.5-49 1
._.m__.______...___._, _ _ . _ , _, _ . _ . _ _ . _ , _ _.
(o) ss_-
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 040 Steam Line Rupture IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the steam line rupture emergency task:
EK1.01 Consequences of PTS..................................... 4.1 4.4 EKl.02 Leak rate versus pressure change........................ 3.2 3.6 EK1.03 RCS shrink and consequent depressurization.............. 3.8 4.2 EK1.04 Nil ductility temperature............................... 3.2 3.6 EK1.05 Reactivi ty ef fects o f coo 1 down. . . . . . . . . . . . . . . . . . . . . . . . . . 4.1 4.4 EK1.06 High-energy steam line break considerations............. 3.7 3.8 EKl.07 Effects of feedwater introduction on dry S/G. . . . . . . . . . . . 3.4 4.2
, EK2 Knowledge of the following components:
EK2.01 Va1ves.................................................. 2.6* 2.5 EK2.02 Sensors and detectors................................... 2.6* 2.6 EK2.03 Controllers and positioners............................. 2.4* 2.4
/ EK2.04 Pumps................................................... 2.0 2.1
('-- EK2.05 Breakers, relays, and disconnects....................... 1.9 2.1 EK2.06 Motors.................................................. 2.0 2.1 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Operation of steam line isolation valves................ 4.2 4.5 EK3.02 ESFAS initiation........................................ 4.4 4.4 EK3.03 Steam line non-return va1ves............................ 3.2* 3.5*
EK3.04 Actions contained in E0Ps for steam line rupture........ 4.5 4.7 EK3.05 A i rl o c k l e a k te s ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1* 2.3*
EK3.06 Containment temperature and pressure considerations..... 3.4 3.9 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Manual and automatic ESFAS initiation................... 4.6 4.6 EA1.02 Feedwater i s ol ati on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 5 4.5 EA1.03 Isolation of one steam line from header................. 4.3 4.3 EA1.04 Isolation of all steam lines from header................ 4.3 4.3 EA1.05 Manual and automatic RPS trip initiation................ 4.5 4.5 EA1.06 S/G and steam line pressures and flows.................. 4.0 4.1 EA1.07 Steam pressures and flow rates via computer, safety parameter display system, and other indications......... 3.4* 3.7 y'~'s EA1.08 Normal operating steam parameters, as a function of
( ) power................................................... 3.6 3.7 K/A catalog 3.5-51
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 040 Steam Line Rupture IMPORTANCE K/A NO. ABILITY R0 SR0 EA1.09 Setpoints of main steam safety and P0RVs................ 3.4* 3.4 EA1.10 AFW system.............................................. 4.1 4.1 EA1.11 MFW system.............................................. 3.2* 3.1*
EA1.12 RCS pressure and temperature............................ 4.2 4.2 EA1.13 Steam line isolation valve indications.................. 4.2 4.2 EA1.14 Nuclear instrumentation................................. 4.2 4.2 EA1.15 T-ave. protection indicators............................ 3.9* 3.8*
EA1.16 Reactor coolant loop delta temperature gauges........... 3.4 3.4*
EA1.17 Reactor trip breaker indicators......................... 4.3 4.3 EA1.18 Control rod position indicators......................... 4.2 4.2 EA1.19 Postaccident monitoring panel indicators................ 3.8* 3.9 EA1.20 Containment pressure and temperature trends............. 4.1 4.2 EA1.21 Vibration a1 arm......................................... 2.3* 2.5 EA1.22 Load sequencer status lights............................ 3.0* 3.0*
EA1.23 All pressure gauges per steam generator (for pressure drop)................... ............................... 3.6 3.5 EA1.24 Main steam header pressure gauges.............. ........ 3.8 3.8 EA2 Ability to determine or interpret:
EA2.01 Occurrence and location of a steam line rupture from pressure and flow indications........................... 4.2 4.7 EA2.02 Conditions requiring a reactor trip..................... 4.6 4.7 EA2.03 Difference between steam line rupture and LOCA.......... 4.6 4.7 EA2.04 Conditions requiring ESFAS initiation................... 4.5 4.7 EA2.05 When ESFAS systems may be secured....................... 4.1 4.5 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 2.9* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.7
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.2 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.5* 3.7*
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.7 4.2
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.6 4.4 K/A catalog 3.5-52
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 040 Steam Line Rupture
. IMPORTANCE
- 4 SYSTEM GENERIC K/As R0 SR0
- 9. Ability to verify system alarm setpoints and operate controls i identified in the alarm response manual. 3.8 4.0 i-
- 10. Ability to recognize abnormal indications for system operating
! parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.4 4.6
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of 4.6 4.6 system components or controls.
I i
i i
i i
e i
I i,
i i
i f
i I
j r i
i I i t
i K/A catalog 3.5-53
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 051 Loss of Condenser Vacuum IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the Loss of Condenser Vacuum emergency task:
EK1.01 Relationship of condenser vacuum to circulating water, flow rate, and temperature.............................. 2.4* 2.4*
EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 1.6 1.6 EK2.02 Controllers and positioners............................. 1.6 1.6 EK2.03 Pumps................................................... 1.6 1.5 "
EK2.04 Motors.................................................. 1.6 1. 5 EK2.05 Heat exchangers and condensers.......................... 1.7* 1.6 EK2.06 Sensors and detectors................................... 1.6 1.5 EK2.07 Steam jet air ejectors and vacuum pumps................. 1.9* 1.7 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Loss of steam dump capability upon loss of condenser vacuum.................................................. 2.8* 3.1*
ABILITY EAl Ability to operate and monitor the following:
EA1.01 Condenser vacuum pump................................... 1.9* 1.9 EA1.02 Condenser vacuum........................................ 2.3* 2.2*
EA1.03 Gland steam header pressure............................. 2.0* 1.9 EA1.04 Rod position............................................ 2.5* 2.5*
EA1.05 Turbine header pressure................................. 1.8* 1.7 EA1.06 Turbine throttle and governor valves position........... 2.0* 2.0 EA1.07 Feedwater flow.......................................... 2.2* 2.2*
EA1.08 Air ejector steam supply................................ 2.3* 2.1 EA1.09 Circulating water system................................ 2.1* 2.0 EA2 Ability to determine or interpcet:
EA2.01 Cause for low vacuum condi tion. . . . . . . . . . . . . . . . . . . . . . . . . . 2.4* 2.7*
EA2.02 Conditions requiring reactor and/or turbine trip........ 3.9 4.1 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 2.5* 2. 9*
- 3. Knowledge of which events related to system operation / status should be reported. 2.5* 3.2*
K/A catalog 3.5-54
_ _= __ .- - ._ - __. -
/^ SYSTEM: 000 Emergency Plant Evolutions
(. EPE MODE: 051 Loss of Condenser Vacuum IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.8 3.6*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.3* 2.8*
- 7. Ability to locate, explain, and apply all limits and precau-tions. 2.8* 3.2*
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 2.9* 3.6*
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.0 3.1
- 10. Ability to recognize abnormal indications for system operating
! parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.6 3.9
- 11. Ability to perform those actions, without reference to proce-( dure, for all casualties which require immediate oper-ation of system components or controls. 3.7* 3.7 5
4 1
l l
1(
K/A catalog 3.5-55
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 054 Loss of Main Feedwater (MFW)
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the loss of MFW emergency task:
EK1.01 MFW line break depressurizes the S/G (similar to a steam line bre1k)............................................. 4.1 4.3 EKl.02 Effects of feedwater introduction on dry S/G............ 3.6 4.2 EK2 Knowledge of the following components:
EK2.01 Valves....... .......................................... 2.4* 2.3 EK2.02 Controll e r ar.d pos i tioners. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2* 2.2 EK2.03 Pumps................................................... 2.1 2.2 EK2.04 Motors.................................................. 1.9 2.0 EK2.05 Heat exchangers and condensers.......................... 1.9 2.1 EK2.06 Breakers, relays, and disconnects....................... 1.8 1.9 EK2.07 Sensors and detectors................................... 2.1 2.2 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Reactor and/or turbine trip, manual and automatic....... 4.1 4.4 EK3.02 Matching of feedwater and steam flows................... 3.4* 3.7*
EK3.03 Manual control of AFW flow control valves............... 3.8 4.1 EK3.04 Actions contained in E0Ps for loss of MFW............... 4.4 4.6 EK3.05 HPI/PORV cycling upon total feedwater loss.............. 4.6 4.7 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 AFW controls, including the use of alternate AFW sources. 4.5 4.4 EA1.02 Manual startup of electric and steam-driven AFW pumps... 4.4 4.4 EA1.03 AFW auxiliaries, including oil cooling water supply..... 3.5 3.7 EA1.04 HPI, under total feedwater loss conditions.............. 4.4 4.5 EA2 Ability to determine or interpret:
EA2.01 Occurrence of reactor and/or turbine trip............... 4.3 4.4 EA2.02 Differentiation between loss of all MFW and trip of one MFW pump................................................ 4.1 4.4 EA2.03 Conditions and reasons for AFW pump startup............. 4.1 4.2 EA2.04 Proper operation of AFW pumps and regulating valves..... 4.2 4.3 EA2.05 Status of MFW pumps, regulating and stop valves......... 3.5 3.7 EA2.06 AFW adjustments needed to maintain proper T-ave and S/G 1evel................................................... 4.0 4.3 EA2.07 Reactor trip first-out panel indicator.................. 3.4* 3.9 EA2 08 Steam flow-feed trend recorder.......................... 2.9 3.3*
K/A cataloO 3.5-56
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 054 Loss of Main Feedwater (MFW)
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.4
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.6*
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1* 3.8*
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.1* 3.4
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.6 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical specifi-cations. 3.3 4.0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.6 3.7 N 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.2
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.3 4.3 K/A catalog 3.5-57
O Containment Integrity Systems and Malfunctions E
o !
e-lO i
i v)
!(
I SYSTEM: 007 Pressurizer Relief Tank / Quench Tank System (PRTS)
TASK MODE: 000 Generic TASK: Perform lineups of the PRT (quench tank)
Fill the PRT Monitor the PRT l Transfer the PRT (quench tank) contents Add nitrogen to the PRT i Vent nitrogen from the PRT Recirculate the PRT (quench tank) with cooling pumps Operate the PRTS to form a steam bubble in the PZR l IMPORTANCE l
K/A NO. KNOWLEDGE R0 SRO K1 Knowledae of the physical connections and/or cause-l effect relationships between the PRTS and the following systems:
Kl.01 Containment system...................................... 2.9 3.1 l Kl.02 WGDS.................................................... 2.3 2.4 l
K1.03 RCS..................................................... 3.0 3.2 i
K1.04 Nitrogen................................................ 2.1 2.3
'x_/ Kl.05 Makeup / fill water....................................... 2.1 2.2 K2 Knowledge of bus power supplies to the following:
i l K3 Knowledge of the effect that a loss of the PRTS will have on the following:
K3.01 Containment............................................. 3.3 3.6 K4 Knowledge of PRTS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Quench tank cooling..................................... 2.6 2.9 K4.02 Source of makeup / fill water............................. 2.2 2.3 l K4.03 Nitrogen cover gas...................................... 2.0 2.2 K5 Knowledge of the following theoretical concepts as they apply to the PRTS:
K5.01 Principles of steam quenching........................... 2.2 2.6 KS.02 Method of forming a steam bubble in the PZR............. 3.1 3.4 K5.03 Characteristics of convection heat transfer............. 1.8 2.1 b
K/A catalog 3.6-1 t
SYSTEM: 007 Pressurizer Relief Tank / Quench Tank System (PRTS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.04 Properties of noncondensable gases in contact with water................................................... 1.9 2.2 K5.05 Characteristics of conduction heat transfer............. 1.8 2.1 K5.06 Properties of condensable gases in contact with water... 1.9 2.2 K6 Knowledge of the applicable performance and design at-tributes of the following PRTS components:
K6.01 Va1ves.................................................. 1.9 2.0 K6.02 Sensors and detectors................................... 1.8 1.9 K6.03 Pumps................................................... 1.4* 1.7*
K6.04 Motors.................................................. 1. 3
- 1.6*
K6.05 Breakers , relays , and disconnects. . . . . . . . . . . . . . . . . . . . . . . 1.6 1.8 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:
A1.01 Maintaining quench tank water level within limits....... 2.9 3.1 A1.02 Maintaining quench tank pressure........................ 2.7 2.9 A1.03 Monitoring quench tank temperature...................... 2.6 2.7 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Stuck-open PORV or code safety. . . . . . . . . . . . . . . . . . . . . . . . . . 3. 9 4.2 A2.02 Abnormal pressure i n the PRT. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 3.2 A2.03 Oterpressurization of the PZR........................... 3.6 3.9 A2.04 Ovarpressurization of the waste gas vent header......... 2.5 2.9 A2.05 Exceeding PRT high pressure limits...................... 3.2 3.6 A2.06 Bubble formation in PZR................................. 2.6 2.8 A2.07 Reci rcul ati ng quench tan k. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 3* 2.6*
A3 Ability to monitor automatic operation of the PRTS, in-cluding:
A3.01 Components which discharge to the PRT................... 2.7* 2.9 O
K/A catalog 3.6-2
~
f'N SYSTEM: 007 Pressurizer Relief Tank / Quench Tank System (PRTS)
) TASK MODE: 000 Generic v
Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 PRT spray supply va1ve.................................. 2.7* 2.7*
A4.02 PRT drain valve......................................... 2.2 2.2 A4.03 Nitrogen block valve.................................... 2.1 1.9 A4.04 PZR vent valve.......................................... 2.6* 2.6 A4.05 PZR heaters............................................. 2.4* 2.2*
A4.06 Throttle va1ve.......................................... 2.4* 2.2*
A4.07 Converting inches (or feet) of tank level to gallons (or percent)............................................ 1.6 1. 8 A4.08 Location and interpretation of radioactive gas recorder. 2.2* 2.3 A4.09 Relationships between PZR level and changing levels of the PRT and bleed holdup tank........................... 2.5 2.7 A4.10 Recognition of leaking PORV/ code safety. . . . . . . . . . . . . . . . . 3.o 3.8 SYSTEM GENERIC K/As
( 1. Knowledge of operator responsibilities during maintenance,
(, test, and surveillance activities. 2.7 2.8
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisor or off plant personnel. 2.6* 3.1 {
l
- 3. Knowledge of which events related to system operation / status should be reported. 2.6* 3.1
- 4. Knowledge of system purpose and/or function. 3.3* 3.4*
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.0* 3.5*
- 6. Ability to locate and operate components, using local controls (outside the control room). 1.9 2.6
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.1* 3.4
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 2.9* 3.7*
- 9. Ability to verify system alarm setpoints and operate controls
/ i identified in the alarm response manual. 3.4 3.4 4 /
v K/A catalog 3.6-3
SYSTEM: 007 Pressurizer Relief Tank / Quench Tank System (PRTS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.5* 3.7
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.6* 3.6
- 12. Ability to perform specific system and integrated plant opera- -
tions during: S Controlled plant load change................................... 2.2* 2.1 Normal plant operations........................................ 2.2* 2.1 Plant heatup and startup....................................... 2.4* 2.4 Plant shutdown and coo 1down.................................... 2.3 2.3 O
O
m
/ \
SYSTEM: 022 Containment Cooling System (CCS)
TASK MODE: 000 Generic TASK: Perform lineups of the CCS Fill and vent the CCS Start the CCS Monitor the CCS (air and water sides)
What if lower containment temperature cannot be controlled within specified limits?
Shut down the CCS
_ IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems:
1 K1.01 SWS/ cooling system...................................... 3.5 3.7 I K1.02 SEC/ remote monitoring systems........................... 3.7? 3.5?
K1.03 Auxiliary steam......................................... 2.4* 2.3*
Kl.04 Chilled water........................................... 2.9* 2.9* l
/ 'N 1 Knowledge of power supplies to the following:
( ) K2 K2.01 Containment cooling fans................................ 3.0* 3.1 K2.02 Chillers................................................ 2.5* 2.4* ,
K2.03 M0Vs.................................................... 2.3* 2.3 '
K3 Knowledge of the effect that a loss of the CCS will have on the following -
l K3.01 Containment equipment subject to damage by high or low l temperature, humidity, and pressure..................... 2.9* 3.2* l K3.02 Containment instrumentation readings.................... 3.0 3.3 K3.03 Electrical insulation................................... 1.7 2.1 K4 Knowledge of CCS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Cooling of containment penetrations..................... 2.5* 3.0*
i K4.02 Correlation of fan speed and flowpath changes with containment pressure.................................... 3.1* 3.4*
K4.03 Automatic containment isolation......................... 3.6* 4.0*
K4.04 Cooling of control rod drive motors..................... 2.8 3. 3 K4.05 Containment cooling after LOCA destroys ventilation ducts................................................... 2.6* 2.7 s, K4.06 Containment pipe chase cooling.......................... 2.1* 2.4*
7 i 4 V
K/A catalog 3.6-5
w SYSTEM: 022 Containment Cooling System (CCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5 Knowledge of the following theoretical concepts as they apply to the CCS:
K5.01 Gas laws (Boyles, Charles), to appreciate environmental conditions.............................................. 1. 6 2.0 K6 Knowledge of the applicable performance and design at-tributes of the following CCS components:
K6.01 Valves.................................................. 1.9 2.1 K6.02 Sensors and detectors................................... 2.1 2.1 K6.03 Controllers and positioners............................. 1.8 2.0 K6.04 Pumps................................................... 1.6 1.8 K6.05 Motors.................................................. 1.7 1.9 K6.06 Breakers, relays, and disconnects....................... 1.7 1.9 K6.07 Computers and calculators............................... 1.8 1.9 K6.08 Heat exchangers and condensers.......................... 1.9 2.0 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including:
A1.01 Containment temperature................................. 3.6 3.7 A1.02 Containment pressure.................................... 3.6 3.8 A1.03 Containment humidity.................................... 3.1 3.4 A1.04 Cooling water flow...................................... 3.2 3.3 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Fan motor over-current............ ..................... 2.5 2.7 A2.02 Fan motor vibration..................................... 2.3 2.6 A2.03 Fan motor thermal overload /high-speed operation. . . . . . . . . 2.6 3.0 A2.04 Loss of service water................................... 2.9* 3.2 A2.05 Major leak in CCS....................................... 3.1 3.5 A2.06 Loss of CCS pump.... ................................... 2.8* 3.2*
A3 Ability to monitor automatic operation of the CCS, in-cluding:
A3.01 Initiation of safeguards mode of operation.............. 4.1 4.3 K/A catalog 3.6-6
SYSTEM: 022 Containment Cooling System (CCS)
/n\ TASK MODE: 000 Generic b Tasks as noted previously.
IMPORTANCE K/A N0. ABILITY R0 SR0 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 CCS fans................................................ 3.6 3.6 A4.02 CCS pumps............................................... 3.2* 3.1*
A4.03 Dampers in the CC5...................................... 3.2* 3.2*
A4.04 Valves in the CC5....................................... 3.1* 3.2 A4.05 Containment readings of temperature, pressure, and hu-midity system........................................... 3.8 3.8 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.1 3.3
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.3
- 3. Knowledge of which events related to system operation / status (n
v
) should be reported. 2.6* 3.5
- 4. Knowledge of system purpose and/or function 3.5 3.8
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.8 3.8
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9* 3.0
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.4 3.8
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.3 4.1
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.2 e 11. Ability to perform those actions, without reference to proce-( dure, for all casualties which require immediate operation of
'N system components or controls. 3.9* 4.1 K/A catalog 3.6-7
SYSTEM: 022 Containment Cooling System (CCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.5 2.5 Normal plant operations........................................ 2.7 2. 6 Plant heatup and startup....................................... 2.7 2.7 Plant shutdown and cooldown.................................... 2.4 2.5 O
l l
l l
l l
i O
K/A catalog 3.6-8 l
l
,c f 1 5 /
Nd SYSTEM: 025 Ice Condenser System TASK MODE: 000 Generic TASK: Monitor the ice condenser system IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the ice condenser system and the following systems:
K1.01 Containment ventilation................................. 2.7* 2.7*
Kl.02 Refrigerant systems..................................... 2.7* 2.7*
K1.03 Containment sump system................................. 3.2* 3.0*
K2 ' Knowledge of bus power supplies to the following:
K2.01 Containment ventilation fans and dampers................ 2.2" 2.7*
K2.02 Refrigerant systems..................................... 2.0* 2.5*
K2.03 Isolation valves........................................ 2.0* 2.2*
K3 Knowledge of the effect that a loss of the ice con-7s s i denser system will have on the following:
,h "
.1 Containment............................................. 3.8* 3.8*
K4 Knowledge of ice condenser system design feature (s) and/
or interlock (s) which provide for the following:
K4.01 Glycol expansion tank levels and ice condenser system containment isolation valves............................ 2.2* 2.5*
K4.02 System contro1.......................................... 2.8* 3.0*
K5 Knowledge of the following theoretical concepts as they apply to the ice condenser system:
K5.01 Relationships between pressure and temperature.......... 3.0* 3.4*
K5.02 Heat transfer........................................... 2.6* 2.8*
K5.03 Gas laws................................................ 2.4" 2.8*
K6 Knowledge of tha applicable performance and design attri-butes of the following ice condenser system components:
K6.01 Upper and lower doors of the ice condenser.............. 3.4* 3.6*
ABILITY
[\,_,-)
Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ice condenser system controls including:
K/A catalog 3.6-9
SYSTEM: 025 Ice Condenser System TASK MODE: 000 Generic Task as noted previously.
IMPORTANCE K/A N0. ABILITY R0 SR0 A1.01 Temperature chart recorders............................. 3.0* 3.0*
A1.02 Glycol expansion tank 1evel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5* 2.2*
A1.03 Glycol flow to ice condenser air handling units......... 2.5* 2.5*
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ice condenser system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operat 's:
A2.01 Trip of glycol circulation pumps........................ 2.2* 2.7*
A2.02 High/ low floor cooling temperature...................... 2.7* 2.5*
A2.03 Opening of ice condenser doors............. ............ 3.0* 3.2*
A2.04 Containment isolation................................... 3.0* 3.2*
A2.05 Abnormal glycol expansion tank level . . . . . . . . . . . . . . . . . . . 2. 5* 2.7*
A2.06 Decreasing ice condenser temperature.................... 2.5* 2.7*
A3 Ability to monitor automatic operation of the ice con-denser system, including:
A3.01 Refrigerant system...................................... 3.0* 3.0*
A3.02 Isulation va1ves........................................ 3.4* 3.4*
A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Ice condenser isolation valves... ............ ......... 3.0* 2.7*
A4.02 Containment vent fans.................. .. ............ 2.7* 2.5*
A4.03 Glycol circulation pumps..................... .. ...... 2.2* 2.2*
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.2* 3.0*
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.2* 3.2*
- 3. Knowledge of wnich events related to system operation / status should be reported. 2.2* 3.2*
- 4. Knowledge of system purpose and/or function 3.4* 3.6*
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.0* 3.8*
O K/A catalog 3.6-10
p SYSTEM: 025 Ice Condenser System Generic
, V) c TASK MODE: 000 Task as noted previously. .
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.2* 2.5*
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.2* 3.2*
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.2* 4.0*
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.0* 3.2*
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.8* 4.0*
- 11. Ability to perform those actions, without reference to proce-
', ("N dure, for all casualties which require immediate operation of 3.8* 4.0*
Q system components or controls.
L2. Ability to perform specific system and integrated plant opera-tions during:
Control led plant load change. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5* 2.5*
Normal plant operations........................................ 2.5* 2.5*
Plant heatup and startup....................................... 2.7* 2.78 Plant shutdown and coo 1down.................................... 2.5* 2.5*
O V
K/A catalog 3.6-11
1 ig)
'V SYSTEM: 026 Containment Spray System (CSS)
TASK MODE: 000 Generic TASK: Perform lineup of the CSS Monitor CSS IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems:
Kl.01 ECCS.................................................... 4.2 4.2 Kl.02 Cooling water........................................... 4.1 4.1 K2 Knowledge of bus power supplies to the following:
K2.01 Containment spray pumps................................. 3.4* 3.6 K2.02 M0Vs.................................................... 2.7* 2.9 K3 Knowledge of the effect that a loss of the CSS will have 7s on the following:
( )
%./
K3.01 CC$..................................................... 3.9 4.1 K3.02 Recirculation spray system.............................. 4.2* 4.3*
K4 Knowledge of CSS design feature (s) and/or interlock (s) which prcvide for the following:
K4.01 Source of water for CSS, including recirculation phase after L0CA.............................................. 4.2 4.3 K4.02 Neutralized boric acid to reduce corrosion and remove inorganic fission product iodine from steam (Na0H) in containment spray....................................... 3.1 3.6 K4.04 Reduction of temperature and pressure in containment after a LOCA by condensing steam, to reduce radiological hazard, and protect equipment from corrosion damage (spray)................................................. 3.7 4.1 K4.05 Prevention of material from clogging nozzles during recirculation............................................ 2.8 3.3 K5 Knowledge of the following theoretical concepts as they apply to the CSS:
K5.01 Water chemistry relationship to corrosion control....... 2.2 2.9*
K5.02 Principle of eductor flow............................... 1.9* 2.2*
b G
K/A catalog 3.6-13
SYSTEM: 026 Containment Spray System (CSS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6 Knowledge of the applicable performance and design at-tributes of the following CSS components:
K6.01 Valves.................................................. 2.0 2.1 K6.02 Pumps................................................... 2.4* 2.4*
K6.03 Sensors and detectors................................... 2.2* 2.3 K6.04 Controllers and positioners............................. 2.0 2.1 K6.05 Heat exchangers......................................... 2.1 2. 2*
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including:
A1.01 Containment pressure.................................... 3.9 4.2 A1.02 Containment temperature................................. 3.6* 3.9 A1.03 Containment dump level......... ........................ 3.5 3.5 A1.04 Containment humidity...... ............................. 3.1 3.3 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Reflux boiling pressure spike when first going on re-circulation................. .......................... 2.7 3.0 A2.02 Failure of automatic recirculation transfer.... ........ 4.2* 4.4*
A2.03 Failure of ESF.......................................... 4.1 4.4 A2.04 Failure of spray pump.................. .. ............. 3.9 4.2 A2.05 Failure of chemical addition tanks to inject............ 3.7 4.1 A3 Ability to monitor automatic operation of the CSS, in-cluding:
A3.01 Pump starts and correct MOV positioning............... . 4.3 4.5 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 CSS controls.. .......... ............... ............. 4.5 4.3 O
K/A catalog 3.6-14
bh SYSTEM: 026 Containment Spray System (CSS)
( TASK MODE: 020 Normal Operations TASK: Perform lineup of the CSS Fill the CSS Perform the recirculation spray systems valve test Fill the containment spray chemical additive tank Perform the recirculation spray subsystem pumps test Recirculate a spray tank Manually initiate containment spray Monitor the CSS Perform the containment spray pump test Perform postaccident recirculation Secure containment spray Isolate the CSS Drain the CSS IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems:
K1.01 Waste water holdup tank (vent).......................... 2.1* 2.0*
<- K1.02 Fill / makeup water....................................... 2.2* 2.2*
'\s) K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the CSS will have o_n the following:
K4 Knowledge of CSS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Iodine scavenging via the CSS........................... 2.8 3.2*
K4.02 Adequate level in containment sump for suction
( i n t e rl o c k) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 8* 4.1*
K4.03 Automatic swapover to containment sump suction for re-circulation phase after LOCA (RWST low-low level alarm). 4.1* 4.3*
K4.04 Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after after swapover)................................... 3.7* 4.1*
K5 Knowledge of the following theoretical concepts as they apply to the CSS:
K5.01 Stratification of liquids: concentrated Na0H solution has a higher specific gravity than weak boric acid solu-tion, so they must be vigorously mixed to make an effec-p tive spray.............................................. 2.0 2.5*
1 Chemistry control....................................... 2.0 2.7
( v ) KS.02 K6 Knowledge of the applicable performance and design at-tributes of the following CSS components:
K/A catalog 3.6-15
SYSTEM: 026 Containment Spray System (CSS)
TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 Al Ability to predict and/or monitor changes in parameters Qo prevent exceeding design limits) associated with operating the CSS controls including:
A1.01 Chemical additive tank level and concentration. . . . . . . . . . 3.1 3.4 A1.02 Containment spray pump cooling.......................... 2.7 3.0 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Increase in spray flow following swapover, because of 2.2 2.6 higher pump suction pressure.............................
A2.02 Loss of containment spray pump suction when in recircu-lation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded (cavitation, void-ing), or sump level below cutoff (interlock) limit. . . . . . 3.6 3.9 A2.03 Safe securing of containment spray (when it can be done)................................................... 3.2 3.7 A2.04 Radiation hazard potential of BWST...................... 2.5* 2.9*
A3 Ability to monitor automatic operation of the CSS, in-cluding:
A3.01 Verification that cooling water is supplied to the con-tainment spray heat exchanger........................... 3.9* 4.2*
A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 The remote location and use of spool pieces and other equipment to set up portable recirculation pump for additive tank, including power supply................... 2.3* 2.6*
A4.02 The remote location and use of the special tank needed for draining C5S........................................ 2.2* 2.5*
A4.03 The remote sampling of the Na0H tank and RWST/BWST for chemical analysis....................................... 2.2* 2.6*
A4.04 Containment spray reset switches........................ 3.5 3.5 O
K/A catalog 3.6-16
,- SYSTEM: 026 Containment Spray System (CSS)
J TASK MODE: 020 Normal Operations G;
Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC X/As R0 SR0
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.7 4.1
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 2.8* 3.6
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.6
- 4. Knowledge of system purpose and/or function. 3.9 4.2
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.3 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.1* 3.4
- 7. Ability to locate, explain, and apply all limits and precau-p tions. 3.6 4.1 Ability to recognize inaications for system operating param-8.
eters, which are entry level conditiens for Technical Specifi-cations. 3.6 4.4
- 9. Ability to verify system alara setpoints and operate controls identified in the alarm response manual. 3.6 3.9
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.3 4.6
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4.5
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.5 2.5 Normal plant operations........................................ 2.5 2.4 Plant heat and startup......................................... 2.9* 2.8 Plant shutdown and cooldown.................................... 2.6 2.6 O
V K/A catalog 3.6-17
73 iv) -
SYSTEM: 027 Containment Iodine Removal System (CIRS)
TASK MODE: 000 Generic TASK: Operate the containment iodine removel units Monitor the containment iodine removal units IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the CIRS and the following systems:
K1.01 CSS..................................................... 3.4* 3.7*
K2 Knowledge of bus power supplies to the following:
K2.01 Fans.................................................... 3.1* 3.4*
K3 Knowledge of the effect that a loss of the CIRS will have on the following:
fg K4 Knowledge of CIRS design feature (s) and/or interlock (s) which provide for the following:
(w/ )
K5 Knowledge of the following theoretical concepts as they apply to the CIRS:
K5.01 Purpose of charcoal fil ters. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1* 3.4*
K6 Knowledge of the applicable performance End design at-tributes of the following CIRS components:
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CIRS controls including:
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CIRS; and (b) based on those predictions, use Procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 High temperature in the filter system................... 3.0* 3.3*
f x, A3 Ability to monitor automatic operation of the CIRS,
' including:
\.)I K/A catalog 3.6-19
SYSTEM: 027 Containment Iodine Removal System (CIRS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A4 Ability to manually operate and/or monitor in the control room:
A4.01 CIRS controls........................................... 3.3* 3.3*
A4.02 Remote operation and handling of iodine filters......... 2.8* 3.0*
A4.03 CIRS fans............................................... 3.3* 3.2*
A4.04 Filter temperature...................................... 2.8* 2.9*
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.1* 3.4*
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 2.7* 3.5*
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.5*
- 4. Knowledge of system purpose and/or function. 3.3* 3.4*
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.6* 3.8*
- 6. Ability to locate and operate components, using local controls (outside the control roem). 2.6* 2.9*
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.1* 3.6*
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.1* 3. 9*
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.1* 3.4*
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.8* 4.1*
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9* 4.1*
O K/A catalog 3.6-20
1 L
t.
SYSTEM: 027 Containment Iodine Removal System (CIRS)
TASK MODE: 000 Generic !
l Tasks as noted previously.
I IMPORTANCE !
SYSTEM GENERIC K/As R0 SRO l 12. Ability to perform specific system and integrated plant opera-l, tions during:
i j Controlled plant load change................................... 2.4* 2.2*
- Normal plant operations........................................ 2.4* 2.2*
l Plant heat and startup......................................... 2.4* 2.2*
! Plant shutdown and cooldown.................................... 2.6* 2.4*
1 1
1 t
I i !'
is
.: i i
4 l- l j
i i
t i I
l i i i '
1 i
i 1
!, K/A catalog 3.6-21
, . - - - . . . . . _ . . ~ . - _ _ _ _ _ . -._..._. .. - _~.__-_--.---__..-_,...,.-_.,-.:
V SYSTEM: 028 Hydrogen Recombiner and Purge Control System (HRPS)
TASK MODE: 000 Generic TASK: Perform lineups of the HRPS Perform hydrogen recombiner test Start up the hydrogen recombiners Start up the hydrogen purge system Monitor the HRPS Shut down the hydrogen purge system Operate the hydrogen analyzer IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the HRPS and the following systems:
Kl.01 Containment annulus ventilation system (including pres-sure limits)............................ .............. 2.5* 2.5 K1.02 Air supply system....................................... 2.0* 2.2*
/S K2 Knowledge of bus power supplies to the following:
> 1 K2.01 Hydrogen recombiners.................................... 2.5* 2.8*
K3 Knowledge of the effect that a loss of the HRPS will have on the following:
K3.01 Hydrogen concentration in containment................... 3.3 4.0 K4 Knowledge of HRPS design feature (s) and/or interlock (s) which provide for the following:
K5 Knowledge of the following theoretical concepts as they apply to the HRPS:
K5.01 Explosive hydrogen concentration........................ 3.4 3.9 K5.02 Flammable hydrogen concentration........................ 3.4 3.9 K5.03 Sources of hydrogen within containment.................. 2.9 3.6*
K5.04 The selective removal of hydrogen....................... 2.6? 3.2?
K6 Knowledge of the applicable performance and design at-tributes of the following components:
K6.01 Hydrogen recombiners.................................... 2.6 3.1 I
l K/A catalog 3.6-23
SYSTEM: 028 Hydrogen Recombiner and Purge Control System (HRPS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 Al Ability to predict and/or monitor changes in parameter (to prevent exceeding design limits) associated with operating the HRPS controls including:
A1.01 Hydrogen concentration.................................. 3.4 3.8 A1.02 Containment pressure.................................... 3.4* 3.7*
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or
! operations:
A2.01 Hydrogen recombiner power setting, determined by using plant data book................................... 3.4* 3.6*
A2.02 LOCA condition and related concern over hydrogan........ 3.5 3.9 A2.03 The hydrogen / air concentration in excess of limit flame propagation or detonation with resulting equipment dam-age in containment...................................... 3.4 4.0 A3 Ability to monitor automatic operation of the HRPS, in-
! cluding:
A4 Ability to manually operate and/or monitor in the con-l trol room:
l A4.01 HRPS controls........................................... 4.0* 4.0*
l A4.02 Location and interpretation of containment pressure indications............................................. 3.7* 3.9 A4.03 Location and operation of hydrogen sampling and analy-sis of containment atmosphere, including alarms and indications............................................. 3.1 3.3 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.2* 3.4
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 2.5 3. 4
- 3. Knowledge of which events related to system operation / status should be reported. 2.6 3. 5*
- 4. Knowledge of system purpose and/or function. 3.5 3.7 K/A catalog 3.6-24
^'s SYSTEM: 028_ Hydrogen Recombiner and Purge Control System (HRPS)
(Q TASK MODE: 000 Generic Tasks as noted previously. l 1
IMPORTANCE SYSTEM GENERIC K/AS R0 SR0
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.9 3.9
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.8* 2.9*
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.1 3.6
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.4 4.1
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.2 3.4
- 10. Ability to recognize abnormal indications for system operating
. parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.2
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.0 4.1*
- 12. Ability to perform specific system and integrated plant opera-tions during: ,
Controlled plant load change................................... 2.2 2.1 Normal plant operations........................................ 2.2* 2.1 Plant heat and startup......................................... 2.4* 2.4 Plant shutdown and coo 1down.................................... 2.4* 2.3 K/A catalog 3.6-25 4
o IV)
SYSTEM: 103 Containment System TASK MODE: 000 Generic TASK: Perform cycling of manual containment isolation value surveillance Perform containment integrity verification Perform containment isolation valve test Perform containment leak test Perform trip valve timing checks and leak detection to verify isolation valve integrity IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems:
K1.01 CCS..................................................... 3.6 3.9 K1.02 Containment isolation / containment integrity............. 3.9 4.1*
K1.03 Shield building vent system............................. 3.1* 3.5*
K1.04 Electrical penetrations................................. 2.3 2.7 K1.05 Personnel access hatch and emergency access hatch....... 2.8* 3.0*
K1.06 Subsurface drain system................................. 2.4* 2.7*
hsV) K1.07 K1.08 Containment vacuum system...............................
SIS, including action of safety injection reset.........
3.5*
3.6 3.7*
3.8 K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the containmant system will have on the following:
K3.01 Loss of containment integrity under shutdown conditions. 3.3* 3.7*
K3.02 Loss of containment integrity under normal operations... 3.8 4.2 K3.03 Loss of containment integrity under refueling operaticns. 3.7 4.1 K4 Knowledge of containment system design feature (s) and/or interlock (s) which provide for the following:
K4.01 Vacuum breaker protection............................... 3.0* 3.7*
K4.02 Containment penetration cooling......................... 2.1 2.6 K4.03 Prevention of radiation streaming....................... 2.1 2.6*
K4.04 Personnel access hatch and emergency access hatch....... 2.5 3.2 K4.05 Containment construction................................ 1.9 2.2 K4.06 Containment isolation system............................ 3.1 3.7 K5 Knowledge of the following theoretical concepts as they apply to the containment system:
\
K/A catalog 3.6-27
SYSTEM: 103 Containment System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6 Knowledge of the applicable performance and design at-tributes of the following containment system components:
K6.01 Va1ves.................................................. 2.1* 2.3 K6.02 Controllers and positioners............................. 1.9 2.1*
K6.03 Pumps................................................... 1.5 1.6 K6.04 Heat exchangers and condensers....... .................. 1.5 1. 7 K6.05 Breakers, relays, and disconnects....................... 1.5 1.7 K6.06 Sensors and detectors................................... 1.9 2.1 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including:
A1.01 Containment pressure, temperature, and humidity......... 3.7 4.1 A2 Ability to (a) predict the impacts of the following '
malfunctions or operations on the containment system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Integrated leak rate test............................... 2.0* 2.6*
A2.02 Necessary plant conditions for work in conta *nment. . . . . . 2.2 3.2*
A2.03 Phase A and B isolation................................. 3.5* 3.8*
A2.04 Containment ovacuation (including reccgnition of the alarm)............................................. .... 3.5* 3.6*
A2.05 Emergency containment entry......... ................. . 2.9 3.9 A3 Ability to monitor automatic operation of the contain-ment system, including:
A3.01 Containment isolation................................... 3.9 4.2 A4 Ability to manually operate and/or monitor in the con-trol rc ....;
A4.01 Flow control, pressure control, and temperature control valves, including pneumatic valve controller. . . . . . . . . . . . 3.2* 3.3 O
K/A catalog 3.6-28
SYSTEM: 103 Containment System
/ T TASK MODE: 000 Generic
- ( )
Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A4.02 Excess letdown divert valves to reactor coolant drain tank.................................................... 2.1* 2.2*
A4.03 ESF slave relays........................................ 2.7* 2.7*
A4.04 Phase A and phase B resets.............................. 3.5* 3.5*
A4.05 PDP speed controller.................................... 2.4* 2.2*
A4.06 Operation of the containment personnel airlock door..... 2.7* 2.9*
A4.07 Use of the air lock rate test panel. . . . . . . . . . . . . . . . . . . . . 2.4* 2.5*
A4.08 Operation of refueling drain valves (for draining re-fueling canal to lower containment sump). . . . . . . . . . . . . . . . 1.9 2.2 A4.09 Containment vacuum system............................... 3.1* 3.7*
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.5 3.8
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.4 q 3. Knowledge of which events related to system operation / status should be reported. 2.7*
i (V 3
- 4. Knowledge of system purpose and/or function. 3.6*
3.5 3.8
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.8 3.1
- 7. Ability to locate, explain, and apply all limits and precau-tions. . 3.5 3.9
- 8. Ability to recognize indications' for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.5 4.2
- 9. Ability to verify system alarm setpoints and operate c'ontrols identified in the alarm response manual. 3.5 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.2 4.4 O
V K/A catalog 3.6-29
- = w *-' - =r --'- *'
SYSTEM: 103 Containment System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.3 4.4
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.5 2.7*
Normal plant operations........................................ 2.6* 2.7*
Plant heatup and startup....................................... 2.9 3.1 Plant shutdown and cooldown.................................... 2.7 2.9 O
l O
K/A catalog 3.6-30
m
/ \
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 069 Loss of Containment Integrity IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they '
apply to the loss of containment integrity emergency task:
EK1.01 Ef fect of pressure on leak rate. . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 3.1 EK2 Knowledge of the following components:
EK2.01 Va1ves.................................................. 2.4* 2.4 EK2.02 Sensors and detectors................................... 2.4* 2.4 EK2.03 Personnel access hatch and emergency access hatch....... 2.8* 2.9 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Guidance contained in E0P for loss of containment integ-rity.................................................... 3.8* 4.2 ABILITY
(~)
\_ /
EA1 Ability to operate and monitor the following:
EA1.01 Isolation valves, dampers, and electro pneumatic devices. 3.5 3.7 EA1.02 Blind flanges, as part of containment isolation......... 2.2 2.5 EA1.03 Fluid systems penetrating containment................... 2.8 3.0 EA2 Ability to determine or interpret:
EA2.01 Loss of containment integri ty. . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7 4.3 EA2.02 Verification of automatic and manual means of restoring :
integrity............................................... 3.9 4.4 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi- i cation of plant supervisors or off plant personnel. 2.8* 3.6
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.7 ,
1
- 5. Knowledge of the Technical Specification bases and definitions )
related to limiting conditions for operations and safety limits. 3.3 4.0 I l
(S 6. Ability to locate and operate components, using local controls 6
(outside the control room). 2.9 3.2 l
K/A catalog 3.6-31
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 069 Loss of Containment Integrity IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.4 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.4 3.4
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.5 3.9
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.5
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require imn:ediate operation of system components or controls. 4.1 4.3 O
O K/A catalog 3.6-32 l
l l
V e
s 2
E a_
M E
1 Electrical Systems and Malfunctions
.~ - -- . . - . .- - - .- . - _ -
J i
n AC Electrical Distribution System SYSTEM: -062 TASK MODE: 000 Generic
- TASK
- Line up the ac electrical distribution system Circuit breaker tests i Operate a static inverter l
^
' Equipment / bus testing for faults Monitor the ac-electrical distribution system i De-energize a motor control center (MCC) bus -
Perform transfer of power supply to 4kV unit service buses Restore a motor control center (MCC) bus to service Perform ac breaker lineup De-energize an engineering safeguards (4160V vital) bus
. Station blackout Restore an engineering safeguards bus to service Perform operation of circuit breakers and generator motor-operated disconnects p'
Backfeed unit auxiliary transformer from main transmission switchboard (main T/G links removed)
+
m
,,'1 Rack out a 480V/600V bus load breaker
, -Rack in a 480V/600V bus load breaker 1 <
Rack out an auxiliary bus breaker 4
[ Rack in an auxiliary bus breaker (4160V/6900V)
Transfer a vital.(120V) instrument power supply
, What if normal supply breaker failed to open?
, Perform ground isolatio~n.
i What if normal feedbreaker to the unit board does not close? '
i Isolate the power control breakers (PCBs)
What if the D/G does not start satisfactorily?
f IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-
, effect relationships between the ac distribution sys tem and the following systems:
2 K1.01 CO 2 deluge.............................................. 2.4 2.7*
K1. 02 ED/G.................................................... 4.1 4.4 Kl.03 DC distribution......................................... 3.5 4.0 l K1.04 O f f- s i te powe r s ou rce s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7 4.2 K2 ' ( Knowledge of bus power supplies to the following:
h K2iO1 Major system 1oads...................................... 3.3 3.4 K3 Knowledae of the effect that a loss of the ac distribu-j tion system will have on the following:
K/A catalog 3.7-1
1 SYSTEM: 062 AC Electrical Distribution System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K3.01 Major system loads...................................... 3.5 3.9 K3.02 ED/G.................................................... 4.1 4.4 K3.03 DC system............................................... 3.7 3.9 K4 Knowledge of ac distribution system design feature (s) and/or interlock (s) which provide for the following:
K4.01 Bus lockouts............................................ 2.6 3.2 K4.02 Ci rcui t breaker automatic trips. . . . . . . . . . . . . . . . . . . . . . . . . 2. 5 2.7 K4.03 Interlocks between automatic bus transfer and breakers.. 2.8* 3.1 K4.04 Protective relaying..................................... 2.2 2.9 K4.05 Paralleling of ac sources (synchroscope)................ 2.7* 3.2 K4.06 One-line diagram of 6.9kV distribution, including sources o f normal and alternative power. . . . . . . . . . . . . . . . . 2. 9* 3.3*
K4.07 One-line diagram of 4kV to 480V distribution, including sources of normal and alternative power................. 2.7 3.1 K4.08 One-line diagram of 230kV system, including sources of normal and alternative power............................ 2.3* 2.9*
K4.09 One-line diagram of 120V distribution, including sources of normal and alternative power......................... 2.4* 2.9*
K4.10 Uninterruptable ac power sources. . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.5 K5 Knowledge of the following theoretical concepts as they apply to the ac distribution system:
K5.01 Basic trans former theory (tap setting). . . . . . . . . . . . . . . . . . 1. 6 1.9 K5.02 Definition of open circuit...................... . . . . . . . 1. 6 2.0 K5.03 Principles involved with paralleling between two ac sources................................................. 2.4 2.6 K5.04 General principles of operation of a static inverter.... 1.9 2.5 K6 Knowledge of the applicable performance and design at-tributes of the following ac distribution system compo-nents:
K6.01 Motors........................................... ...... 1.7 1.8 K6.02 Breakers , relays , and di sconnects. . . . . . . . . . . . . . . . . . . . . . 1. 9 2.2 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including:
A1.01 Signi ficance of D/G load limits. . . . . . . . . . . . . . . . . . . . . . . . 3. 4 3.8 A1.02 Relationship between load and generator voltage......... 2.2 2.6 K/A catalog 3.7-2
SYSTEM: 062 AC Electrical Distribution System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A1.03 Effect on instrumentation and controls of switchin power supplies....................................g . . . . . . 2. 5 2. 8 A1.04 Ef fects on loads of energizing a bus. . . . . . . . . . . . . . . . . . . . 2.4 2.7 A1.05 Bus voltages............................................ 2.3 2.4 A1.06 Load currents........................................... 2.2 2.3 A1.07 Inverter outputs........................................ 2.4 2.6 l
l A2 Ability to (a) predict the impacts of the following mal-l functions or operations on the ac distribution system; l and (b) based on those predictions, use procedures to l correct, control, or mitigate the consequences of those l
malfunctions or operations:
A2.01 Types of loads that, if de-energized, would degrade or hinder plant operation.................................. 3.4 3.9 l A2.02 Causes and significance of grounds...................... 2.2 2.6 l A2.03 Consequences of improper sequencing when transferring to l or from an inverter..................................... 2.9 3.4 A2.04 Effect on plant of de-energizing a bus.................. 3.1 3.4*
A2.05 Methods for energizing a dead bus....................... 2.9 3.3*
A2.06 Keeping the safeguards buses electrically separate...... 3.4* 3.9 A2.07 Consequences of opening a disconnect under load......... 3.0* 3.4*
A2.08 Consequences of exceeding voltage limitations........... 2.7 3.0*
A2.09 Consequences of exceeding current limitations........... 2.7 3.0*
A2.10 Effects of switching power supplies on instruments and controls................................................ 3.0 3.3 A2.11 Aligning standby equipment with correct emergency power source (0/G)............................................ 3.7 4.1 A2.12 Restoration of power to a system with a fault on it..... 3.2 3.6 A2.13 Ide,tification and ranking of the most probable cause of grounds, referring to electrical distribution diagrams.. 2.2* 2.6*
A2.14 Parformance of ground isolation procedures: determina-tion of their effect on interface systems............... 2.3* 2.9*
A2.15 Consequence of paralleling out-of phase / mismatch in vo1ts................................................... 2.8 3.2 A2.16 Degraded system voltages.............................. . 2.5 2.9
- 43 Ability to monitor automatic operation of se ac distri-bution system, including:
l A3.01 Vital ac bus amperage.......................... ...... 3.0 3.1 A3.02 Main T/G exciter current indicator...................... 2.4* 2.2*
I A3.03 Adequate transformer / inverter operation . . . . . . . . . . . . . . . . 2. 3* 2.3 A3.04 Operation of inverter (e.g., precharging synchronizing light, static transfer)......... ................ .... 2.7 2.9 A3.05 Safety-related indic.ators and control s. . . . . . . . . . . . . . . . . . 3. 5 3.6 K/A catalog 3./ 3
SYSTEM: 062 AC Electrical Distribution System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 All breakers (including available switchyard)........... 3.3 3.1 A4.02 Remote racking in and out of breakers................. . 2.5 2.8 A4.03 Synchroscope, including an understanding of running and incoming voltages....... ........... .......... .. .... 2.8 2.9 A4.04 Local operati on o f brea kers. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 2.7 A4.05 Remote preparation of breakers for testing.............. 2.1 2.2 A4.06 Remote removal and re-installation of control power fuses..................................................2.3 2.5 A4.07 Synchronizing and paralleling of different ac supplies.. 3.1* 3.1*
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.1 3.5
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.5
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.6*
- 4. Knowledge of system purpose and/or function. 3.4 3.7
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.0 4.0
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.8 3.4
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.2 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.4 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.4 K/A catalog 3.7-4
SYSTEM: 062 AC Electrical Distribution System
.I TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.2 4.3
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.8 3.1 Normal plant operations........................................ 2.8 3.1
! -Plant heatup and startup....................................... 2.9 3.3 Plant shutdown and coo 1down.................................... 2.9 3.3
)
i b
K/A catalog 3.7-5
M k
SYSTEM: 063 DC Electrical Distribution System TASK MODE: -000 Generic TASK: Start up and shift a vital battery charger Monitor the dc electrical distribution system Monitor the dc electrical system for grounds Energize dc switchboards De-energize dc switchboards Energize de equipment De energize dc equipment Secure a battery charger IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the dc electrical system and the following systems:
K1.01 Ground detection system................................. 2.4 2.9 K1.02 AC electrical system.................................... 2.7 3.2 g ~'s K1.03 Battery charger and battery............................. 2.9 3.5 Kl.04 2.2 2.7 (v) Battery ventilation system..............................
K2 Knowledge of bus power supplies to the following:
K2.01 Major dc 1oads.......................................... 2.9* 3.1*
K2.02 Battery room ventilation................................ 2.0 2. 2 K3 Knowledge of the effect that a loss of the dc electrical system will have on the following:
K3.01 ED/G.................................................... 3.7* 4.1 K3.02 Components using dc control power....................... 3.5 3.7 K4 Knowledge of dc electrical system design feature (s) and/
or interlock (s) which provide for the following:
K4.01 Manual / automatic transfers of control. . . . . . . . . . . . . . . . . . . 2.7 3.0*
K4.02 Breaker interlocks, permissives, bypasses and cross-ties. 2.9* 3.2*
K4.03 Effect of jumpering out ce11s........................... 2.1 2.4 K4.04 Trips................................................... 2.6? 2.9?
i K5 Knowledge of the following theoretical concepts as they 1 apply to the dc electrical system:
~3 K5.01 Knowledge of basic dc electrical theory................. 1.9 2.1
['s_/ 3 K5.02 Hydrogen generation during battery charging............. 2.2 2.6* I K/A catalog 3.7-7
l SYSTEM: 063 DC Electrical Distribution System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6 Knowledge of the applicable performance and design at-tributes of the following dc electrical system compo-nents:
K6.01 Motors......... .. ...... ................... ... . . . 1.8 1.7 K6.02 Breakers, relays and disconnects.. .... . ..... . .. . 1.9 2.1 K6.03 Test instruments........ . ....... ... ..... .... 1.5 1.5 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the dc electrical system controls including:
A1.01 Battery capacity as it is affected by discharge rate.... 2.5 3.3 A1.02 Battery capacity, given ICV values......... .... .... 2.2 2.7*
A2 Ability to (a) predict the impacts of the following mal-functions or operations on the dc electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Grounds........ ..... ................ .............. . 2.5 3.2*
A2.02 Loss of ventilation du ing battery charging. . . . . . . . . . . . . 2.3 3.1 A3 Ability to monitor automatic operation of the dc elec-trical system, including:
A3.01 Meters, annunciators, dials, recorders, and indicating lights... ..... ... ..... . . .. .... ... ........... 2.7 3.1 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Major breakers and control power fuses.......... ...... 2.8* 3.1 A4.02 Battery voltage indicator. ...... ............... ... . 2.8* 2.9 A4.03 Battery discharge rate......... ......... ..... . ...... 3.0* 3.1 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.3 3.7
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.4 K/A catalog 3.7-8
n SYSTEM: 063 DC Electrical Distribution System-
-( '. TASK MODE: 000 Generic
\
Tasks as noted previously.
IMPORTANCE
-SYSTEM GENERIC K/As R0 SRO
. 3. Knowledge of which events related to system operation / status should be reported. 2.6* 3.4
- 4. Knowledge of system purpose and/or function. 3.5 3.9
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.0 3.9
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9* 3.1-
- 7. Ability to locate, explain, and apply all lircits and precau-tions. 3.2 3.7
- 8. Ability.to recognize-indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.2 4.1 A
- 9. Ability to verify system alarm setpoints and operate controls (V) identitied in the alarm response manual. 3.4 3.6
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.3
- 11. Ability to perform those actions, without reference to proce-dure,.for all casualties which require immediate operation of system components or controls. 4.0 4.4
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.4* 2.4 No rmal pl a n t o p e ra ti o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5
- 2. 5 Plant heatup and startup....................................... 2.6* 2.6 Plant shutdown and cooldown.................................... 2.5* 2.5
\
L K/A catalog 3.7-9 l
lA)
V SYSTEM: 064 Emergency Diesel Generator (ED/G) System TASK MODE: 000 Generic TASK: Perform a lineup of the ED/G system Start an ED/G Load the ED/G Perform ED/G load tests Monitor the ED/G Perform ED/G inoperative test (loss of reserve power)
Unload the ED/G Shut down the ED/G Operate the diesel-starting air compressor Restart an ED/G with an automatic start signal present IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the phy!;ical connections and/or cause-
-effect relationships'between the ED/G system and thefollowingsystemg:
K1.01 AC distribution system.................................. 4.1 4.4 O K1.02 D/G cooling water system................................ 3.1 3.6*
Q Kl.03 K1.04 Diesel fuel oil supply system...........................
DC distribution system..................................
3.6 3.6 4.0 3.9 Kl.05 Starting air system..................................... 3.4 3.9 K2 Knowledge of bus power supplies to the following:
K2.01 Air compressor.......................................... 2.7* 3.1 K2.02 Fuel oil pumps.......................................... 2.8* 3.1 K2.03 Control power........................................... 3.2* 3.6 !
K3 Knowledge of the effect that a loss of the ED/G system I will have on the following:
K3.01 Systems controlled by automatic loader.................. 3.8* 4.1 K3.02 ESFAS controlled or actuated systems.................... 4.2 4.4 4
K3.03 ED/G (manual loads)..................................... 3.6 3.9*
K4 Knowledge of ED/G system design feature (s) and/or inter-lock (s) which provide for the following:
K4.01 Trips while loading the ED/G (frequency, voltage, speed). 3.8 4.1 K4.02 Trips for ED/G while operating (normal or emergency).... 3.9 4.2 K4.03 Governor valve operation................................ 2.5 3.0 K4.04 O v e r l o a d ra t i n g s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.7 (O K4.05 Incomplete-start relay.................................. 2.8 3.2
-() K4.06 K4.07 Speed droop contro1.....................................
Field flashing..........................................
2.2 2.2 2.7 2.8 i
K/A catalog 3.7-11
SYSTEM: 064 Emergency Diesel Generator (ED/G) System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K4.08 ED/G fuel isolation valves......... . . .............. 2.9* 3.5 K4.09 Field on ED/G......... ............. .. ......... ..... 2.4 3.0 K4.10 Automatic load sequencer: blackout....... . ... . ... . 3.5 4.0 K4.11 Automatic load sequencer: safeguards....... .. . .... 3.5 4.0 K5 Knowledge of the following theoretical concepts as they apply to the ED/G system:
K5.01 Definition of frequency and synchronous frequency. .... 2.0 2.2 K5.02 Reactive power control (using set voltage)....... . . . . 1. 9 2.4*
K5.03 Real power control (using set frequency).. ......... .. 1.9 2.4*
K6 Knowledge of the applicable performance and design at-tributes of the following ED/G system components:
K6.01 Valves..... ...... .................. ............ . . . . 2.1 2.2 K6.02 Sensors and detectors..... ......... ... ...... . .. .. 2.1 2.3 K6.03 Controllers and positioners.... ....... . ..... ........ 2.1 2.3 K6.04 Pumps.... ........ .. ... . . ..... ....... ........ 2.1 2.2 K6.05 Motors....... ......... ............ . ........... .. 2.1 2.1 K6.06 Breakers, relays, and disconnects......... . ........ 2.2* 2.5*
K6.07 Air receivers................. . .. ..... . .... ....... 2.7 2.9 K6.08 Fuel oil storage tanks.. ..... . .. . ...... .......... 3.2 3.3 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including:
A1.01 ED/G lube oil temperature and pressure......... ........ 3.0 3.1 A1.02 Fuel consumption rate with load. .. . .. . ... .. ..... 2.5 2.8 A1.03 Operating voltages, currents,and temperatures. . .. .... 3.2 3.3 A1.04 Crankcase temperature and pressure..... .... .. ... ... 2.8 2.9 A1.05 D/G room temperature. ....... ........... ....... . ... 2.5 2.5 A1.06 Cylinder temperature differential.. ... ........... .... 2.3 2.5 A1.07 Maintaining minimum load on ED/G (to prevent reverse power)........... ... ... ............ ......... ... . . 2.9 2.9 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunc-tions or operations:
K/A catalog 3.7-12
SYSTEM: 064 Emergency Diesel Generator (ED/G) System I
.vO)
( TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2.01 Failure modes of water, oil, and air valves............. 3.1* 3.3 A2.02 Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level, temperatures........ 2.7 2.9 A2.03 Parallel operation of ED/Gs............................. 3.1 3.1 A2.04 Unloading prior to securing an ED/G............... ..... 2.7 3.0 A2.05 Loading the ED/G........................................ 3.1 3.2*
A2.06 Operating unloaded, lightly loaded, and highly loaded time limit.............................................. 2.9 3.3 A2.07 Consequences of operating under/over-excited. . . . . . . . . . . . 2. 5 2.7 A2.08 Consequences of opening / closing breaker between buses (VARS , out-o f phase , vol tage) . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7 3.1 A2.09 Synchronization of the ED/G with other electric power supplies................................................ 3.1 3.3 A2.10 Unloading (reduction of generated power) in steps over a period of time........................................ 2.4 2.9 A2.11 Conditions (minimum load) required for unloading an ED/G. 2.6 2.9 A2.12 Los s of ai r-cool i ng f ans . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8* 3.1*
A2.13 Consequences of opening auxiliary feeder bus (ED/G sub supply)................................................. 2.6* 2.8*
Q A2.14 Effects (verification) of stopping ED/G under load on isolated bus............................................ 2.7 2.9 A2.15 Water buildup in cyclinders............................. 2.6 3.1 A2.16 Loss of offsite power during full-load testing of ED/G.. 3.3 3.7 A3 Ability to monitor automatic operation of the ED/G sys-tem, including:
A3.01 Automatic start of compressor and ED/G.................. 4.1 4.0 A3.02 Minimum time for load pickup............................ 3.4 3.7 A3.03 Indicating lights, meters, and recorders................ 3.4 3.3 A3.04 Number of starts available with an air compressor....... 3.1 3.5 A3.05 Operation of the governor control of frequency and voltage control in parallel operation................... 2.8 2.9 A3.06 Start and stop............................. ............ 3.3 3.4 A3.07 Load seq'uencing......................................... 3.6* 3.7*
A3.08 Consequences of automatic transfer to automatic posi-tion a f te'r the ED/G i s stopped. . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7? 4.0 A3.09 Functions (modes) of automatic transfer switch (to a starttlp bank)............,.............................. 4.0* 4.0 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Local and remote operation of the ED/G.................. 4.0 4.3 A4.02 Adjustment of exciter voltage (using voltage control switch).................................................3.3 3.4 K/A catalog 3.7-13
SYSTEM: 064 Emergency Diesel Generator (ED/G) System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A4.03 Synchroscope............................................ 3.2 3.3 A4.04 Remote operation of the air compressor switch (differ-ent modes)........................................ ..... 3.2* 3.2 A4.0S fransfer of ED/G control between manual and automatic... 3.1 3.2 A4.06 Manual start, loading, and stopping of the ED/G......... 3.9 3.9 A4.07 Transfer ED/G (with load) to grid....................... 3.4 3.4 O
l l
l l
l l
1 1
O K/A catalog 3.7-14
SYSTEM: 064 Emergency Diesel Generator (ED/G) System
( ) TASK H0DE: 050 What If/ Abnormal
/
TASK: What if emergency loads are not shed when time sequence starts during emergency diesel inoperative test?
What if ED/G breaker closed at other than 12:00 position on synchroscope?
What if ED/G load is not reduced?
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the ED/G system and the following systems:
K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the ED/G system will have on the following:
K4 Knowledge of ED/G System design feature (s) and/or inter-lock (s) which provide for the following:
K5 Knowledge of the following theoretical concepts as they apply to the ED/G system:
O Knowledge of the applicable performance and design at-(), K6 f
tributes of the following ED/G system components:
K6.01 Valves.................................................. 2.4 2.4*
K6.02 Sensors and detectors................................... 2.4* 2.4*
K6.03 Controllers and positioners............................. 2.4* 2.4*
K6.04 Pumps.................................. ................ 2.2 2.3 K6.05 Motors.................................................. 2.1 2.1 K6.06 Breakers, relays, and disconnects....................... 2.3* 2.4* l l
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including:
A1.01 Maintaining minimum load on ED/G (to prevent reverse power).................................................. 3.1 3.4 A2 Ability to (a) predict the impacts of the following mal-functions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Consequences of not shedding loads during nonoperabil-
'V i ty t e s t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3* 2.6*
K/A catalog 3.7-15
SYSTEM: 064 Emergency Diesel Generator (ED/G) System TASK MODE: 050 What If/ Abnormal Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2.02 Consequences of premature opening of breaker under load. 2.6* 2.7 A2.03 Consequences of high VARS on ED/G integrity............. 2.5 2.7 A2.04 Identification and analysis of loads not shed during test.................................................... 2.4* 2.7*
A2.05 Significance and interpretation of opening of ring bus during test..................... ......... .. .......... 2.6* 2.9*
A2.06 Potential automatic safety sequences (water /C0 2)and electrical damage (loose wires)....................... . 2.4 2.8*
A3 Ability to monitor automatic operation of the ED/G sys-tem, including:
A3.01 Function of ED/G megawatt load controller.. ............ 2.8 2.8*
A3.02 Need for setting offsite power breaker to automatic..... 3.1* 2.9*
A3.03 Purpose of automatic load sequencer.. ................ 3.3* 3.5 A3.04 Rpm controller / megawatt load control (breaker-open/
breaker-closed effects)............................... . 3.0* 2.9 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Ope n i ng o f the ri ng bus . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2
- 3.2*
A4.02 Establishing power fro.m the ring bus (to relieve ED/G).. 3.2* 3.3*
A4.03 Need for, and consequences of, manually shedding (loads) safeguards bus................................. ........ 3.3 3.4 A4.04 The setting of droop voltage to zero................ .... 2.2 2.4 A4.05 Synchroscope....... ................. .................. 2.7* 2.6 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.6 4.0
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.5
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.7*
- 4. Knowledge of system purpose and/or function. 3.7 4.0
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 4.1 K/A catalog 3.7-16
l-l SYSTEM: 064 Emergency Diesel Generator (ED/G) System
. TASK MODE: 050 What If/ Abnormal i- Tasks as noted previously.
l IMPORTANCE SYSTEM GENERIC K/As R0 SR0 Ability to locate and operate components, using local controls
~
t 6.
l- (outside the control room). 3.5* 3.6 i 7. Ability to locate, explain, and apply all limits and precau-tions. 3.6 4.0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi- '
cations. 3.4 4.4
- 9. Ability to verify system alarm setpoints.and operate controls identified in the alarm response manual. 3.7 4.0
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.4 4.7
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of
\ system components or controls. 4.4 4.6 ;
- 12. Ability to perform specific system and integrated plant opera-tions during: '
Controlled plant load change................................... 2.6* 2.7 No rmal pl ant ope rati ons . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7* 2.7 Plant heatup and startup....................................... 2.7 2.8 Plant shutdown and cooldown.................................... 2.6 2. 6 I
i l
k, s
K/A catalog 3.7-17
A f I U
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 055 Loss of Offsite and Onsite Power (Station Blackout)
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the loss of offsite and onsite power emergency task:
EK1.01 Effect of battery discharge rates on capacity........... 3.3 3.7 EKl.02 Natural circulation cooling............................. 4.1 4.4 EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 2.0 2.2 EK2.02 Sensors, detectors and indicators....................... 2.1* 2.2*
EK2.03 Controllers and positioners............................. 1.9 2.1 EK2.04 Pumps................................................... 1.9 2.1 EK2.05 Motors.................................................. 2.0 2.2 EK2.06 Heat exchangers and condensers.......................... 1.7 2.1 EK2.07 Breakers, relays, and disconnects....................... 2.2* 2.4*
Q EK3 Knowledge of the bases or reasons for the following:
EK3.01 Length of time for which battery capacity is designed... 2.7 3.4 EK3.02 Actions contained in E0P for loss of offsite and onsite power................................................... 4.3 4.6 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 In-core thermocouple temperatures....................... 3.7 3.9 EA1.02 Manual ED/G start....................................... 4.3 4.4 EA1.03 Manual MT jacking....................................... 1.9* 1.9*
EA1.04 Reduction of loads on the battery. . . . . . . . . . . . . . . . . . . . . . . 3. 5 3.9 EA1.05 Battery, when approaching fully discharged.............. 3.3 3.6 EA1.06 Restoration of power with one ED/G...................... 4.1 4.5 EA1.07 Restoration of power from offsite....................... 4.3 4.5 EA2 Ability to determine or interpret:
EA2.01 Existing valve positioning on a loss of instrument air system.................................................. 3.4 3.7 l EA2.02 RCS core cooling through natural circulation cooling to 4.4 4.6 S/G cooling.............................................
i EA2.03 Actions necessary to restore power...................... 3.9 4.7 i
\") EA2.04 Instruments and controls operable with only dc battery power available......................................... 3.7 4.1 K/A catalog 3.7-19
., . . _ , , - - . _ . _ . ._ _~ _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - . . . . . . _ _ .
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 055 Loss of Offsite and Onsite Power (Station Blackout)
IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.05 When battery is approaching fully discharged. . . ... .... 3.4 3.7 EA2.06 Faults and lockouts that must be cleared prior to re-energizing buses.. ..... . .... ........... ........... 3.7 4.1 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 3.0* 3. 7
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.8
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 3.9
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.4 3.9
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.5 4.0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.5 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.7 3.9
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.3 4.5
- 11. Ability to perform t.ose actions, without reference to proce-dure, for all casua' ties which require immediate operation of system components or ontrols. 4.3 4.4 O
K/A catalog 3.7-20
p SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 056 Loss of Offsite Power IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the loss of offsite and onsite power emergency task:
EK1.01 Principle of cooling by natural convection.............. 3.7 4.2 EK1.02 Definition of terms: volts, watts, amp, degrees F, %,
p s i g , i nche s o f me rc u ry , gpm. . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.1 EKl.03 Definition of subcooling: use of steam tables to deter-mineit.................................................3.1* 3.4*
EK1.04 Definition of saturation conditions, implication for t h e sy s t em s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1* 3.2*
EK2 Knowledge of the following components:
EK2.01 Valves.................................................. 1.8 1.8 EK2.02 '
Sensors, detectors, and indicators...................... 2.0* 1. 9 EK2.03 Controllers and pos itioners. . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 1. 9 EK2.04 Pumps........................... ....................... 1.7 1.7 EK2.05 Motors.................................................. 1.7 1. 7 EK2.06 Heat exchangers and condensers. . . . . . . . . . . . . . . . . . . . . . . . . . 1. 6 1.7
[ EK2.07 Demineralizers and ion exchangers....................... 1.6 1.6
(~ EK2.08 Breakers, relays, and disconnects....................... 2.1* 2.1 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Order and time to initiation of power for the load sequencer............................................... 3.5 3.9 EK3.02 Actions contained in E0P for loss of offsite power.. . ... 4.4 4.7 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Power relief controllers to maintain no-load T-ave...... 4.0* 3.8*
EA1.02 ESF bus synchronization select switch to close bus tie breakers................................................4.0* 3.9 EA1.03 Adjustment of ED/G load by selectively energizing PZR backup heaters.......................................... 3.2* 3.3*
EA1.04' Adjustment of speed of ED/G to maintain frequency and voltage levels.......................................... 3.2 3.1 EA1.05 ' Initiation (manual) of safety injection process......... 3.8 3.9 EA1.06 Safety injection pump................................... 3.6* 3.6*
EA1.07 S e rv i c e wa te r p ump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2* 3.2*
EA1.08 HVAC chill water pump and unit.......................... 2.5* 2. 5 EA1.09 C CW p um p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3 3.3 l EA1.10 Auxiliary / emergency feedwater pump (motor driven). . . . . . . 4.3 4.3 EA1.11 H P I sy s t e m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.7* 3.7
% EA1.12 Reactor building cooling unit........................... 3.2 3.3 K/A catalog 3.7-21
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 056 Loss of Offsite Power IMPORTANCE K/A NO. ABILITY R0 SR0 EA1.13 Fuel handling building exhaust fan.. . . .............. 2.2 2.2 EA1.14 Relay room cooling unit...................... .. ....... 2.3* 2.3*
EA1.15 Service rater booster pump.......... ............. ... . 2.7* 2.9*
EA1.16 ESF switch gear room cooling unit... . ................ 2.5 2.5 EA1.17 Service water building normal ventilation supply fan.... 2.3* 2.4*
EA1.18 Control room normal ventilation supply fan.. .. . .. .. 3.2 3.2 EA1.19 Battery room ventilation exhaust fan.. ......... .. . 2.4* 2.4*
EA1.20 Speed switch room ventilation fan........ ....... ..... 3.0* 3.0*
EA1.21 Reset of the ESF load sequencers... ... ........ ..... . 3.3* 3.3*
EA1.22 Main turbine lube oil system....... ....... . . . . . . . . . 1. 8 1.9 EA1.23 Turbine turning gear (manually). . . . . . . . . . . . . . . . . . . . . . . 1. 9
- 1. 9 EA1.24 Plant computer, to call up in-core temperature moni-toring group............... ..... .. ........... ....... 2.9* 3.0*
EA1.25 Main steam supply valve control switch. ........... ... 2.9* 2.9*
EA1.26 Circuit breakers.......................... .. .... .... 2.5* 2.6 EA1.27 Normal letdown isolation valve................ . ....... 2.3* 2.3 EA1.28 SWS flow control valve for the CCW cooler to control CCW outlet temperature........................ .........3.1* 3.1*
EA1.29 CCW heat exchanger temperature control valves........... 2.7 2.7 EA1.30 AFW tlow control valve operating switches............... 3.5 3.6 EA1.31 PZR heater group control switches..... ................. 3.3 3.3 EA1.32 PZR PORV hand switch..... .. ........................... 3.4* 3.4 EA1.33 PORV block valve control switch......................... 3.3 3.5 EA1.34 Normal makeup flow contro11er..................... ..... 2.7 2.8 EA1.35 Control switches for the reactor makeup water pump. . . . . . 2.3* 2.3*
EA1.36 Gland seal and condenser air removal systems............ 1.8 1.8 EA1.37 Instrument air.......................................... 3.4 3.5 EA2 Ability to determine or interpret:
EA2.01 PORV controller indicator and setpoint............. ... 3.3* 3.4 EA2.02 ESF load sequencer status lights....................... 3.5* 3.6*
EA2.03 Operational status of safety injection pump............. 3.8 3.9 EA2.04 Operational status of service water pump................ 3.5 3. 7 EA2.05 Operational status of HVAC chill water pump............. 2.6* 2.8*
EA2.06 Operational status of CCW pump.......................... 3.5 3.6 EA2.07 Operational status of emergency feedwater pump (motor driven)................................... ... .... 4.2 4.3 EA2.08 Operatio",1 status of fuel-handling building exhaun far . .. ........................................... 2.2 2.3*
EA2.09 Opeiutional status of reactor building cooling unit..... 2.7 2.9 EA2.10 Operational status of relay room cooling unit........... 2.0* 2.2*
EA2.11 Operational status of service water booster pump........ 2.9* 2.9*
EA2.12 Operational status of ESF switch gear room cooling unit. 2.4* 2.6*
EA2.13 Operational status of ventilation supply fans for the service water building, control room and battery room... 2.5 2.6 EA2.14 Operational status of ED/Gs (A and B)......... ......... 4.4 4.6 K/A catalog 3.7-22
- Q SYSTEM: 000 Emergency Plant Evolutions g EPE MODE: 056 Loss of Offsite Power IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.15 Operational status of main generator emergency bearing oil pumps............................................... 1.9 2.1 EA2.16 Operational status of feedwater pump turbine emergency oil pumps............................................. .9* 2.l*
EA2.17 Operational status of PZR backup heaters.............. 4 3.6 EA2.18 Reactor coolant temperature, pressure, and PZR level recorders............................................... 3.8 4.0 EA2.19 T-cold and T-hot indicators (wide range)................ 4.0 4.2 EA2.20 AFW flow indicator...................................... 3.9 4.1 EA2.21 ED/G frequency and voltage indicators................... 3.6 3.8 EA2.22 Emergency lube oil pump indicators and low pressure alarms on ED/G.......................................... 3.4 3.6 EA2.23 Turbine trip-reactor button and indicator............... 3.7 3.9 EA2.24 CCW pump ammeter, flowmeter ar.d run indicator........... 3.0 3.1 EA2.25 Emergency feedwater ammeter and flowmeter............... 3.9 4.0 EA2.26 Reactor building cooling unit ammeter and run indicator. 2.2* 2.4*
EA2.27 Fuel-handling building exhaust fan indicator............ 1.8* 1. 9
- EA2.28 Auxiliary building gas treatment indicator.............. 2.2* 2.6*
EA2.29 Service water booster pump ammeter and flowmeter........ 3.0* 3.2*
EA2.30 Switch gear room cooling unit run indicator............. 2.0 2.2
/ EA2.31 Ventilation supply fan and run indicators for the ser-( vice water building, control room and battery room...... 2.1 2.2 EA2.32 Transient trend of coolant temperature toward no-load T-ave................................................... 4.3 4.3 EA2.33 ESF channels, A and B breaker-trip alarms, indicators and bus voltage indicators.............................. 3.6? 3.7?
EA2.34 hd bottom lights....................................... 4.1 4.2 EA2.35 12 actor trip a1 arm...................................... 4.1 4.1 EA2.36 Turbine stop valve indicator......................*...... 3.9 4.1 EA2.37 ED/G indicators for the following: voltage, frequency, load, load-status, and closure of bus tie breakers...... 3.7* 3.8 EA2.38 Load sequencer status lights............................ 3.7* 3.8
- EA2.39 Safety injection pump ammeter and flowmeter............. 3.5* 3.6 EA2.40 Service water pump ammeter and flowmeter................ 3.3 3.4 EA2.41 HVAC chill water pump run and alarm indicators.......... 2.3* 2.3*
- EA2.42 Occurrence of a reactor trip............................ 4.1 4.1 EA2.43 Occurrence of a turbine trip............................ 3.9 4.1 l
EA2.44 Indications of loss of offsite power.................... 4.3 4.5 EA2.45 Indicators to assess status of ESF breakers (tripped /
not-tripped) and validity of alarms (false /not-false). . . 3.6* 3.9 i EA2.46 That the ED/Gs have started automatically and that the l bus tie breakers are closed............................. 4.2 4.4 j EA2.47 Proper operation of the ED/G load sequencer............. 3.8 3.9 j EA2.48 Reactor coolant temperature, pressure, and PZR level following a power outage transient...................... 4.3 4.4 EA2.49 Nonessential equipment to be secured to avoid overload i of ED/Gs................................................ 3.0 3.4 K/A catalog 3.7-23
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 056 Loss of Offsite Power IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.50 That load and VAR limits, alarm setpoints, frequency and voltage limits for ED/Gs are not being exceeded..... 2.8* 3.1 EA2.51 AT, (core, heat exchanger, etc.)... .. ....... ....... 3.3* 3.4*
EA2.52 PZR level required for a given power level.. . . . .. 2.6* 2.8*
EA2.53 Status of emergency bus under voltage relays............ 2.9 3.2 EA2.54 Breaker position (remote and local)...... ......... . .. 2.9 3.0 EA2.55 Subcooled margin monitors.. . .. . .. . . . 3.8 3.9 EA2.56 RCS T-ave.. . .. ............ .......... ....... ... 3.6* 3.7 EA2.57 RCS hot-leg and cold-leg temperatures... ... . .. .. . 3.9 4.1 EA2.58 Air compressors (indicating lights).... .. .. . ........ 2.3 2.6*
EA2.59 Gland seal pressure gauge.... ........... . ... .. .... 1.5 1. 6 EA2.60 MSIV open................. ...... ........... .... .... 2.7* 2.9*
EA2.61 Condensate pump............... ............. ..... . 1. 6 1. 7 EA2.62 B rea ke r fo r feedwa te r pumps. . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7 1.9*
EA2.63 Feedwater heater drain pump breaker trip........ ...... . 1. 5 1. 5 EA2.64 Circulating water pump switch........................... 1.6 1. 7 EA2.65 Screen wash pump............. .........................1.5 1. 7 EA2.66 CVCS charging f10w................................... . 3.2 3.4 EA2.67 Seal injection flow (for the RCPs).................. ... 2.9 3.1 EA2.68 CVCS letdown flow. ...... ........ .... . ............. 2.7 2.9 EA2.69 Valve position............ ........... .............. .. 2.3* 2.5" EA2.70 Reactor building CCW temperature... ....... ............ 2.1 2.2 EA2.71 Turbine service water heat exchange...................... 1. 7 1. 7 EA2.72 Auxiliary feed flow............................. ....... 4.1 4.3 EA2.73 PZR heater on/off.. . ............................. .. 3.5 3.6 EA2.74 PORV position........ ................................. 3.6 3.7 EA2.75 CVCS makeup.. .... .................................... . 3.0 3.2 EA2.76 Reactor makeup water pump (running).......... .......... 2.6 2.6 EA2.77 Auxiliary feed pump (running)................. ......... 4.1 4.4 EA2.78 Bus voltmeters..... ............................... .... 2.7 3.0 EA2.79 Turbine turning gear status light............. .. .. . . . 1. 7 1. 7 EA2.80 Inpu t/ou tput vol tage al arm. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1* 2.2*
EA2.81 S/G level meter scale and pressure gauge................ 3.7 3.8 EA2.82 Temperatures displayed on plant computer CRT monitor.... 2.6 2.7 EA2.83 Instrument air pressure gauge........................... 2.7 3.0 EA2.84 Turbine bearing pressure meter.......................... 1.6 1. 8 EA2.85 Condenser vacuum gauge readings.... ..... .... . ....... 1.8* 1.9*
EA2.86 Main steam pressure meter scale.. ...................... 2.7* 2.7*
EA2.87 Circulation water pump ammeter readings......... ....... 1.6 1. 6 EA2.88 Necessary S/G water level for natural circulation....... 4.1 4.2 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifica-tion of plant supervisors or off plant personnel. 2.8* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.7 K/A catalog 3.7-24
r3 SYSTEM: 000 Emergency Plant Evolutions
! EPE MODE: 056 Loss of Offsite Power d'
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 5. Knowledge of the Technical Spcification bases and definitions related to limiting conditions for operations and safety limits. 3.2 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.5 3.7
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.7 4.1
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.6 4.4
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 4.0 4.1
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.5 4.6 x ) 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4.6 m
I \
l O K/A catalog 3.7-25
~
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 057 Loss of Vital AC Electrical Instrument Bus IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the loss of vital ac electrical instrument bus emergency task:
EK2 Knowledge of the following components:
EK2.01 Valves..................................... ............ 1.9 2.1 EK2.02 Sensors, detectors, and indicators................. .... 2.2* 2. 3
- EK2.03 Controllers and positioners............................. 2.2* 2. 4 EK2.04 Pumps....... ........................................... 2.0 1.9 EK2.05 Breakers, relays and disconnects........... ............ 2.2* 2.3 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Actions contained in E0P for loss of vital ac electri-cal instrument bus.............................. ....... 4.1 4.4 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Manual inverter swapping................................ 3.7* 3.7 EA1.02 Manual control of PZR leve1............................. 3.8 3.7 EA1.03 Feedwater pump speed to control pressure and level in S/G............... ..................................... 3.6* 3.6 EA1.04 RWST and VCT va1ves.............................. ...... 3.5 3.6 EA1.05 Backup instrument indications........................... 3.2 3.4 EA1.06 Manual control of components for which automatic control is lost..................................... ........... 3.5 3.5 EA2 Ability to determine or interpret:
EA2.01 Safety injection tank pressure and level indicators..... 3.7 3.8 EA2.02 Core flood tank pressure and level indicators........... 3.7* 3.8*
EA2.03 RPS panel alarm annunciators and trip indicators........ 3.7 3.9 EA2.04 ESF system panel alarm annunciators and channel status indicators.............................................. 3.7 4.0 EA2.05 S/G pressure and level meters........................... 3.5 3.8 EA2.06 AC instrument bus alarms for the inverter and alternate power source............................................ 3.2 3.7 EA2.07 Valve indicator of charging pump suction valve from RWST. 3.3 3.5 EA2.08 Reactor power digital display and remote flux meter..... 3.4* 3.5*
EA2.09 T-ave. and T-ref. chart recorder............ ........... 3.1* 3.4*
EA2.10 Turbine load limiter control............................ 2.3 2.5 EA2.11 Main feed pump running indicator and controller......... 2.9* 3.0*
EA2.12 PZR level controller, instrumentation, and heater indi-cations................................................. 3.5 3.7 EA2.13 VCT level and pressure indicators and recorders......... 3.0 3.4 K/A catalog 3.7-26
f3 SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 057 Loss of Vital AC Electrical Instrument Bus (G )
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO
~EA2.14 That substitute power sources have come on line on a loss of initial ac...................................... 3.2 3.6 EA2.15 That a loss of ac has occurred.......................... 3.8 4.1 EA2.16 Normal and abnormal PZR level for various modes of plant operation......................................... 3.0 3.1 EA2.17 System and component status, using local or remote controls................................................ 3.1 3.4 EA2.18 The indicator, valve, breaker, or damper position which w i l l occ u r o n a l o s s o f powe r. . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.1 EA2.19 The plant automatic actions that will occur on the loss of a vital ac electrical instrument bus................. 4.0 4.3 EA2.20 Interlocks in effect on loss of ac vital electrical instrument bus that must be bypassed to restore normal equipment operation..................................... 3.6 3.9 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3.6 A 3. Knowledge of which events related to system operation / status should be reported.
( ) 2.8* 3. 7 v
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 4.1
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.3* 3.8
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.6 4.1
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.4 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.9 4.1
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.3 4.5
- 11. Ability to perform those actions, without reference to proce-p dure, for all casualties which require immediate operation of g j system components or controls. 4.5 4.5 K/A catalog 3.7-27
SYSTEM: 000 Emergency Plant Evolut;ons EPE MODE: 058 Loss of DC Power IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the loss of dc power emergency task:
EKl.01 Battery charger equipment and instrumentation....... . 2.8 3.1*
EK1.02 Electrical units: volts, amps, and dc.. . .............. 2.0 2. 3 EK2 Knowledge of the following components:
EK2.01 Motors........ .............. ... ... ................. 1.9 2. 2 EK2.02 Breakers, relays, and disconnects... ......... .... . . 2.2* 2.4*
EK3 Knowledge of the bases or reasons for the following:
EK3.01 Use of dc control power by D/Gs... ..................... 3.4* 3.7 EK3.02 Actions contained in E0P for loss of dc power....... . . 4.0 4.2 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Cross-tie of the affected dc bus with the alternate supply........ ................... ....... ............. 3.4* 3.5 EA1.02 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector............... 3.1* 3.1 EA1.03 Vital and battery bus components........................ 3.1 3.3 EA2 Ability to determine or interpret:
EA2.01 That a loss of dc power has occurred; verification that substitute power sources have come on line.............. 3.7 4.1 EA2.02 125V dc bus voltage, low / critical low, alarm....... .... 3.3* 3.6 EA2.03 DC loads lost; impact on ability to operate and monitor p l a n t sy s t em s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5 3.9 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervitors or off plant personnel. 2.7* 3. 5
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.6*
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 3.9 O
K/A catalog 3.7-28
p SYSTEM: 000 Emergency Plant Evolutions
( T EPE MODE: 058 Loss of DC Power wp IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 6. Ability to locate and operate components, using local controls (outside the control room). 3.3 3.5
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.2 3. 7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Speci-fications. 3.4 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.6 3.8
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.2
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.1 4.3 e
'N K/A catalog 3.7-29
9l li i
\
l l
1 Control Air Systems and Malfunctions l
l 1
I
'O
O I I G
SYSTEM: 078 Instrument Air System (IAS)
TASK MODE: 000 Generic TASK: Perform lineups of the IAS Start up the IAS Monitor IAS
- Shif t instrument air compressors Operate system air dryers Perform testing of automatic operation of IAS IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 j1 Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems:
K1.01 Sensor air.-............................................. 2.8* 2.7*
K1.02 Service air............................................. 2.7* 2.8 K1.03 Containment air......................................... 3.3* 3.4*
K1.04 Cool ing wate r to compres so r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 2.9 K1.05 MSIV air................................................ 3.4* 3.5*
O l.
U / K2 Knowledge of bus power supplies to the following:
K2.01 Instrument ai r compressor. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7 2.9 K2.02 Emergency air compressor................................ 3.3* 3.5*
K3 Knowledge of the effect that a loss of the IAS will have on the following:
K3.01 Containment air system.................................. 3.1* 3.4*
K3.02 Systems having pneumatic valves and controls............ 3.4 3.6 K3.03 C ro s s- t i ed u n i ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 0 3.4 K4 Knowledge of IAS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Manual / automatic transfers of control . . . . . . . . . . . . . . . . . . . 2. 7 2. 9 K4.02 Cross-over to other air systems......................... 3.2 3.5 K4.03 Securing of SAS upon loss of cooling water.............. 3.1* 3.3*
K5 Knowledge of the following theoretical concepts as they apply to the IAS:
K5.01 Gas laws................................................ 1.5 1.7 K5.02 Diesel effect........................................... 1.7 1. 8
(
K/A catalog 3.8-1
SYSTEM: 078 Instrument Air System (IAS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO ;
)
K6 Knowledge of the applicable performance and design at-tributes of the following IAS components:
K6.01 A i r c omp re s s o r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4 2.6 K6.02 Pressure gauges......................................... 1.9 2.1 K6.03 Temperature indicators................................. 1.8 2.1 K6.04 Service air refusal valve........ ...................... 2.2* 2.4*
K6.05 A i r d ry e r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.2 K6.06 Cross-tie va1ve......................................... 2.1 2.4 K6.07 Va1ves.................................................. 1.7 1. 9 K6.08 Sensors and detectors....... ................. ......... 1.7 1. 9 K6.09 Controllers and positioners... ......................... 1.7 2.1 K6.10 Motors.................................................. 1.5 1. 7 K6.11 Heat exchangers and condensers.......... ........ ...... 1.6 1.7 K6.12 Breakers, relays, and disconnects....................... 1.5 1.8 K6.13 Filters................................................. 1.6 1.9 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the IAS controls including:
A2 Ability to (a) predict the impacts of the following mal-functions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Air dryer and filter malfunctions.................. .... 2.4 2.9 A3 Ability to monitor automatic operation of the IAS, in-cluding:
A3.01 Air pressure..... .... ................................ 3.1 3.2 A3.02 Air temperature. ................... ................. 2.3 2.3 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Pressure gauges................................. ....... 3.1 3.1 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.7 3.1 K/A catalog 3.8-2
O SYSTEM: 078 Instrument Air System (IAS) i s TASK MODE: 000 Generic s
, Tasks as noted previously.
IMPORTANCE l SYSTEM GENERIC K/As R0 SR0
- 2. Knowledge of system status criteria which require the notifi-
! cation of plant supervisors or off plant personnel. 2.5* 3.1*
l
- 3. Knowledge of which events related to system operation / status should be reported. 2.5* 3.0*
- 4. Knowledge of system purpose and/or function. 3.2 3.4 l 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety I limits. 2.5 3.2* I i
- 6. Ability to locate and operate components, using local controls l (outside the control room). 2.9 3.2 1
( 7. Ability to locate, explain, and apply all limits and precau-tions. 3.0 3.5
- 8. Ability to recognize indications for system operating param-lV eters, which are entry level conditions for Technical Specifi-cations. 2.7* 3.3*
l
- 9. Ability to verify system alarm setpoints and operate controls '
identified in the alarm response manual. 3.1 3.3
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.4 3.7
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate r;peration of system components or controls. 3.7* 3.7
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.2 2.4*
Normal plant operations........................................ 2.2 2.4 Plant heatup and startup....................................... 2.4* 2.6*
Plant shutdown and cooldown.................................... 2.3* 2.3 l
( I l
K/A catalog 3.8-3 l l
/~'s
! \
QJ SYSTEM: 079 Station Air System (SAS)
YASK MODE: 000 Generic TASK: Perform lineups of SAS Start up a station air compressor Monitor SAS operation Shut down the SAS IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the SAS and the following systems:
Kl.01 IAS..................................................... 3.0 3.1 K1.02 Cool i ng wate r to compre s s o r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2 2. 2 K2 Knowledge of bus power supplies to the following:
K2.01 Station air compressors................................. 2.3 2.3
[\ K3 Knowledge of the effect that a loss of the SAS will
\s / have on the following:
K3.01 Ventilation system...................................... 1.7 1.9 K4 Knowledge of SAS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Cross-connect with IAS.................................. 2.9 3.2 K4.02 Automatic control of station ai r pressure. . . . . . . . . . . . . . . 2.2 2.4 K5 Knowledge of the following theoretical concepts as they
~
apply to the SAS:
K5.01 Gas laws................................................ 1.4 1.6 K5.02 Diesel effect: safety implications...................... 1.5 1.7 .
l 1
K6 Knowledge of the applicable performance and design at- 1 tributes of the following SAS components:
K6.01 Valves.................................................. 1.6 1.7 K6.02 Sensors and detectors................................... 1.4 1. 5 K6.03 Controllers and positioners............................. 1.7 1.8 K6.04 Motors.................................................. 1.3 1.4 K6.05 Heat exchangers and condensers.......................... 1.3 1.4
/
es K6.06 Breakers, relays, and disconnects....................... 1.4 1.4
\ K6.07 Filters................................................. 1. 5 1.6 K/A catalog 3.8-5
SYSTEM: 079 Station Air System (SAS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SAS controls including:
A2 Ability to (a) predict the impacts of the following mal-functions or operations on the SAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Cross-connection with IAS............................... 2.9 3.2 A3 Ability to monitor automatic operation of the SAS in-c i ud_i ng:
A3.01 Normal operating pressure............................... 2.0* 2.1*
A3.02 Normal operating temperature.................... ....... 1.8 1. 9 A3.03 Automatic start of the compressor....................... 1.9 2.0 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Cross-tie valves with IAS............................... 2.7 2.7 A4.02 Reducti on o f loads o f f SAS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.1 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.2 2.5
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.1 2.6* ,
- 3. Knowledge of which events related to system operation / status should be reported. 2.1 2.6*
- 4. Knowledge of system purpose and/or function. 2.5 2.7
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.4 3.1*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.1 2.2 K/A catalog 3.8-6
1 SYSTEM: 079 Station Air System (SAS)
(())
_, TASK MODE: 000 Generic Tasks as noted previously.
1 IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 7. Ability to locate, explain, and apply all limits and precau-tions.
2.3 2.6'
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 2.6* 3.2*
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 2.6 2.7
- 10. Ability to recognize abnormal indications for system operating
, parameters, which are entry-level conditions for emergency and abnormal operating procedures. 2.8* 2.9* ,
- 11. . Ability to perform those actions, without reference to proce-
- dure, for all casualties which require immediate operation of l system components or controls. 3.1* 3.2*
, 12. Ability to perform specific system and integrated plant opera-tions during:
Control l ed pl ant l oad change. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.3 Normal plant operations........................................ 2.2 2.2 Plant heatup and startup....................................... 2.2 2.3 Plant shutdown and coo 1down.................................... 2.2 2. 2 O
l K/A catalog 3.8-7 1
(n) v SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 065 Loss of Instrument Air IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the loss of instrument air emergency task:
EK1.01 Understanding units of flow and pressure...SCFM, linear m e t e r , p s i g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ., . 1. 9 2.2 EK2 Knowledge of the following components:
EK2.01 Compressors............................................. 2.2 2.4 EK2.02 Valves.................................................. 1.9 2.1 EK2.03 Pumps................................................... 1.7 1.8 EK2.04 Motors.................................................. 1.6 1.7 EK2.05 Air dryers , filters , and heat exchangers. . . . . . . . . . . . . . . . 2.0 2.2 EK3 Knowledge of the bases or reasons for the following:
g'"N Placing previously running compressor switch "off"...... 2.2* 2.3
( ') EK3.01 EK3.02 Checking previously running compressor electrical breaker.................................................2.2 2.4 EK3.03 Knowing effects on plant operation of isolating certain '
equipment from instrument air........................... 2.9 3.4 I EK3.04 Cross-over to backup air supplies....................... 3.0 3.2 l EK3.05 Checking electric loads on a running compressor......... 2.2? 2.7? l EK3.06 Blocking open certain valves during recovery............ 2.3* 2. 7*
EK3.07 Backup of compressor cooling water...................... 2.3* 2.5*
EK3.08 Actions contained in E0P for loss of instrument air..... 3.7 3.9 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Remote manual loaders................................... 2.7* 2.5 EA1.02 Components served by instrument air to minimize drain I on system............................................... 2.6 2. 8 EA1.03 Restoration of systems served by instrument air when pressure is regained.................................... 2.9 3.1 EA1.04 Emergency air compressor................................ 3.5* 3.4*
EA1.05 RPS..................................................... 3.3* 3.3* ;
EA2 Ability to determine or interpret:
~~x EA2.01 Cause and effect of low pressure instrument air alarm... 2.9 3.2
, )EA2.02 Relationship of flow readings to system operation....... 2.4* 2.6*
%.)
K/A catalog 3.8-9
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 065 Loss of Instrument Air IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.03 Location and isolation of leaks......................... 2.6 2.9 EA2.04 Typical conditions which could cause a compressor trip (e.g., high temperature)................... ............ 2.2 2.7 EA2.05 When to commence plant shutdown if instrument air pres-sure is decreasing...................................... 3.4* 4.1 EA2.06 When to trip reactor if instrument air pressure is de-creasing...............................................3.6* 4.2 EA2.07 Whether backup nitrogen supply is controlling valve position...................................... .... .. 2.8* 3.2*
EA2.08 Failure modes of air-operated equipment.............. .. 2.9* 3.3 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.2
- 3. Knowledge of which events related to system operation / status should be reported. 2.5 3.3*
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.8 3.4*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.8* 3.1
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.0 3.5
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 2. 9 3.7*
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.0 3.3
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.8 4.1
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 3. 9 O
K/A catalog 3.8-10
,- x SYSTEM: 000 Emergency Plant Evolutions
( EPE MODE: 068 Control Room Evacuation
')
\/~
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they apply to the control room evacuation emergency task:
EK1.01 Use of steam tables..................................... 2.4* 2.7*
EK2 Knowledge of the following components:
EK2.01 Auxiliary shutdown panel layout......................... 3.9 4.0 EK2.02 Reactor trip system............................... ..... 3.7 3.9 EK2.03 Controllers and positioners. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.1 EK2.04 Pumps................................................... 2.2 2.4*
EK2.05 Motors.................................................. 2.1 2.1 EK2.06 Breakers, relays, and disconnects....................... 2.4* 2.7 EK2.07 ED/G.................................................... 3.3 3.4 EK3 Knowledge of the bases or reasons for the following:
EK3.01 System response to reactor trip......................... 3.9 4.2 EK3.02 System response to turbine trip......................... 3.7 4.1 EK3.03 Transfer of AFW flow control valves and pumps to local
/~~N control................................................. 3.7 4.3
( I EK3.04 Filling the feedwater system and closing the AFW pump
' discharge valve......................................... 3.0* 3.2*
EK3.05 Repositioning valves to isolate and drain the AFW pump turbine and steam supply header......................... 2.5* 3.0*
EK3.06 Transfer of S/G atmospheric relief valves to local con-trol; operation to maintain specified T-ave............. 3.9 4.3 EK3.07 Maintenance of S/G level, using AFW flow control valves. 4.0 4.3 EK3.08 Trip of the MFW and necessary condensate pumps.......... 3.4 3.9 EK3.09 Transfer of the following to local control: charging pumps, charging header flow control valve, PZR heaters, and boric acid transfer pumps......... ................. 3.9 4.4 EK3.10 Maintenance of PZR level, using pumps and heaters....... 3.9 4.2 EK3.11 Tech-Spec limits and tables for quantity of boric acid.. 3.2 3.6 EK3.12 Required sequence of actions for emergency evacuation of control room......................................... 4.1 4.5 EK3.13 Performing a shutdown margin calculation, including boron needed and boration time.......................... 3.3 3.9 EK3.14 Safety injection setpoint of main steam line pressure... 3.2* 3.4*
EK3.15 Turbine trip setpoint for automatic-stop because of low oil pressure........................... ................ 2.2* 2.4*
EK3.16 Fail-open of the control room doors for personnel evacuation.............................................. 2.8* 3.3*
EK3.17 Injection of boric acid into the RCS.................... 3.7 4.0 EK3.18 Actions contained in E0P for control room evacuation emergency task............. ..................... ...... 4.2 4.5 f-s\
k /
\j K/A catalog 3.8-11
l l
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 068 Control Room Evacuation IMPORTANCE K/A NO. ABILITY R0 SR0 EA1 Ability to operate and monitor the following:
EA1.01 S/G atmospheric relief valve..... .... .... . ... ... 4.3 4.5 EA1.02 AFW emergency pump.... ...... . . ............ ..... 4.3 4.5 EA1.03 S/G level..... . ......... ...... .. ......... ...... 4.1 4.3 EA1.04 MFW pump trip......... .................... ..... ...... 3.3* 3.6 EA1.05 Condensate pump trip...... .........................2.7* 2.9*
EA1.06 Charging pump..... ..... .. ......... ... ...... .. . 4.1 4.2 EA1.07 PZR heaters.......... ... ............ . ............... 4.1 4.2 EA1.08 Local boric acid flow..................... ............. 4.2* 4.2*
EA1.09 Synchroscope key................. .......... ......... . 3.1* 2.7*
EA1.10 Power distribution: ac and dc...... ............ . . 3.7* 3.9 EA1.11 Emergency borate valve controls and indicators.... . . 3.9 4.1 EA1.12 Auxiliary shutdown panel controls and indicators....... . 4.4 4.4 EA1.13 Charging pump controllers (to maintain PZR level)....... 4.1 4.2 EA1.14 Reactor trip breakers and switches. ...... ...... ... .. 4.2 4.4 EA1.15 Turbine trip lights and indicators..... ...... .. ... 3.7 3.7 EA1.16 Turbine throttle valve indicating lights and position indicators................... .. ........ ........ .... 3.2* 3.3 EA1.17 Turbine stop valve bistable lights........ . ........... 3.2* 3.3*
EA1.18 Turbine automatic-stop oil pressure indicators and lights.................................... . ... ....... 2.8* 2.8*
EA1.19 Boric acid transfer pump..................... .. . . .. . 3.7 3.9 EA1.20 Indicators for operation of startup transformer.. ..... 3.2* 3.2*
EA1.21 Transfer of controls from control room to shutdown panel or local control............. .. ............. ... 3.9 4.1 EA1.22 Flow control valve for RCS charging header.. ........... 4.0 4.3 EA1.23 Manual trip of reactor and turbine... .... ...... ..... 4.3 4.4 EA1.24 Control room re-accessibility...... .. ...... .......... 3.0* 3.6 EA1.25 Plant emergency alarm...... ............ .... ..... ... 3.2* 3.7 EA1.26 Unlocking of switches and operation of AFW valves.. . .. 3.6* 3.8*
EA1.27 Local trip of main feed pumps and condensate pumps...... 3.2* 3.4*
EA1.28 PZR level control and pressure control. . . . . .. 3.8 4.0 EA1.29 Calculation of boron needed for xenon-free shutdown. .. 3.1 3.6 EA1.30 Operation of the letdown system............. ... .. ... 3.4 3.6 EA1.31 ED/G...... ..... . ....... ...... ..... .. .......... 3.9 4.0 EA1.32 Natural circulation flow......... .... ..... . . . . 3.9 4.1 EA2 Ability to determine or interpret:
EA2.01 S/G 1evel........... .. . . .... .. . . .......... 4.0 4.3 EA2.02 Local boric acid flow..... .. ..... ..... . ....... 3.7* 4.2*
EA2.03 T-hot, T-cold, and in-core temperatures...... .. .. 4.0 4.2 EA2.04 S/G pressure...... . .. . ... ... . ...... . . .. ..... 3.7 4.0 EA2.05 Availability of heat sink. .... .......... ..... . .. 4.2 4.3 EA2.06 RCS pressure.. ............. . . .. . ... ... . . .... 4.1 4.3 EA2.07 PZR level. ... ... .... ..... . ... ... ... ... . .. 4.1 4.3 EA2.08 S/G pressure...... .. ...... .. ... ...... ... . . . 3.9 4.1 K/A catalog 3.8-12
f'~'s SYSTEM: 000 Emergency Plant Evolutions
! ! EPE MODE: 068 Control Room Evacuation V
IMPORTANCE K/A NO. ABILITY R0 SRO EA2.09 Saturation margin....................................... 4.1 4.3 EA2.10 Source-range count rate............................,.... 4.2* 4.4*
EA2.11 Indications of natural circulation...................... 4.3 4.4 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.9 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.8* 3.7
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 3.1 3.9
- 6. Ability to locate and operate components, using local controls (outside the control room). 4.0 4.1
- 7. Ability to locate, explain, and apply all limits and precau-
/'_~s\
tions. 3.5 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifi-cations. 3.4 4.4
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.6
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.4 4.6
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4.5 A
K/A catalog 3.8-13
-~
O s'
_l i
i Instrumentation Systems 5l t and Malfunctions O
C
m '
/
\m .
SYSTEM: 012 Reactor Protection System (RPS)
TASK MODE: 000 Generic TASK: Place an RPS channel in the tripped condition Bypass a trip condition on a reactor protection panel Monitor the RPS IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the RPS and the following systems:
Kl.01 120V vital / instrument power system...................... 3.4 3.7 K1.02 125V de system.......................................... 3.4 3.7 K1.03 CRDS................................................. .. 3.7 3.8 K1.04 RPIS.................................................... 3.2* 3.3*
Kl.05 ESFAS........... ....................................... 3.8* 3.9 K1.06 T/G..................................................... 3.1* 3.1 Kl.07 S05..................................................... 3.2* 3.2*
K1.08 MFW.......................................... .......... 2.9* 3.1 I) s_-
K2 Knowledge of bus pover supplies to the sollowing:
K2.01 RPS channels, components, and interconnections.......... 3.3 3. 7 K3 Knowledge of the effect that a loss of thc RPS will
~
have on the following: i K3.01 CRDS.................................................... 3.9 4.0 K3.02 T/G....................................... ......... .. 3.2* 3.3 K3.03 SD5..................................................... 3.1* 3.3 l K3.04 ESFAS.................................................. 3.8* 4.1* l K4 Knowledge of RPS design feature (s) and/or interlock (s) l which provide for the following:
Trip logic when one channel 00C or in test..............
K4.01 3.7 4.0 K4.02 Automatic reactor trip when RPS setpoints are exceeded for each RPS function; basis for each................. 3.9 4.3 i K4.03 Function generator processing and combining of detector '
signals in RPS channels................................. 2.3 2.7*
K4.04 Redundancy............................................. 3.1 3.3 K4.05 Spurious trip protecti on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7 2.9 K4.06 Automatic or manual enable / disable of RPS trips......... 3.2 3.5 K4.07 First-out indication............ . ..................... 3.0 3.2*
/'~'N K4.08 Logic matrix testing........... . ..................... 2.8* 3.3*
( ) K4.09 Separation of control and protection circuits........... 2.8 3.1 K/A catalog 3.9-1
SYSTEM: 012 Reactor Protection System (RPS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5 Knowledge of the following theoretical concepts as they apply to the RPS:
K5.01 DNB........................... . ....................... 3.3* 3.8 K5.02 Power density....................................... ... 3.1* 3.3*
K6 Knowledge of the applicable performance and design attributes of the following RPS components:
K6.01 Bistables and bistable test equipment...... ...........2.8 3.3 K6.02 Redundant channels.................... . ... ..... .... 2.9 3.1 K6.03 Trip logic circuits................. ........... ...... 3.1 3.5 K6.04 Bypass-block circuits... ........... ................... 3.3 3.6 K6.05 Test circuits......... ... ....... .................. .. 2.4 2.8 K6.06 Sensors and detectors................................... 2.7* 2.8 K6.07 Core protection calculator.. ........................... 2.9* 3.2*
K6.08 C0LSS........................................... ....... 3.6* 3.7*
K6.09 CEAC................................. .. ............... 3.6* 3.7*
K6.10 Permissive circuits............ ............... ........ 3.3 3. 5 K6.11 Trip setpoint calculators...... ........................ 2.9* 2. 9 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPS controls including:
A1.01 Trip setpoint adjustment................................ 2.9* 3.4*
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Faulty bistable operation.................... ..... . .. 3.1 3.6 A2.02 Loss of instrument power.......... .......... . ........ 3.6 3.9 A2.03 Incorrect channel bypassing.......................... .. 3.4 3.7 A2.04 Erratic power supply operation..... .......... ... ..... 3.1 3.2 A2.05 Faulty or erratic operation of detectors and function generators................ ............................. 3.1* 3.2*
A2.06 Failure of RPS signal to trip the reactor.. ..... . .... 4.4 4.7 A2.07 Loss of dc control power..... ... ...... ...... ... .. 3.2* 3.7 O
K/A catalog 3.9-2
/N SYSTEM: 012 Reactor Protection System (RPS)
( ,) _
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A3 Ability to monitor automatic operation of the RPS, including: ;
A3.01 Individual channel...................................... 3.8 3.9 A3.02 Bistables............................................... 3.6 3.6 A3.03 Power supply............................................ 3.4 3. 5 A3.04 Circuit breaker......................................... 2.8* 2.9 A3.05 Single and multiple channel trip indicators............. 3.6 3.7 A3.06 Trip 1ogic.............................................. 3.7 3.7 A3.07 Trip breakers........................................... 4.0 4.0 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Manual trip button...................................... 4.5 4.5 A4.02 Components for individual channels...................... 3.3 3.4 A4.03 Channel blocks and bypasses............................. 3.6 3.6 fss A4.04 Bistable, trips, reset and test switches................ 3.3* 3.3 t ) A4.05 Channel defeat controls................................. 3.6 3.6
\d A4.06 Reactor trip breakers................................... 4.3 4.3 A4.07 M/G set breakers........................................ 3.9* 3.9*
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.9 4.1
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3. 5*
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.7*
- 4. Knowledge of system purpose and/or function. 4.1 4.3
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 3.2* 4.0
- 6. Ability to locate and operate components, using local con-trols (outside the control room). 3.1 3.4 s
s' 7. Ability to locate, explain, and apply all limits and precau-
, tions. 3.7 4.2
\
K/A catalog 3.9-3
SYSTEM: 012 Reactor Protection System (RPS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 8. Ability to recognize indications for system operating param-eters which are entry level conditions for Technical Specifications. 3.7 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.9 4.1
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.4 4.7
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.5 4.5
- 12. Ability to perform specific system and integrated plant opera- ,.
tions during:
Controlled plant load change................................... 2.9 2.9 Normal plant operations........................................ 3.0 3.0 Plant heatup and startup....................................... 3.1 3.1 Plant shutdown and cooldown....................... ........ ... 3.0 3.1 O
K/A catalog 3.9-4
SYSTEM: 015 Nuclear Instrumentation System (NIS)
TASK MODE: 000 Generic TASK: Perform reactor power-range instrumentation calibration test Perform axial power distribution monitoring test (alarm)
Perform calorimetric heat balance calculation Perform hot-functional and low power physics tests (meter refueling)
! Perform source-range tests Perform intermediate-range test Perform power range permissives and trip test IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the NIS and the following systems:
K1.01 RPS..................................................... 4.1 4.2 K1.02 Vital ac systems........................................ 3.4 3.6 K1.03 CRDS....................................................3.1* 3.1
,_s K1.04 ESF..................................................... 3.5* 3.5*
/ ') K1.05 1C5..................................................... 3.9* 3.9*
,( _, / K1.06 Reactor regulating system............................... 3.1* 3.4*
j K1.07 Plant computer.......................................... 2.4* 2.4 K1.08 RCS (pump start)........................................ 2.6* 2.9*
K2 Knowledge of bus power supplies to the following:
K2.01 NIS channels, components, and interconnections.......... 3.3 3.7 K3 Knowledge of the effect that a loss of the NIS will have on the following:
K3.01 RPS.............................. ...................... 3.9 4.3
' K3.02 CRDS............................... .................... 3.3* 3.5*
K3.03 Fuel handling system.................................... 2.7 3.4*
K3.04 I05..................................................... 3.4* 4.0*
K3.05 Plant computer.......................................... 2.3* 2.4 1 K3.06 Reactor regulating system............................... 2.9* 3.2*
K4 Knowledge of NIS design feature (s) and/or interlock (s)
I which provide for the following: .
I K4.01 Source-range detector power shutoff at high powers...... 3.1 3.3 K4.02 Rod motion inhibits..................................... 3.7 3.9
/N K4.03 Reading of source range / intermediate range / power range 4.0*
outside control 3.9*
,, )
( room....................................
K4.04 Slow response time of SPNDs............................. 3.4? 3.6?
K/A catalog 3.3-5
SYSTEM: 015 Nuclear Instrumentation System (NIS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K4.05 Reactor trip............................................ 4.3 4.5 K4.06 Reactor trip bypasses................................... 3.9 4.2 K4.07 Permissives............................................. 3.7 3.8 K4.08 Automatic rod motion on demand signals... .............. 3.4 3.7 K5 Knowledge of the following theoretical concepts as they apply to the NIS:
K5.01 Detector operation...................................... 2.9 3.2 K5.02 Discriminator / compensation operation.................... 2.7 2.9 K5.03 Calibration adjustments................................. 2.3* 2.6 K5.04 Factors affecting accuracy and reliability of calori-metric calibrations..................................... 2.6 3.1 K5.05 Criticality and its indications.............. . ........ 4.1 4.4 K5.06 Subcritical multiplications and NIS indications......... 3.4 3.7 K5.07 Effects of burning on axial flux density. . . . . . . . . . . . . . . . 2. 7? 2.9?
K5.06 Entha1py................................................ 2.0 2.3*
K6 Knowledge of the applicable performance and design
! attributes of the following NIS components:
K6.01 Sensors, detectors, and indicators...................... 2.9 3.2 l K6.02 Discriminator / compensation circuits...................... .: 6 2.9 K6.03 Component interconnections.............................. 2.6 3. 0 l K6.04 Bistables and logic circuits............................ 3.1 3.2 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the NIS controls including:
A1.01 NIS calibration by heat balance......................... 3.5 3.8*
A1.02 SUR..................................................... 3.5 3.6 A1.03 NIS power indication.................................... 3.7 3.7 A1.04 Quadrant power tilt ratio............................... 3.5 3.7 A1.05 Imbalance (axial shape)................................. 3.7 3. 9 l A1.06 Fuel burnup............................................. 2.5* 2.9*
3.3* 3.4*
A1.07 Changes in boron concentration..........................
A1.08 Changes in RCS temperature.............................. 3.3* 3.4 l
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
K/A catalog 3.9-6
SYSTEM: 015 Nuclear Instrumentation System (NIS)
/] TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE l K/A NO. ABILITY R0 SRO A2.01 Power supply loss or erratic operation. . . . . . . . . . . . . . . . . . 3.5 3.9 A2.02 Faulty or erratic operation of detectors or compen-sating components....................................... 3.1 3.5*
A2.03 Xenon oscillations...................................... 3.2 3.5*
A3 Ability to monitor automatic operation of the NIS, including:
A3.01 Console and cabinet indications......................... 3.8 3.8 ,
A3.02 Annunciator and alarm signals........................... 3.7 3.9 ,
A3.03 Verification of proper functioning /operabili ty. . . . . . . . . . 3.9 3.9 )
A3.04 Maximum disagreement allowed between channels........... 3.3 3.5 !
l A4 Ability to manually operate and/or monitor in the con- l trol room:
A4.01 Selection of controlling NIS channel.................... 3.6* 3.6*
A4.02 NIS indicators.......................................... 3.9 3.9 A4.03 Trip bypasses........................................... 3.8 3.9 e
(
O K/A catalog 3.9-7 l
i
SYSTEM: 015 Nuclear Instrumentation System (NIS)
TASK MODE: 020 Normal Operations TASK: Operate the scaler-timer Operate the audio count-rate drawer Perform a power imbalance calculation Perform a quadrant power-tilt calculation Monitor the NIS What if quadrant power-tilt ratio exceeds tech-spec limits?
Perform full-core flux mapping IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the NIS and the following systems:
K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the NIS will have on the following:
K4 Knowledge of NIS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Redundant sources of information on axial flux density distribution............................................ 2.8 3.3 K4.02 Redundant sources of information on power level. . . . . . . . 3.2 3.5 K5 Knowledge of the following theoretical concepts as they apply to the NIS:
K5.01 In-core detector operation............. ...... ... ... . 2.5 2.9 K5.02 Ex-core detector operation...... ....................... 2.8 3.0 K5.03 Axial flux imbalance, including long-range effects. . . . . . 3.3 3.7 K5.04 Quadrant power tilt, including long-range ef fects. . . . . . . 3.2 3.6 K5.05 Peaking and hot-channel factor. ........................ 3.1 3.5 K5.06 Neutron flux density, definition and relation to reac-tor power... ........................................... 2.8 3.1 K5.07 Effects of xenon on local flux, and factors affecting xenon concentrations.................. . ............... 3.3 3. 7 K5.08 Definition and calculation of quadrant tilt ratio....... 2.9 3.4-K5.09 DNB and DNBR definition and effects..... .... .. ....... 3.5 3. 7 K5.10 Definition of reactor poison.. ...... ..... . .... .. . 2.9 3.2 K5.11 Heat balance.... ............. .. .. ............... ... 2.9 3.2 K6 Knowledge of the applicable performance and design attributes of the following NIS components:
K6.01 Audio indication, including deaf spots in control room and containment..... . .. .... ... . ... .. .. 2.2 2.6 KG.02 Scaler-timers.. .. ........ .. .............. . ..... . 2.1 2.6 K/A catalog 3.9-8
, SYSTEM: 015 Nuclear Instrumentation System (NIS)
(m
%.)
) TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6.03 Imbalance indication.................................... 2.4 2.9*
K6.04 In-core detector locations, radially and axially........ 2.1 2.4 i
^
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the NIS controls including:
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron vs. control rod reactivity changes...................... 3.3 3.8
' /N A2.02 Core void formation..................................... 3.3 3.8 k'
A3 Ability to monitor automatic operation of the NIS, including:
A3.01 Recognition of audio output expected for a given plant condition...............................................2.6 2.7*
A3.02 Interpretation of in-core flux density maps from in-core detectors............................................... 2.4* 3.2*
A4 Ability to manually operate and/or monitor in the con-trol room:
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.5 3.9
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.4
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.5*
- 4. Knowledge of system purpose and/or function. 3.6 3.8 fi!
s 5. Knowledge of the Technical Specification bases and defini-U tions related to limiting conditions for operations and safety limits. 2.8* 3.9 K/A catalog 3.9-9
SYSTEM: 015 Nuclear Instrumentation System (NIS)
TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.7* 2.8*
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.5 4.0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.3 4.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.7 3.8
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.2 4.4
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.3 4.4
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.9 3.1*
Normal plant operations........................................ 3.0 3.0 Plant heatup and startop....................................... 3.2 3.1 Plant shutdown and cooldown.................................... 3.0 3.0 O
K/A catalog 3.9-10
/m %
b' SYSTEM: 016 Non-Nuclear Instrumentation System (NNIS)
TASK MODE: 000 Generic TASK: Line up the NNIS IMPORTANCE K/A N0. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the NNIS and the following systems:
Kl.01 RCS..................................................... 3.4* 3.4*
Kl.02 PZRLCS.................................................3.4* 3.3*
K1.03 5D5..................................................... 3.2* 3.2*
K1.04 M FW sy s t e m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 . 7
- 2.7*
K1.05 C o n d e n s a t e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1* 2.2*
Kl.06 A FW sy s t e m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 6
- 3.5*
K1.07 ECCS.................................................... 3.7* 3.7*
K1.08 PZRPCS.................................................3.4* 3.4*
K1.09 ESFAS................................................... 3.7* 3.7*
Kl.10 CC5..................................................... 3.1* 3.1*
,s '
Kl.11 MT/G.................................................... 2.3* 2.2*
(s Kl.12 S/G..................................................... 3.5* 3.5*
KP Knowledge of bus power supplies to the following:
K2.01 NN I S c h a n n e l s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4
- 2.5*
K3 Knowledge of the effect that a loss of the NNIS will have on the following:
K3.01 RCS..................................................... 3.4* 3.6* l K3.02 PZRLCS................................................3.4* 3.5*
K3.03 5DS..................................................... 3.0* 3.1*
K3.04 M FW sy s t e m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 . 6
- 2.7*
K3.05 Condensate.............................................. 1.8* 2.0*
K3.06 AFW system.............................................. 3.5* 3.7* ;
K3.07 ECCS.................................................... 3.6* 3.7* )
K3.08 PZR PCS................................................. 3.5* 3.7* 1 K3.09 ESFAS...................................................3.5* 3.7*
K3.10 CCS..................................................... 3.0* 3.2*
K3.11 MT/G.................................................... 2.2* 2.2*
K3.12 S/G..................................................... 3.4* 3.6*
K4 Knowledge of NNIS design feature (s) and/or interlock (s) ,
which provide for the following: I 1
K4.01 Reading of NNIS channel values outside control room..... 2.8* 2.9*
[%'))
K/A catalog 3.9-11
SYSTEM: 016 Non-Nuclear Instrumentation System (NNIS)
TASK MODE: 000 Generic Task as noted previously.
IMPORTANCE K/A N0. KNOWLEDGE R0 SRO K4.02 Sensing, signal processing, display, recording, and a l a rm s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3* 2.7*
K4.03 Input to control systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 8* 2.9*
K5 Knowledge of the following theoretical concepts as they apply to the NNIS:
K5.01 Separation of control and protection circuits........... 2.7* 2.8*
K6 Knowledge of the applicable performance and design attributes of the following NNIS components:
K6.01 Sensors and detectors................................... 2.3* 2.5*
ABILITY g Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the NNIS controls including:
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Detector failure........................................ 3.0* 3.1*
A2.02 Loss of power supply....................... ........... 2.9* 3.2*
A2.03 Interruption of transmitted signal................. .. 3.0 3.3*
A2.03 Voltage to instruments, both too high and too low..... . 2.5* 2.6*
A3 Ability to monitor automatic operation of the NNIS, including:
A3.01 Automatic selection of NNIS inputs to control systems... 2.9* 2.9*
A3.02 Relationship between meter readings and actual param-eter val"as.............................................. 2.9* 2.9*
A4 Abiiity to manually operate and/or monitor in the con-trol room:
A4.01 NNI channel sel ect control s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9* 2.8*
A4.02 Recorders............... ......... .................. 2.7 2.6*
O K/A catalog 3.9-12
r^N SYSTEM: 016 Non-Nuclear Instrumentation System (NNIS)
( ) TASK MODE: 000 Generic v
Task as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.3* 3.5*
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.2*
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.5*
- 4. Knowledge of system purpose and/or function. 3.2* 3.4*
- 5. Knowledge of the Technical Specification bases and definitions related to limiting conditions for operations and safety limits. 2.7* 3.5*
- 6. Ability to locate and operate components, using local con-trols (outside the control room). 2.7* 2.7*
IT 7. Ability to locate, explain, and apply all limits and precau-h tions. 3.1* 3.5*
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3. l* 3.8*
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.2* 3. 2*
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.8* 3.9*
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.2* 4.2*
- 12. Ability to perform specific system and integrated plant opera-tions during: .
Controlled plant load change................................... 3.0* 2.8*
Normal plant operations........................................ 3.0* 2.8*
Plant heatup and startup....................................... 3.0* 2.8*
Plant shutdown and cooldown............................ ....... 3.0* 3.8*
O K/A catalog 3.9-13 L_
!n 4 1, )
\~ /
, SYSTEM: 017 In-Core Temperature Monitor (ITM) System TASK MODE: 020 Normal Operations TASK: Operate the ITM Monitor the ITM IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the ITM system and the following systems:
K1.01 Plant computer (C0LSS).................................. 3.2* 3.2*
K1.02 RCS..................................................... 3.3 3.5 K2 Knowledge of bus power supplies to the following:
K2.01 ITM system.............................................. 2.0 2.2 K3 Knowledge of the effect that a loss of the ITM system 7-~s will have on the following:
s- K3.01 Natural circulation indications......................... 3.5* 3.7*
K4 Knowledge of ITM system design feature (s) and/or interlock (s) which provide for the following:
K4.01 Input to subcooling monitors............................ 3.4 3.7 K4.02 Sensing and determination of location core hot spots.... 3.1 3.6 K4.03 Range of temperature indication......................... 3.1 3.3 K5 Knowledge of the following theoretical concepts as they apply to the ITM system:
K5.01 Temperature at which cladding and fuel melt............. 3.1 3.9 K5.02 Saturation and subcooling of water...................... 3.7 4.0 K5.03 Indication of superheating.............................. 3.7 4.1 K6 Knowledge of the applicable performance and design attributes of the following ITM system components:
K6.01 Sensors and detectors................................... 2.7 3.0 Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with s operating the ITM system controls including:
\s_,/ A1.01 Core exit temperature................................... 3.7 3.9 K/A catalog 3.9-15
SYSTEM: 017 In-Core Temperature Monitor (ITM) System TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Thermocouple open and short circuits.................... 3.1 3.5 A2.02 Core damage............................................. 3.6 4.1 A3 Ability to monitor automatic operation of the ITM system, including:
A3.01 Indications of normal, natural, and interrupted circu-lation of RCS........................................... 3.6* 3.8*
A3.02 Measurement of in-core thermocouple temperatures at panel outside control room.............................. 3.4* 3.1*
A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Actual in-core temperatures............................. 3.8 4.1 A4.02 Temperature values used to determine RCS/RCP operation during inadequate core cooling (i.e., if applicable, average of five highest values)......................... 3.8 4.1 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.9 3.2
- 2. Knowledge of system status criteria which require the notifi-l cation of plant supervisors or off plant personnel. 2.6* 3.5
- 3. Knowledge of which events related to system operation / status should be reported. 2.5* 3.6
- 4. Knowledge of system purpose and/or function. 3.3 3.5
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 3.1* 3.7*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9* 3.2*
O K/A catalog 3.9-16
l s
g SYSTEM: .017 In-Core Temperature Monitor (ITM) System J TASK MODE: 020 Normal Operations
~ )
Tasks as noted previously.
t i IMPORTANCE l SYSTEM GENERIC K/As R0 SR0
}- 7. Ability to locate, explain, and apply all limits and precau-
! -tions. 3.1 3.5
- 8. Ability to recognize. indications for system operating param-
- eters, which are entry level conditions for Technical Specifications. 3.1 4.0 j -9. Ability to verify system alarm setpoints and operate controls 1 identified in the alarm response manual. 3.1 3.4 i
e l 10. Ability to recognize abnormal indications for system operating parameters, which_ are entry-level conditions for emergency and j; abnormal operating procedures. 4.0 4.1 1
11.- Ability _to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.7* 3.8 1 12. . Ability to perform specific system and integrated plant opera-4 tions during:
! ' Controlled plant load change................................... 2.4 2.4
'. Normal plant operations........................................ 2.4 2.4 Plant heatup and startup....................................... 2.4 2.4 j Plant snutdown and cooldown.................................... 2.3 2.3 I
i-i 1
4-4 1 i I t
P 4
i j K/A catalog 3.9-17 4
4
m
,y (v)
SYSTEM: 072 Area Radiation Monitoring (ARM) System TASK MODE: 000 Generic TASK: Perform lineups of the ARM system Perform the ARM instrumentation functional test Operate ARM monitors Monitor ARM operation Perform the ARM equipment check IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the ARM system and the following systems:
Kl.01 Pl ant ventil ation systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1* 3.5*
K2.02 Containment isolation................................... 3.5 3.9 K2.03 Fuel building isolation................................. 3.6* 3.7*
K2.04 Control room venti l ati on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 3* 3.5*
K2.05 MRSS.................................................... 2.8* 2.9*
s (s
xv i
/
K2 Knowledge of bus power supplies to the following:
K2.01 Radiation monitoring systems............................ 2.3* 2.5 K3 Knowledge of the effect that a loss of the ARM system will have on the following:
K3.01- Containment ventilation isolation....................... 3.2* 3.4*
K3.02 Fuel handling operations................................ 3.1 3.5 K4 Knowledge of ARM system design feature (s) and/or inter-lock (s) which provide for the following:
K4.01 Containment ventilation isolation....................... 3.3* 3.6*
K4.02 Fuel bui l di ng i sol ati on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2* 3.4*
K4.03 Plant ventilation systems............................... 3.2* 3.6*
K5 Knowledge of the following theoretical concepts as they apply to the ARM system:
K5.01 Radiation theory, including sources, types, units, and effects................................................. 2.7 3.0 KS.02 Radiation intensity changes with source distance........ 2.5 3.2 K6 Knowledge of the applicable performance and design
(h
(
attributes of the following ARM system components:
K6.01 Sensors and detectors................................... 2.1 2.6 K6.02 Va1ves.............................................. ... 1.6 1.9 K/A catalog 3.9-19
SYSTEM: 072 Area Radiation Monitoring (ARM) System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ARM system controls including:
A1.01 Radiation levels............... .......... ........ ... 3.4 3.6 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Erratic or failed power supply.......................... 2.7 2.9 A2.02 Detector failure........................................ 2.8 2.9 A2.03 B l own powe r- s upp ly f us e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 7 2.9 A3 Ability to monitor automatic operation of the ARM sys-tem, including:
A3.01 Changes in ventilation alignment........................ 2.9* 3.1 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Alarm and interlock setpoint checks and adjustments. . . . . 3.0* 3.3 A4.02 Major components........................................ 2.5* 2.5 A4.03 Check source for operability demonstration. ............ 3.1 3.1 SY51EM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.0 3.3
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.3
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.6
- 4. Knowledge of system purpose and/or function. 3.5 3.7
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8* 3.6*
K/A catalog 3.9-20
,m SYSTEM: 072 Area Radiation Monitoring (ARM) System
!'l i -
TASK MODE: 000 Generic l V-l Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.4 2.8 f 7. Ability to locate, explain, and apply all limits and precau-l tions. 2.9 3.3 l
- 8. Ability to recognize indications for system operating param-
.eters, wnich are entry level conditions for Technical Specifications. 3.2 4.0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.5 3.7
- 10. Ability to recognize abnormal indications for system operating
_ parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.3
- 11. Ability to perform those actions, without reference to proce-dure, for all. casualties which require immediate operation of
[~N) y system components or controls. 4.0 4.1
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.7 2.7 Normal plant operations........................................ 2.7 2.6 Plant heatup and startup....................................... 2.6 2.7 Plant shutdown and coo 1down.................................... 2.6 2.7 0
.K/A catalog 3.9-21
SYSTEM: 073 Process Radiation Monitoring (PRM) System TASK MODE: 000 Generic TASK: Perform lineups of air PRM system Perform PRM instrumentation functional check Operate the PRMs Perform PRM equipment check i Monitor the PRM system l IMPORTANCE !
K/A NO. KNOWLEDGE R0 SR0 l
l K1 Knowledge of the physical connections and/or cause-ef fect relationships between the PRM system and the following systems:
K1.01 Those systems served by PRMs............................ 3.6 3.9 K2 Knowledge of bus power supplies to the following:
K2.01 Radiation monitoring systems............................ 2.3* 2.7*
K3 Knowledge of the effect that a loss of the PRM system will have on the following:
K3.01 Radioactive effluent releases...................... .... 3.6 4.2 K4 Knowledge of PRM system design feature (s) and/or interlock (s) which provide for the following:
K4.01 Release termination when radiation exceeds setpoint..... 4.0 4.3 K4.02 Letdown isolation on high RCS activity.................. 3.3* 3.9*
K5 Knowledge of the following theoretical concepts as they apply to the PRM system:
K5.01 Radiation theory, including sources, types, units, and effects................................................. 2.5 3.0 K5.02 Radiation intensity changes with source distance........ 2.5 3.1 K5.03 Relationship between radiation intensity and exposure limits.......... . ......................... .......... 2.9* 3.4 K6 Knowledge of the applicable performance and design attributes of the following PRM system components:
K6.0? Sen; ors and detectors.......................... .... ... 2.2 2.4 K6.02 Moving filters............................... ... ...... 2.0 2.1 K6.03 Sample blowers............................... .......... 1.9 2.0 K/A catalog 3. ' -23 l ,
SYSTEM: 073 Process Radiation Monitoring (PRM) System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including:
A1.01 Radiation levels........................................ 3.2 3.5 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor-rect, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Erratic or failed power supply.......................... 2.5 2.9*
A2.02 Detector failure........................................ 2.7 3.2 A2.03 Calibration drift....................................... 2.4 2.9*
A3 Ability to monitor automatic operation of the PRM sys-tem, including:
A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Effluent release................................ ....... 3.9 3.9 A4.02 Radiation monitoring system control panel............... 3.7 3.7 A4.03 Check source for operability demonstration.............. 3.1 3.2 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.3 3.7
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.8* 3. 3
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.5*
- 4. Knowledge of system purpose and/or function. 3.7 3.9
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 3.0* 3.8*
- 6. Ability to locate and operate components, using local controls (cutside the control room). 2.5 2.9
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.4 3. 9 K/A catalog 3.9-24
SYSTEM: 073 Process Radiation Monitoring (PRM) System
( -- TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.3 4.2
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.5 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.2 4.4
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.1 4.3
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.6 2.8 s .
No rmal pl ant operati ons . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 2.8 Plant heatup and startup....................................... 2.6 2.8
(' Plant shutdown and cooldown.................................... 2.6 2.8 D
a K/A catalog 3.9-25
A
-( )
kJ SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 032 Loss of Source-Range Nuclear Instrumentation IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as t' apply to the loss of source range nuclear instrumenta-tion emergency task:
EKl.01 Effects of voltage changes on performance............... 2.5 3.1 EK2 Knowledge of the following components:
EK2.01 Power supplies, including proper switch positions....... 2.7* 3.1 EK2.02 . Sensors and detectors............................ ...... 2.4 2.7 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Startup termination on source-range loss................ 3.2 2.6 EK3.02 Guidance contained in E0P for loss of source-range nuclear instrumentation................................. 3.7* '1 p
( ABILITY uJ EA1 Ability to operate and monitor the following:
EA1.01 Manual restoration of power............ ................ 3.1* 3.4*
EA2 Ability to determine or interpret:
EA2.01 Normal / abnormal power supply operation.................. 2.6 2.9*
EA2.02 Expected change in source range count rate when rods are moved............................................... 3.6 3.9 EA2.03 Expected values of source range indication when high voltage is automatically removed........................ 2.8 3.1*
EA2.04 Satisfactory source-range / intermediate-range overlap.... 3.1 3.5 EA2.05 Nature of abnormality, from rapid survey of control room data............................. ................. 2.9* 3.2*
EA2.06 Confirmation of reactor trip............................ 3.9* 4.1*
EA2.07 Maximum allowable channel disagreement.................. 2.8 3.4*
EA2.08 Testing required if power lost, then restored........... 2.2 3.1 EA2.09 Effect of improper HV setting........................... 2.5 2.9 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifica- 1 y'"'$ tion of plant supervisors or off plant personnel. 2.7* 3.3 i
\ J
%/
K/A catalog 3.9-27
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 032 Loss of Source-Range Nuclear Instrumentation IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 3. Knowledge of which events related to system operation / status should be reported. 2.6* 3.5*
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8* 3.7
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.2 2.2
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.2 3.5
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.3 4.2
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.3
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.1 4.2 O
K/A catalog 3.9-28
/ SYSTEM: 000 Emergency Plant Evolutions Q] EPE MODE: 033 Loss of Intermediate-Range Instrumentation IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the loss of intermediate-range instrumentation emergency task:
EKl.01 Effects of voltage changes on performance............... 2.7 3.0 EK2 Knowledge of the following components:
EK2.01 Power supplies, including proper switch position........ 2.4 2.9 EK2.02 Sensors and detectors................................... 2.3 2.6 EK3 Knowledge of the bases or reasons for the following:
EK3.01' Termination of startup following loss of intermediate-range instrumentation................................... 3.2 3.6 EK3.02 Guidance contained in E0P for loss of intermediate-range instrumentation................................... 3.6 3.9 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Power-available indicators in cabinets or equipment drawers.......... ...................................... 2.9 3.1 EA1.02 Level trip bypass....................................... 3.0 3.1 EA1.03 Manual restoration of power. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 0* 3.2*
EA2 Ability to determine or interpret:
EA2.01 Equivalency between source-range, intermediate-range, and power-range channel readings........................ 3.0 3.5 EA2.02 Indications of unreliable intermediate-range channel operation............................................... 3.3 3.6 EA2.03 Indication of blown fuse................................ 2.8 3.1 EA2.04 Satisfactory overlap between source-range, intermediate-range and power-range instrumentation...... 3.2 3.6 EA2.05 Nature of abnormality, from rapid survey of control room data......................... ..................... 3.0* 3.1?
EA2.06 Cause of failure of an intermediate-range channel....... 2.3 2.8* l EA2.07 Confirmation of reactor trip............................ 3.9 4.2 '
EA2.08 Intermediate-range channel operability.................. 3.3 3.4 EA2.09 Conditions which allow bypass of an intermediate-range level trip switch....................................... 3.4* 3.7*
EA2.10 Tech-Spec limits if both intermediate-range channels have failed............................................. 3.1 3.8 EA2.11 Los s of compensati ng vol tage. . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.4 a
K/A catalog 3.9-29
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 033 Loss of Intermediate-Range Instrumentation IMPORTANCE K/A NO. ABILITY R0 SRO EA2.12 Maximum allowable channel disagreement.................. 2.5* 3.1*
EA2.13 Testing required if power lost, then restored........... 2.2* 2.8*
SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.4* 3.1*
- 3. Knowledge of which events related to system operation / status should be reported. 2.4* 3.2*
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.7* 3.5*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.2* 2.2*
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.1 3.5
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.1 3.9
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.1 3.4
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.1
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system comnonents or controls. 3.8* 3.9*
O K/A catalog 3.9-30
4
/N SYSTEM: 000 Emergency Plant Evolutions
( ) EPE MODE: 061 Area Radiation Monitoring (ARM) System Alarms v
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as
, they apply to the ARM system alarms emergency task:
EK1.01 Detector limitations.................................... 2.5* 2.9?
EK2 Knowledge of the following components:
i EK2.01 Detectors at each ARM system location................... 2.5* 2.6*
EK3 Knowledge of the bases or reasons for the fcllowing:
EK3.01 Effect of temperature inversion on ARM system channel indications............................................. 2.3 2.6 EK3.02 Guidance contained in alarm response for ARM system..... 3.4 3.6 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Automatic actuation..................................... 3.6 3.6 s, EA2 Ability to determine or interpret:
EA2.01 ARM panel displays...................................... 3.5 3.7 EA2.02 Normal radiation intensity for each ARM system channel.. 2.9 3.2 EA2.03 Setpoints for alert and high alarms..................... 3.0 3.3 EA2.04 Whether an alarm channel is functioning properly. . . . . . . . 3.1 3.5 EA2.05 Need for area evacuation; check against existing limits. 3.5 4.2 EA2.06 Required actions if alarm channel is out of service..... 3.2 4.1 SYSTEM GENERIC K/As l
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.6* 3.4
- 3. Knowledge of which events related to system operation / status should be reported. 2.6* 3.5
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.6* 3.5*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.6* 2.7 O
( _,/ 7. Ability to locate, explain, and apply all limits and precau-tions. 3.1 3.5 K/A catalog 3.9-31
l SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 061 Area Radiation Monitoring (ARM) System Alarms IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.1 3.9
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.5 3.6
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.1
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 4.0
~
G O
K/A catalog 3.9-32
1 I
i l
Auxiliary Thermal Systems and Malfunctions i
l
""r**- r-e-wym--w---, ____ _ , ,___ _ _
c i A
(Vl SYSTEM: 008 Component Cooling Water System (CCWS)
TASK MODE: 000 Generic TASK: Perform CCWS component operability test Perform CCWS f_ low path verification Perform CCWS pump test Perform CCW flow balance Determine CCWS leak rate from RCS IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the following systems:
K1.01 SWS.....................................................3.1 3.1 Kl.02 Loads cooled by CCWS.................................... 3.3 3.4 K1.03 PRMS.................................................... 2.8* 3.0 K1.04 RCS, in order to determine source (s) of RCS leakage into the CCWS........................................... 3.3* 3.3 K2 Knowledge of bus power supplies to the following:
K2.01 CCW pumps............................................... 2.9* 3.0 K2.02 CCW valves.............................................. 2.1 2.2 K3 Knowledge of the effect that a loss of the CCWS will have on the following:
K3.01 Loads cooled by CCWS.................................... 3.4 3.5 K4 Knowledge of CCWS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Automatic start of standby pump......................... 3.1 3.3 K5 Knowledge of the following theoretical concepts as they apply to the CCWS:
K5.01 Chemistry control....................................... 1.8 2.3 K6 Knowledge of the applicable performance and design attributes of the following CCW components:
K6.01 Va1ves.................................................. 1.9 2.1 O K6.02 Sensors and detectors................................... 1.9 2.0
('~ K6.03 Controllers and positioners............................. 1.8 2.0 K6.04 Pumps...................................................2.1 2.3*
K/A catalog 3.10-1
SYSTEM: 008 Component Cooling Water System (CCWS)
TASK MODE: 000 Generic Tasks as noted previcusly.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K6.05 Motors........................................ ... ..... 1.7 1. 8 K6.06 Heat exchangers and condensers.......................... 2.1* 2.4*
K6.07 Breakers, relays, and disconnets........................ .
1.8 2.1 ABILITY ,
Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including:
A1.01 CCW flow rate......... ................. ............... 2.8 2.9 A1.02 CCW temperature......................................... 2.9 3.1 A1.03 CCW pressure................... ... .................... 2.7 2.9 A1.04 S u rg e ta n k l e ve l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3.2 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Lc.c e' CCW pump........................................ 3.3 3.6 A2.02 High/ low surge tank level...... ............. .......... 3.2 3.5 A2.03 High/ low CCW temperature................................ 3.0 3.2 A2.04 PRMS alarm...................... ....................... 3.3* 3.5*
A3 Ability to monitor automatic operation of the CCWS, including:
A3.01 Setpoints on instrument signal levels for normal opera-tions, warnings, and trips that are applicable to the CCWS.................................................... 3.2* 3.0 A4 Ability to manually operate and/or monitor in the con-trol room:
1 A4.01 CCW indications and controls............................ 3.3 3.1 i
O K/A catalog 3.10-2
l e >x SYSTEM: 008 Component Cooling Water System (CCWS) v) TASK MODE:
TASK:
010 Startup/ Shutdown Perform lineups of the CCWS Fill the CCWS Fill the CCWS components Start up the CCWS Shut down the CCWS Drain the CCWS (one loop)
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the faiTowing systems:
K1.01 Sources of makeup water................................. 3.0 3.1 K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the CCWS will have on the following:
K4 Knowledge of CCWS design feature (s) and/or interlock (s) which provide for the following:
(O)
K4.01 Operation of the surge tank, including the associated valves and controls..................................... 2.9 2.7 K4.02 Sensing elements for the measurement of flow rates for the total CCW flow rate and for the flow rates to the components.............................................. 2.4* 2.4*
K4.03 Weir design aspect of the surge tank.................... 2.1* 2.7*
K5 Knowledge of the following theoretical concepts as they apply to the CCWS:
K5.01 " Water hammer" and how such might be produced in the CCWS.................................................... 2.2* 2.3*
K5.02 Flow rate and velocity of a liquid and of a gas, including temperature effects and their various units of measure.............................................. 1.7 2.1 K5.03 Purpose of venting components when filling or draining the CCWS................................................ 2.3 2.4 K5.04 Theory of the measurement of flow rate.................. 1.6 1. 8 K6 Knowledge of the applicable performance and design attributes of the following CCWS components:
Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with
'~' operating the CCWS controls including:
x- /
K/A catalog 3.10-3
SYSTEM: 008 Component Cooling Water System (CCWS)
TASK MODE: 010 Startup/ Shutdown Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Effect of loss of instrument and control air on the position of the CCW valves that are air operated........ 3.3* 3.5 A3 Ability to monitor automatic operation of the CCWS, including:
A3.01 Operation of the CCW pumps, including interlocks and th e C CW bo o s te r p ump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2 3.2 A3.02 All flow rate indications and the ability to evaluate the performance of this closed-cycle cooling system..... 3.0 3.1 A3.03 Requirements on and for the CCWS for different condi-ti ons o f the powe r pl ant. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.2 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Filling and draining operations of the CCWS including the proper venting of the components.................... 2.5* 2. 5 A4.02 Throttling of the CCW pump discharge valve.............. 2.7* 2.5*
A4.03 Startup of a CCW pump when the system is shut down...... 2.6* 2.6 A4.04 Normal CCW-header total flow rate and the flow rates to the components cooled by the CCWS.................... 2.7* 2.5*
O K/A catalog 3.10-4
,g SYSTEM: -008 ~ Component Cooling Water System (CCWS)
- } TASK MODE
- 030 Mode Change V
TASK: Add chemical to the CCWS Coordinate bleed and feed of component cooling system-for chemistry control Operate CCWS pumps in different combinations Operate CCW heat exchangers in different combinations Monitor component cooling system operation IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections /or and cause-effect relationships between the CCWS and the following systems:
K1.01 Sources of makeup water to the CCWS..................... 2.9 3.0 K2 Knowledge of bus power supplies to the following:
K2.01 CCW pump, including emergency backup.................... 3.0* 3.2*
K3 Knowledge of the effect that a loss of the CCWS will have on the following:
, /'~'s K3.01 CRDS.................................................... 2.9 3.1 4.2 (v) K3.02 RCPS....................................................4.1 K4 Knowledge of CCWS design feature (s) and/or interlock (s) which provide for the following:
K4.01 CCW pump pressure head and water inventory (capacity of CCWS surge tank)..................................... 2.4 2.5 K4.02 Auxiliary building CCWS isolation. . . . . . . . . . . . . . . . . . . . . . . 2. 3* 2.6*
K4.03 Operation of the CCW swing-bus power supply and its associated breakers and controls........................ 2.6* 2.7*
K4.04 Protection of ion exchange resins from high letdown temperature............................................. 2.3 2.3 K4.05 The " standby" feature for the CCW pumps................. 2.7 2.9 K5 Knowledge of the following theoretical concepts as they apply to the CCW5:
K5.01 The concentration level of a chemical solution; how to change the concentration leve1.......................... 1.6 2.0*
l K5.02 Causes and effects of corrosion on carbon steel and stainless steel; the effects on heat transfer through
! such materials.......................................... 1.6 2.1
! K5.03 Effects on corrosion rate of steels due to corrosion-1 inhibiting chemicals.................................... 1.5 2.1*
r'~s K5.04 Knowledge of which chemicals are used for corrosion 1.6 2.1
, (v) inhibitors in the CCWS..................................
l l
K/A catalog 3.10-5 l
SYSTEM: 008 Component Cooling Water System (CCWS)
TASK MODE: 030 Mode Change Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6 Knowledge of the applicable performance _ design attributes of the following CCWS componet >
K6.01 Valves.......... ... ....... ........ .. ....... 1.9 2.0 K6.02 Sensors and detectors........ .... ... .. ... . . . . . . . . 1. 8 1. 8 K6.03 Controllers and positioners........... .. .. . . . . . 1. 8 1.9 K6.04 Pumps................................... . . . . . . . . . . . . . 1. 9 2.1 K6.05 Motors........... .. .......... ....... . . . . . . . . . . . 1. 7 1.7 K6.06 Heat exchangers and condensers.. ...... . .. . . . . . . . . 1. 9 2.3*
K6.07 Breakers, relays, and disconnects....... .. ............ 1.9 1.9 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including:
A2 Ability to (a) nredict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Calculation of required recirculation time for chemical addition... ............................................ 1.7^ 2.0*
A2.02 Consequences of high or low CCW flow rate and tempera-ture; the flow rate at which the CCW standby pump will start.... ......................... ..... .. .. ..... .. 2.5* 2.8*
A2.03 Effects of shutting (automatically or otherwise) the isolation valves of the letdown cooler.................. 2.5 2.7*
A2.04 Results of excessive exit temperature from the letdown cooler, including the temperature ef fects on ion-exchange resins....... ................................. 2.3 2.8 A3 Ability to monitor automatic operation of the CCWS, including:
A3.01 Control of the electrically operated, automatic isola-tion valves in the CCWS........... ......... ........3.0 3.1 A3.02 Typical CCW pump operating conditions, including vibra-tion and sound levels and motor current.. .... .... ... . 2. 5 2. 5 A3.03 Effects of recirculation within the CCWS. ............. 2.3* 2.2*
A3.04 Automatic actions associated with the CCWS that occur as a result of a safety injection signal... . .... .... 3.6* 3.7*
A3.05 Normal CRDM temperatures..... .......... .. ......... .. 2.4* 2.3 K/A catalog 3.10-6
O SYSTEM: 008 Component Cooling Water System (CCWS) l i TASK MODE: 030 Mode Change d
Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A3.06 CCW pump instruments and their respective sensors, including flow, pressure, oil level, and discharge temperature............................................. 2.9* 3.0 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Remote operation of hand-operated throttle valves to re gu l ate CCW fl ow rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5* 2.5 A4.02 Control of minimum level in the CCWS surge tank......... 2.9* 2.9 A4.03 CCW p ump co ntrol swi tch. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1* 2.8 A4.04 CCW temperature control val ve. . . . . . . . . . . . . . . . . . . . . . . . . . 3. 0* 2.9*
A4.05 Conditions that require the operation of two CCW coolers................................................. 3.1* 3.1 A4.06 CCW pump recirculation valve and its three-way control switch.................................................. 3.0* 2.9*
SYSTEM GENERIC K/As l
\
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.9 3.4
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.5
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.7
- 4. Knowledge of system purpose and/or function. 3.5 3.7 1
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.9* 3.7$
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.7 3.1 l
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.3 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.2 4.0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.6 K/A catalog 3.10-7
SYSTEM: 008 Component Cooling Water System (CCWS)
TASK MODE: 030 Mode Change Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.2
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 4.0
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.9 2.9 Normal plant operations........................................ 2.9 2.9 Plant heatup and startup...................... ........ ...... 2.9 3.0 Plant shutdown and cooldown.................................... 2.9 3.1 O
l l
l i
O K/A catalog 3.10-8
( i 1
/
~#
SYSTEM: 075 Circulating Water System TASK MODE: 000 Generic TASK: Perform circulating water / service water systems test Remove marine growth from main condenser circulating water passages IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the circulating water system and the following systems:
Kl.01 SWS..................................................... 2.5 2.5 K1.02 Li quid radwaste di scharge. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.1 K1.03 Condenser............................................... 1. 9 1.9 K1.04 S/GB.................................................... 1.7 1.8 Kl.05 MRSS and SD5....................... .................... 2.0 1. 9 Kl.06 Cooling towers.......................................... 1.9* 1.7*
K1.07 Reci rcul ati on spray sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2* 2.1*
Kl.08 Emergency / essential SWS................................. 3.2* 3.2*
K1.09 Vacuum priming.......................................... 1.5 1.4
< x (v ) K2 Knowledge of bus power supplies to the following:
K2.01 Circulating water pumps................................. 1.6 1. 7 K2.02 M0Vs.................................................... 1.7 1.7 K2.03 Emergency / essential SWS pumps........................... 2.6* 2.7*
K2.04 Lube oil pumps......................................... 1.4* 1.4*
K3 Knowledge of the effect that a loss of the circulating water system will have on the following:
K3.01 SWS.................................................... 2.3 2.6 K3.02 Main condenser.......................................... 2.1 2.4 K3.03 SD5.....................................................2.3 2.4 K3.04 MT/G............................. ...................... 1.9 2.1 K3.05 Reci rcul ation spray sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1* 2.3*
K3.06 Plant efficiency........................................ 1.5 1.7 K4 Knowledge of circulating water system design feature (s) and interlock (s) which provide for the following:
K4.01 Heatsink...............................................2.5 2.8 l K5 Knowledge of the following theoretical concepts as they I apply to the circulating water system:
,a
( ) K5.01 Definition and units of measure of a vacuum............. 1.4 1. 5 l K5.02 Purpose of a vacuum on the main condenser................ 1. 5 1. 5 K/A catalog 3.10-9 b
SYSTEM: 075 Circulating Water System TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.03 Factors that affect main condenser vacuum... .. .. . . 1. 5 1. 6 K5.04 . Principle of operation of the main condenser... ... .... 1. 4 1.6 K5.05 Principle of operation of the cooling towers.. . .. .... 1.6* 1.9*
K5.06 Principle of cooling by evaporation...... ..... . ..... 1.4 1. 6 K5.07 Relationship of seawater temperature to marine growth... 1.4* 1.6*
K6 Knowledge of the applicable performance and design attributes of the following circulating water system components:
K6.01 Valves. ........ . . .. ....... . .. ............... 1. 5 1.6 K6.02 Sensors and detectors........ ........ ...... ..... ... 1. 5 1. 5 K6.03 Controllers and positioners... ........ ... ..... ..... 1.5 1.5 K6.04 Pumps.................. . ... . .. . ... . ...... . 1. 5 1. 6 K6.05 Motors................. .... ........... .... . .. .... 1.5 1. 5 K6.06 Breakers, relays, and disconnects........ ... .. . . . 1. 5 1.5 ABILITY Al Ability to predict and/or mnnitor changes in parameters (to prevent exceeding design limits) associated with operating the circulating water system controls including:
A1.01 Cooling water temperature. ........ .......... . . . . . . 1. 8 2.0 A1.02 Intake levels. .. ...................... ............. 2.2* 2.5 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use proce-dures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Loss of intake structure.... . .. .. ..... .. . 3.0* 3.2 A2.02 Loss of circulating water pumps.. ..... . ......... . 2.5 2.7 A2.03 Safety features and relationship between condenser vacuum, turbine trip, and steam dump........ .. ..... . 2.5 2.7*
A3 Ability to monitor automatic operation of the circu-lating water system, including:
A3.01 Autcmatic isolation of circulating water valves..... . . 2.1* 2.1*
A3.02 Alternate flow paths for circulating water. . . . . ..... 2.3* 2.3*
A4 Ability to manually operate and/or monitor in the con-trol room:
K/A catalog 3.10-10
. SYSTEM: 075 Circulating Water System
-TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A4.01' Emergency / essential SWS pumps............................ 3.2* 3.2*
A4.02 Circulating water pump.................................. 2.2* 12 . 3 A4.03 The circulating water system, such that the correct number of pumps are operating for all plant power levels.................................................. 2.3* 2.2 A4.04 Air eductor system...................................... 1.8* 1.8*
l l
l l
l l
I l
i i
K/A catalog 3.10-11
SYSTEM: 075 Circulating Water System TASK MODE: 010 Startup/ Shutdown TASK: Perform lineups of the circulating water system Start up the circulating water system Monitor circulating water system operations Shut down the circulating water system IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the circulating water system and the following systems:
K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the circulating water system will have on the following:
K4 Knowledge of circulating water system design feature (s) and/or interlock (s) which provide for the following:
K4.01 Interlocks between circulating water system pumps and discharge va1ve.................................. ...... 2.0* 2.1*
K4.02 Interlocks between circulating water system pumps and cooling tower pumps................ .... ............... 1.7* 2.1*
K5 Knowledge of the following theoretical concepts as they apply to the circulating water system:
K5.01 Purpose of the vacuum priming system............... .. . 1.6 1. 6 K6 Knowledge of the applicable performance and design attributes of the following circulating water system components:
ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the circulating water system controls including:
A1.01 Pump amperage (normal range and limitations).... ....... 1.7 1.7 A1.02 Pump oil levels and seal flows (normal range and limitations).................. ............ ............ 1.7 1.6 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use proce-dures to correct, control, or mitigate the consequences of those malfunctions or operations:
K/A catalog 3.10-12
-i [ SYSTEM: 075 Circulating Water System TASK MODE: 010 Startup/ Shutdown x
Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A3 Ability to monitor automatic operation of the circu-lating water system, including:
A3.01 Pump amperage (normal range and limitations)............ 1.7 1.7 A3.02 Pump oil levels and seal flows (normal range and limitations)............................................ 1.7 1.6 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 The circulating water system, to maintain a vacuum in the main condenser during shutdown as long as is n e c e s s a ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3* 2.3 A4.02 Water box vacuum priming isolation valves, control switches, and indicators................................ 1.8* 1.7*
A4.03 Vacuum priming tank / priming compressor controller....... 1.7* 1.6*
A4.04 Gland seal water supply system.......................... 1.6 1.6 A4.05 Circulating water box inlet and outlet valves........... 1.9* 1.8*
c A4.06 Circulating water pump and circulating pump discharge
' valve................................................... 1.9 1.8 v
K/A catalog 3.10-13
SYSTEM: 075 Circulating Water System TASK MODE: 020 Normal Operations TASK: Operate the water box priming subsystem Monitor water box priming subsystem operation Monitor condenser cleaning subsystem operation Start up and shut down the de-icing subsystem Operate circulating water pumps in different combinations Isolate a water box (salt water operations)
Restore flow to a water box Operate the vacuum priming system on the circulating water system vacuun loop Operate the cooling towers Isolate a water box (fresh water)
Operate the cooling tower blowdown subsystem Operate cooling tower makeup subsystem IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the circulating water system and the following systems:
K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the circulating water system will have on the following:
K3.01 ESFAS................................................... 3.4* 3.5*
K4 Knowledge of circulating water system design feature (s) and/or interlock (s) which provide for the following:
K4.01 Automatic pickup of backup lube oil pumps (ac and dc)... 1.7* 1.9*
K4.02 Operation of condenser tube cleaning system............. 1.5* 1. 5
- K4.03 Travel i ng sc reen operati on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 6 1. 8 K4.04 Relationship between water box inlet valve position and circulating pump logic (including switching time required to close water box inlet valve switch)......... 1.7* 1.7^
K5 Knowledge of the following theoretical concepts as they apply to the circulating water system:
K5.01 Relationship between circulating water conductivity and corrosion............................................... 1.5 1.7 K5.02 Damage to piping and components from hydraulic shock.... 1.7 1.8 K6 Knowledge of the applicable performance and design attributes of the following circulating water system compor.ents:
O K/A catalog 3.10-14
3 SYSTEM: 075 Circulating Water System TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the circulating water system controls including:
A1.01 Lube oil temperature and pressure. . . . . . . . . . . . . . . . . . . . . . . 1. 5 1. 6 A1.02 Circulating water temperature (inlet and outlet)....... 1.7 1.7 A1.03 Circulating water pump motor current and pump discharge pressure................................................ 1.5 1. 5 A1.04 Circulating water makeup pump motor current (within limits)................................................. 1.6* 1.6*
A1.05 Normal conditions for pump oil levels and seal water pressure................................................ 1.4 1. 5 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use proce-dures to correct, control, or mitigate the consequences
'N of those malfunctions or operations:
A2.01 Effects of extremes in ambient temperature on cooling tower operation.............................. .......... 1.8* 2.1*
A2.02 Potential damage to condenser from high discharge pres-sures of circulating water pump......................... 1.6 1.6 A2.03 Operating two circulating water pumps when power level exceeds 50% of pl ant rating. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7* 1.8*
A2.04 Potential effects of improper cooling water system flow. 1.7 1.7 A2.05 Ice buildup on intake structure......................... 2.0* 2.0*
A2.06 Operation of amertap ball collector flaps and screens in normal, backwash, and emergency backwash modes....... 1.7* 1.7*
A2.07 Automatic startup mode of water box priming pumps rela-tive to specified minimum vacuum........................ 1.5* 1.6*
A2.08 Time required for fill of piping by induction of water into circulating system using vacuum system............. 1.5* 1.6*
A3 Ability to monitor automatic operation of the circu-lating water system, including:
A3.01 Verification that pump discharge valve closes when ci rcul ating water pump stops. . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7 1. 6 A3.02 Normal and abnormal co'. lector flap differential pres-sures and setpoints..................................... 1.6* 1.5*
A3.03 Makeup flow control valve controller and indicator...... 1.7* 1. 6
- 7-i
( A4 Ability to manually operate and/or monitor in the con-trol room:
K/A catalog 3.10-15
f SYSTEM: 075 Circulating Water System TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A4.01 Startup and shutdown of the circulating water pump...... 1.9 1. 9 A4.02 Discharge valve interlock system........................ 1.8* 1.7*
A4.03 Cooling tower aperations............................. .. 1.8* 1.7*
A4.04 Lube oil pumps for ci rculating water pump. . . . . . . . . . . . . . . 1. 5* 1.7*
A4.05 Operation of the vacuum priming system.................. 1.4 1. 5 A4.06 Traveling screens in manual operation................... 1.6 1.6 A4.07 Isolation of a water box................................ 1.5 1.5 A4.08 Operation of the circulating water bay sluice gate...... 1.6* 1.7*
A4.09 De-icing valve.......................................... 1.6* 1.7*
A4.10 Blowout preventers...................................... 1.7* 1.8*
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.3* 2.5
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.2* 2.8*
- 3. Knowledge of which events related to system operation / status should be reported. 2.2* 3.1*
- 4. Knowledge of system purpose and/or function. 2.5* 2.6
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.4* 3.3*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.0* 2.2*
- 7. Ability to locate, explain, and apply all limits and precau-tions. 2.5 2.8
- 8. Ability to recognize indications for system operating param-eters which are entry level conditions for Technical Specifications. 2.6* 3.3
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 2.7 2.9
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.2* 3.4*
K/A catalog 3.10-16
.,-- SYSTEM: 075 Circulating Water System
( TASK MODE: 020 Normal Operations Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of' system. components or controls. 3.0* 3.1*
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.1 2.3 Normal plant operations........................................ 2.1 2.2 Plant heatup and startup....................................... 2.1 2.2 Plant shutdown and cooldown.................................... 2.1 2.1 l
l I
L L
K/A catalog 3.10-17
t V
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 026 Loss of Component Cooling Water (CCW) 062 Loss of Nuclear Service Water IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the Loss of CCW/ Loss of Nuclear Service Water emergency tasks:
EK2 Knowledge of the following components:
! EK3 Knowledge of the bases or reasons for the following:
EK3.01 The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCW/
nuclear service water coolers........................... 3.2* 3.5*
EK3.02 The automatic actions (alignments) within the CCWS/
nuclear service water resulting from the actuation of the ESFAS............................................... 3.6 3.9 i
C/ EK3.03 Guidance actions contained in E0P for Loss of CCW/
nuclear service water................................... 4.0 4.2 EK3.04 Effect on the CCW/ nuclear service water dischaege flow heade r o f a l o s s o f CCW. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 5 3.7 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 CCW/ nuclear service water temperature indications....... 3.1 3.1 EA1.02 Loads on the CCWS in the control room................... 3.2 3.3 EA1.03 SWS as a backup to the CCWS............................. 3.6* 3.6*
EA1.04 CRDM high-temperature alarm system...................... 2.7* 2.8 EA1.05 The CCWS surge tank, including level control and level alarms, and radiation alarm............................. 3.1 3.1 EA1.06 Control of flow rates to components cooled by the CCWS.. 2.9 2.9 EA1.07 Flow rates to the components and systems that are serv-iced by the CCWS; interactions among the components..... 2.9 3.0 EA2 Ability to determine or interpret:
EA2.01 Location of a leak in the CCWS.......................... 2.9 3.5 EA2.02 The cause of possible CCW loss................ ......... 2.9 3.6 b
K/A catalog 3.10-19
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 026 Loss of Component Cooling Water (CCW) 062 Loss of Nuclear Service Water IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.03 The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition...................................... 2.6 2.9 EA2.04 The normal values and upper limits for the temperatures of the components cooled by CCW......................... 2.5 2.9*
EA2.05 The normal values for CCW-header flow rate and the flow rates to the components cooled by the CCWS.............. 2.4* 2.5*
EA2.06 The length of time after the loss of CCW flow to a com-ponent before that component may be damaged............. 2.8* 3.1*
SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.3
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.5
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8 3.7
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.8* 2.9
- 7. Ability to locate, explain, and apply all limits and precau-l tions. 3.3 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.2 4.1
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 3.5
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4,0 4.2
- 11. Ability to perform those actions, without reference to proce-dures for all casualties which require immediate operation of system components or controls. 3.9 4.1 O
K/A catalog 3.10-20
I O
Indirect Radioactivity Release Control Systems and Malfunctions O
g l
=
8 I 9 i
e.
4 O
l ljI
\
SYSTEM: 029 Containment Purge System (CPS)
TASK MODE: 000 Generic TASK: Perform lineups of the CPS Start up the CPS Shut down the CPS Vent the containment building Initiate a containment radiation signal IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the CPS and the following systems:
Kl.01 Gaseous radiation release monitors............... ..... 3.4 3.7 Kl.02 Containment radiation monitor...................... .... 3.3 3.6 K1.03 Engineered safeguards................................... 3.6 3.8 K1.04 Purge system............................................ 3.0? 3.1?
K1.05 Containment air cleanup and recirculations system....... 2.9* 3.1*
/'~'N K2 Knowledge of bus power supplies to the following:
(#)
K2.01 Purge fans.............................................. 2.1 2.3*
K2.02 Recirculation fans...................................... 2.0 2.4*
K2.03 Purge exhaust radiation monitors........................ 2.3* 2.7*
K2.04 Purge va1ves............................................ 2.1* 2.3 K2.05 Supply air heaters...................................... 1.7 1. 9 I l
K3 '
Knowledge of the effect that a loss of the CPS will have on the following: ,
K3.01 Containment parameters.................................. 2.9 3.1 K3.02 Containment entry....................................... 2.9* 3.5*
K4 Knowledge of CPS design feature (s) and/or interlock (s) which provide for the following:
i l
K4.01 Use of filters for purging to the atmosphere............ 2.4 2.9 l K4.02 Negative pressure in containment........................ 2.9 3.1 K4.03 Automatic purge isolation............................... 3.2* 3.5 K4.04 Prevention of damage to fans from lack of flow rate. . .. . 2.4 2.6 K4.05 Temperature limits on dampers........................... 2.0* 2.1*
K5 Knowledge of the following theoretical concepts as they apply to the CPS:
A
( I K5.01 Maximum concentration permissible....................... 2.4 2.9*
\'
K5.02 Dilution................................................ 2. 3 2.8 K/A catalog 3.11-1
SYSTEM: 029 Containment Purge System (CPS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6 Knowledge of the applicable performance and design attributes of the following CPS components:
K6.01 Valves.................................... .......... .. 1.9 2.0 K6.02 Sensors and detectors................................. . 2.1* 2.3*
K6.03 Controllers and positioners.... ...... ......... .. . 1. 9 2.1 K6.04 Pumps.................................... . . . . . . . . . . . . . . 1. 6 1.9 K6.05 Motors............................................. .... 1.6 1.9 K6.06 Heat exchangers and condensers......................... 1.8 1. 9 K6.07 Breakers, relays, and disconnects........ ............. 1.8 1.9 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CPS controls including:
A1.01 Supply air temperature... ...................... ....... 1.9 2.1 A1.02 Radiation 1evels............................... ... .... 3.4 3.7 A1.03 Containment pressure, temperature, and humidity......... 3.0* 3.3*
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Maintenance or other activity taking place inside containment............... .... ........................ 2.9 3.6 A2.02 Continuance of outdoor temperature inversion. ...... ... 2.2 2.9 A2.03 Startup operations and the associated required valve lineups.............. . ................. .... . ... 2.7 3.1 A2.04 Health physics sampling of containment atmosphere... .. 2.5* 3.2*
A3 Ability to monitor automatic operation of the CPS, including:
A3.01 CPS isolation.. .... ........ ..... . . . .... .... . 3.8 4.0 A4 Ability to manually operate and/or monitor in the control room:
A4.01 Containment purge flow rate........ ... . . ... .. 2.5 2.5 A4.02 Outside atmospheric conditions (prior to purge). . .. .. 2.2 2.5 A4.03 Inlet filtration and heating system. .... ... . . 1. 7 1.8 A4.04 Containment evacuation signal.. ... . . . .. . 3.5 3. 6 K/A catalog 3.11-2
/~3l
(
SYSTEM:
TASK MODE:
029 000 Containment Purge System (CPS)
Generic
'O Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.7 3.1
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.1
- 3. Knowledge of which events related to system operation / status should be reported. 2.5* 3.3*
- 4. Knowledge of system purpose and/or function. 3.3 3.5
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.9* 3.8*
- 6. Ability to locate and operate components, using local con-trols (outside the control room). 2.4 2.6
- 7. Ability to locate, explain, and apply all limits and precau-
\ tions. 3.2 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.2 4.0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 3.5
- 10. Ability to recognize abnormal indications foi system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.1
- 11. Ability 'to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 4.0
- 12. Ability to perform specific system and integrated plant operations during:
Controlled plant. load change....... ........................... 2.3* 2.3*
N o rma l p l a n t op e.ra t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 3
- 2.3*
Plant heatop and startup....................................... 2.4 2.5*
Plant shutdown and cooldown.................................... 2.7 2.8*
a .
K/A catalog 3.11-3
( )
\ /
%,/
SYSTEM: 033 Spent Fuel Pool Cooling System (SFPCS)
TASK MODE: 000 Generic TASK: Fill the spent fuel pools Operate the SFPCS between refueling pool and spent fuel pool Perform BWST purification using filter /demineralizer Lower refueling pool level (fuel transfer canal)
Perform decay heat removal using the SFPCS IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the SFPCS and the following systems:
K1.01 RCS..................................................... 2.4 2.5 K1.02 RHRS.................................................... 2.5 2.7 K1.03 SI5..................................................... 2.4 2.5 K1.04 BWST.................................................... 2.4 2.4 K1.05 RWST.................................................... 2.7* 2.8*
'~'
Kl.06 Boric acid storage tank................................. 2.2 2.3 K1.07 Emergency makeup water systems.......... ............... 2.4 2. 5 K2 Knowledge of bus power supplies to the following:
K2.01 SFPCS components........................................ 1.9 2.1 K3 Knowledge of the effect that a loss of the SFPCS will have on the following:
K3.01 Area ventilation systems................................ 2.6 3.1 K3.02 Area and ventilation radiation monitoring systems....... 2.8 3.2 K3.03 Spent fuel temperature.................................. 3.0 3.3 K4 Knowledge of SFPCS design feature (s) and/or inter-lock (s) which provide for the following:
K4.01 Maintenance of spent fuel leve1......................... 2.9 3.2 K4.02 Maintenance of spent fuel cleanliness................... 2.5 2.7 K4.03 Anti-siphon devices........................,............ 2.6 2.9 K4.04 Maintenance of spent fuel pool radiation................ 2.7? 2.9?
K4.05 Adequate SDM (boron concentration)...................... 3.1 3.3 K5 Knowledge of the following theoretical concepts as they apply to the SFPCS:
s
)
K5.01 K5.02 P ump t h e o ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Heat transfer..... .....................................
- 1. 6 1.7 1.9 1.9 K5.03 D/P detector theo ry of 0PS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 5 1.6 K/A catalog 3.11-5
SYSTEM: 033 Spent Fuel Pool Cooling System (SFPCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K5.04 K eff............ ........... ........................2.1 2.3*
K5.05 Decay heat.......................................... . . . 2.1 2.3 K5.06 Shielding........................ ........ ............. 2.1 2.5 K6 Knowledge of the applicable performance and design attributes of the following SFPCS components:
K6.01 Pumps.. . .................... ......... . . . . . . . . . . . . . . 1. 7 1.9 K6.02 Heat exchangers................. .......... ............ 1.8 1.9 K6.03 Valves........................ .........................1.7 1. 7 K6.04 Motors....................... .........................1.7 1. 7 K6.05 Pressure and pressure detectors. ...... ....... . . . . . . 1. 7 1.7 K6.06 Temperature sensors..................................... 1.8 1.8 K6.07 Filters and demineralizers...................... ....... 1.7 1.8 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SFPCS controls including:
A1.01 Spent fuel pool water level......... ................... 2.7 3.3 A1.02 Radiation monitoring systems... ........ ............... 2.8 3.3 A1.03 SFPCS controls and sensors................. . .......... 2.4 2.7 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the SFPCS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Inadequate SDM.............. ........................... 3.0 3.5 A2.02 Loss of SFPCS........... ......... ...... .... ........ 2.7 3.0 A2.03 Abnormal spent fuel pool water level or loss of water level......... ................. ......... ..... ..... 3.1 3.5 A3 Ability to monitor automatic operation of the SFPCS, including:
A3.01 Temperature control valves..... ... ............. ..... 2.5* 2.7*
A3.02 Spent fuel leak or rupture.... .. ... ................. 2.9 3.1 A4 Ability to manually operate and monitor in the control room:
A4.01 SFPCS pumps.... ........ . ... ................... .. 2.4* 2.3*
A4.02 SFPCS valves...... ........... . . . .. ...... ....... 2.3* 2.1*
K/A catalog 3.11-6
(3 SYSTEM: 033 Spent Fuel Pool Cooling System (SFPCS) i TASK MODE: 000 Generic i
'J Tasks as noted previously.
IMPORTANCE K/A N0. ABILITY R0 SRO A4.03 Support systems for fill and transfer of SFPCS water.... 2.3 2.4 A5 Ability to direct operations of the following:
AS.01 S F P C S p ump s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4 2.9 A5.02 SFPCS valves............................................ 2.4 2.8 AS.03 Support systems for fill and transfer of SFPCS water.... 2.4 2.9 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.8 3.1
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.3* 3.2
- 3. Knowledge of which events related to system operation / status should be reported. 2.3* 3.4
(%
(j 4. Knowledge of system purpose and/or function. 3.1 3.5
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8* 3.5*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2. 4 2.9
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.0 3.5
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.0 3.9
- 9. ' Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.1 3.3 1 10.- Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.7 3.9
- 11. Ability to perform those actions, without reference to proce-O dure, for all casualties which require immediate operation of 3.8 system components or controls. 3.6 K/A catalog 3.11-7
SYSTEM: 033 Spent Fuel Pool Cooling System (SFPCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................. ................. 2.1* 2.2 Normal plant operations................. .... ................ 2.1* 2.2 Plant heatup and startup................................ . . . . . . 2 . 1* 2.2 Plant shutdown and cooldown... ...... ..... ............... ... 2.1* 2.2 O
O K/A catalog 3.11-8
b SYSTEM: 034 Fuel Handling Equipment System (FHES)
TASK MODE: 000 Generic TASK: Operate the spent fuel handling machine / bridge / platform crane Operate the new fuel elevator Operate the refueling machine / main fuel handling bridge (fuel element change)
Operate the control rod change machine / fuel handling bridge / reactor building crane (control rod change)
Operate the fuel transfer system / fuel transfer carriages and upenders Operate the auxiliary fuel handling bridge manipulator crane Operate the auxiliary building overhead crane (general load handling)
What if a spent fuel assembly is dropped in contJ nment?
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the FHES and the following systems:
Kl.01 RCS..................................................... 2.5 3.2 (m) Kl.02 K1.03 RHRS.................................................... 2.5 3.2 2.1 2.7*
(V K1.04 CVCS....................................................
NIS..................................................... 2.6 3.5 Kl.05 Shutdown monitor........................................ 2.5* 3.4*
Kl.06 SFPCS................................................... 2.4 3.0*
K2 Knowledge of bus power supplies to the following:
K2.01 All fuel handling equipment (e.g., cranes, fuel eleva- ;
tors, handling bridge).................................. 1.5 2.0 K2.02 Airsupp1y.............................................. 1. 6 1.9 K2.03 Area monitors........................................... 1.9 2.2 K3 Knowledge of the effect that a loss of the FHES will have on the following:
K3.01 Containment ventilation................................. 2.4* 2.9*
K4 Knowledge of FHES design feature (s) and/or interlock (s) which provide for the following:
K4.01 Fuel protection from binding and dropping............... 2.6 3.4 K4.02 Fuel movement........................................... 2.5 3.3 K4.03 Ove rl oad protecti on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 3.3 K5 Knowledge of the following theoretical concepts as they (A
v) apply to the FHES:
KS.01 General principles of mechanical lifting................ 1.7? 2.1?
K/A catalog 3.11-9
SYSTEM: 034 Fuel Handling Equipment System (FHES)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K5.02 Limiting of load................. .................... . 2.0 2.6 K5.03 Residual heat removal; decay............................ 2.2 2.7 K6 Knowledge of the applicable performance and design attributes of the following FHES components:
K6.01 Fuel handling equipment................................. 2.1 3.0 K6.02 Radiation monitoring systems............................ 2.6 3.3 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the FHES controls including:
A1.01 Load limits.......................... ..... ........ .. 2.4 3.2 A1.02 Water level in the refueling canal...................... 2.9 3.7 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the FHES; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Dropped fuel element.................................... 3.6 4.4 A2.02 Dropped cask......... .................................. 3.4 3.9 A2.03 Mispositioned fuel element................. ..... ..... 3.3 4.0 A3 Ability to monitor automatic operation of the FHES, including:
A3.01 Travel limits........................................... 2.5* 3.1 A3.02 Load limits................ ................... ........ 2.5* 3.1 A3.03 High flux at shutdown................. ..... ........... 2.9 3.3 A4 Ability to manually operate and/or monitor in tha con-trol room:
A4.01 Radiation levels. ............................ ......... 3.3 3.7 A4.02 Neutron levels...................... .. ............. .. 3.5 3.9 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.7 3.2 K/A catalog 3.11-10
T' SYSTEM: 034 Fuel Handling Equipment System (FHES)
T['/
w TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.3* 3.0*
- 3. Knowledge of which events related to system operation / status should be reported. 2.3* 3.2*
- 4. Knowledge of system purpose and/or function. 3.1* 3.5*
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8* 3.7*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.7 3.3
- 7. Ability to locate, explain, and apply all limits and precau-tions. 2.9 3.7
[m) 8. Ability to recognize indications for system operating param-
\d eters, which are entry level conditions for Technical Specifications. 2.9 4.0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.1 3.5
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.7 4.1
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 2.0* 4.1
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.0* 1.9*
Normal plant operations........................................ 2.0* 1.9*
Plant heatup and startup....................................... 2.0* 1.9*
Plant shutdown and coo 1down.................................... 2.2* 2.1*
A K/A catalog 3.11-11
t \
\
v}
SYSTEM: 068 Liquid Radwaste System (LRS)
TASK MODE: 000 Generic
. TASK: Perform lineups of the reactor coolant waste (RCW) system (clean radwaste system)
Perform transfer operations from an RCW holdup / receiver tank Perform transfer operations from a reactor coolant monitor tank Perform transfer operations from reactor coolant drain / pressurizer relief tank.
Monitor the RCW/ boron recovery system Start up the RCW/ boron evaporator Transfer waste / boron recovery evaporator concentrates Shut down the RCW/ boron recovery evaporator Recirculate distillate through the polishing demineralizer Perform transfer of distillate to primary water storage tank IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the LRS and the following systems:
k ')
K1.01 K1.02 RCS and CVCS............................................
Waste gas vent header...................................
2.4 2.5 2.6 2.6 Kl.03 PRT..................................................... 2.2 2.3 K1.04 Reactor drain tank...................................... 2.4* 2.5*
K1.05 CWS/CCWS................................................ 2.3 2.6 K1.06 Boron recovery equipment................................ 2.1* 2.3*
K1.07 Sources of liquid wastes for LRS. . . . . . . . . . . . . . . . . . . . . . . . 2. 7 2.9 Kl.08 Au x i l i a ry s te am . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9
- 2.2*
K2 Knowledge of bus power supplies to the following:
K2.01 Transfer pump........................................... 1.7* 1.9 K2.02 Automatic isolation valves.............................. 1.9 2.1 K2.03 Radiation monitors...................................... 2.1 2.2 K3 Knowledge of the effect that a loss of the LRS will have on the following:
K3.01 CVCS.................................................... 2.2 2.4 K3.02 WGDS.................................................... 2.1 2.4 K4 Knowledge of LRS design feature (s) and/or interlock (s) which provide for the following:
'~
/' K4.01 Safety and environmentai precautions for handling hot,
( ,%/ acidic, and radioactive liquids......................... 3.4 4.1 l
K/A catalog ~ 3.11-13 1
SYSTEM: 068 Liquid Radwaste System (LRS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5 Knowledge of the following theoretical concepts as they apply to the LRS:
K5.01 Thermal stress on equipment. . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7 2.2*
K5.02 Relationships between temperature and pressure of a wa t e r- b a s e d f 1 u i d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 5 1.9 K5.03 Units of radiation, dose, and dose rate.... ............ 2.6 2. 6 K5.04 Biological hazards of radiation and the resulting goal of ALARA. .................... .................. ...... 3.2 3.5 K5.05 Relationship between evaporator reboiler steam pressure and the heatup rate........... . ........ . . . . . . . . . . . 1. 7 1.9 K5.06 Evaporation-condensation cycle of distilling units...... 1.6* 1.8*
K6 Knowledge of the applicable performance and design attributes of the following LRS components:
K6.01 Filters.................................. ........ .... 1.7 1.9 K6.02 Demineralizers and ion exchangers................. ..... 1.9 2.0 K6.03 Boron recovery evaporator... ...... ... . ...... ....... 1.9 1.9 K6.04 Valves................................ .. .............. 1.8 1. 9 K6.05 Pumps................... ..............................1.7 1. 8 K6.06 Controllers and positioners.. ........... ........ ..... 1.7 1.7 K6.07 Sensors and detectors. .............. .................. 1.9 1.9 K6.08 Breakers, relays, and disconnects.... ................1.6 1.7 K6.09 Miscellaneous liquid radiation waste drain tanks and waste holdup tanks.............. . ........ ............ 1.9 2.1 K6.10 Radiation monitors...... ... . .... ......... ....... .. 2.5 2.9 K6.11 Waste evaporators........ ............................1.8 2.1 ABILITY ,
Al Ability to predict and/or monitor changes in param-eters (to prevent exceeding design limits) associated with operating the LRS controls including:
A1.01 Waste coolant monitor tank..... .... ... .. ........... 2.2* 2.5*
A1.02 Evaporator pressure control....... ..... .. .. ..... . 2.2* 2.3*
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the LRS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 A boric-acid " freeze". .... .. . .. ........ ... ... .. 2.3? 2.2?
A2.02 Lack of tank recirculation prior to release....... .... 2.7* 2.8*
K/A catalog 3.11-14
,-~'s SYSTEM: 068 Liquid Radwaste System (LRS)
( ) TASK MODE: 000 Generic
'N_/
Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A2.03 Insufficient sampling frequency of the boric acid in the evaporator bottoms.................................. 2.5* 2.6*
A2.04 Failure of automatic isolation.......................... 3.3 3.3 A3 Ability to monitor automatic operation of the LRS, including:
A3.01 Evaporator pressure control............................. 2.5* 2.4*
A3.02 Automatic isolation..................................... 3.6 3.6 A4 Ability to manually operate and monitor in the control room:
A4.01 Control board for boron recovery........................ 2.7* 2.4*
A4.02 Remote radwaste release................................. 3.2* 3.1*
A4.03 Stoppage of release i f limits exceeded. . . . . . . . . . . . . . . . . . 3. 9 3.8 A4.04 Automatic isolation..................................... 3.8 3.7 SYSTEM GENERIC K/As
()
1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.7 3.1*
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.2
- 3. Knowledge of which events related to system operation / status should be reported. 2.6* 3.4
- 4. Knowledge of system purpose and/or function. 3.1 3.3
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 3.1* 3.9*
- 6. Ability to locate and operate components, using local controls
~
(outside the control room). 2.4 2.8
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.3 3.8
- 8. Ability'to recognize indications for system operating param-eters, which are entry level conditions for Technical
( Specifications. 3.4 4.1 b)
K/A catalog 3.11-15
SYSTEM: 068 Liquid Radwaste System (LRS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.5
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.2
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 4.1
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.4 2.5 Normal plant operations........................................ 2.4 2. 5 Plant heatup and startup...... .............. ................. 2.5 2.6 Plant shutdown and cooldown. ................................. 2.4 2.5 0
l l
9 K/A catalog 3.11-16
n lV \
SYSTEM: 029 Containment Purge System (CPS)
TASK MODE: 000 Generic TASK: Perform lineups of the CPS Start up the CPS Shut down the CPS Vent the containment building Initiate a containment radiation signal IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the CPS and the following systems:
- K1.01 Gaseous radiation release monitors...................... 3.4 3.7 K1.02 Containment radiation monitor........................... 3.3 3.6 Kl.03 Engineered safeguards.'.................................. 3.6 3.8 K1.04 Purge system............................................ 3.0? 3.1?
K1.05 Containment air cleanup and recirculations system....... 2.9* 3.1*
K2 Knowledge of bus power supplies to the following:
K2.01 Purge fans.............................................. 2.1 2.3*
K2.02 Recirculation fans...................................... 2.0 2.4*
K2.03 Purge exhaust radiation monitors........................ 2.3* 2.7*
K2.04 Purge valves............................................ 2.1* 2.3 K2.05 Supply air heaters...................................... 1.7 1.9 K3 Knowledge of the effect that a loss of the CPS will have on the following:
K3.01 Containment parameters.................................. 2.9 3.1 K3.02 Containment entry....................................... 2.9* 3.5*
K4 Knowledge of CPS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Use of filters for purging to the atmosphere............ 2.4 2.9 K4.02 Negative pressure in containment........................ 2.9 3.1 K4.03 Automatic purge isolation............................... 3.2* 3. 5 K4.04 Prevention of damage to fans from lack of flow rate. . . .. 2.4 2.6 K4.05 Temperature limits on dampers........................... 2.0* 2.1*
K5 Knowledge of the following theoretical concepts as they apply to the CPS:
t ,O t K5.01 Maximum concentration permissible....................... 2.4 2.9*
K5.02 Dilution................................................ 2.3 2.8 K/A catalog 3.11-1
SYSTEM: 029 Containment Purge System (CPS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K6 Knowledge of the applicable performance and design attributes of the following CPS components:
K6.01 Valves.... ............................................. 1.9 2.0 K6.02 Sensors and detectors... ............................ .. 2.1* 2.3*
K6.03 Controllers and positioners.......................... . . 1.9 2.1 K6.04 Pumps......................................... ......... 1.6 1.9
, K6.05 Motors.................................................. 1.6 1.9 K6.06 Heat exchangers and condensers....................... .. 1.8 1.9 K6.07 Breakers, relays, and disconnects....................... 1.8 1.9 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CPS controls including:
A1.01 Supply air temperature.................................. 1.9 2.1 A1.02 Radiation 1evels........................................ 3.4 3.7 A1.03 Containment pressure, temperature, and humidity......... 3.0* 3.3*
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Maintenance or other activity taking place inside containment.... ................... ................ .. 2.9 3.6 A2.02 Continuance of outdoor temperature inversion...... . 2.2 2.9 A2.03 Startup operations and the associated required valve lineups.. ... .. ............................... . .. 2.7 3.1 A2.04 Health physics sampling of containment atmosphere. . .. 2.5* 3.2*
A3 Ability to monitor automatic operation of the CPS, including:
A3.01 CPS isolation... ... ..... . ...... . ....... .. . 3.8 4.0 A4 Ability to manually operate and/or monitor in the control room:
A4.01 Containment purge flow rate.. . ... . . ... .. . 2.5 2.5 A4.02 Outside atmospheric conditions (prior to purge).... . 2.2 2.5 A4.03 Inlet filtration and heating system.... . ... .. 1. 7 1.8 A4.04 Containment evacuation signal. ... ..... . . .. 3.5 3.6 K/A catalog 3.11-2
"'s SYSTEM: 029 Containment Purge System (CPS)
[Q TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.7 3.1
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.1
- 3. Knowledge of which events related to system operation / status should be reported. 2.5* 3.3*
- 4. Knowledge of system purpose and/or function. 3. 3 3.5
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.9* 3.8*
- 6. Ability to locate and operate components, using local con-trols (outside the control room). 2.4 2. 6
,m
(
- 7. Ability to locate, explain, and apply all limits and precau-V} tions. 3.2 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.2 4.0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 3.5
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.1
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 4.0
- 12. Ability to perform specific system and integrated plant operations during:
Controlled plant. load change................................... 2.3* 2.3*
Normal plant operations........................................ 2.3* 2.3*
Plant heatup and startup....................................... 2.4 2.5*
Plant shutdown and c,ooldown.................................... 2.7 2.8*
K/A catalog 3.11-3
ts
( )
\s /
SYSTEM: 033 Spent Fuel Pool Cooling System (SFPCS)
TASK MODE: 000 Generic TASK: Fill the spent fuel pools Operate the SFPCS between refueling pool and spent fuel pool Perform BWST purification using filter /demineralizer Lower refueling pool level (fuel transfer canal)
Perform decay heat removal using the SFPCS IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the SFPCS and the following systems:
Kl.01 RCS..................................................... 2.4 2.5 K1.02 RHRS.................................................... 2.5 2.7 Kl.03 SI5..................................................... 2.4 2.5 K1.04 BWST.................................................... 2.4 2.4 K1.05 RWST.................................................... 2.7* 2.8*
K1.06 Boric acid storage tank................................. 2.2 2.3
/'~"N Kl.07 Emergency makeup water systems.......................... 2.4 2.5 K2 Knowledge of bus power supplies to the following:
K2.01 SFPCS components........................................ 1.9 2.1 K3 Knowledge of the effect that a loss of the SFPCS will have on the following:
K3.01 Area venti l ati on systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6 3.1 K3.02 Area and ventilation radiation monitoring systems....... 2.8 3.2 K3.03 Spent fuel temperature.................................. 3.0 3.3 K4 Knowledge of SFPCS design feature (s) and/or inter-lock (s) which provide for the following:
l K4.01 Maintenance of spent fuel 1evel . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.2 K4.02 Maintenance of spent fuel cleanliness................... 2.5 2.7 K4.03 Anti-siphon devices............................... ..... 2.6 2.9 K4.04 Maintenance of spent fuel pool radiation................ 2.7? 2.9?
( K4.05 Adequate SDM (boron concentration)...................... 3.1 3.3 l
K5 Knowledge of the following theoretical concepts as they apply to the SFPCS:
K5.01 P um p t h e o ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 6 1.9
((N)
'~~'
KS.02 Heat transfer........................................... 1.7 1.9 K5.03 D/P detecto r theo ry o f 0PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 5 1.6 K/A catalog 3.11-5
SYSTEM: 033 Spent Fuel Pool Cooling System (SFPCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5.04 K-eff............ .....................................2.1 2.3*
KS.05 Decay heat............ ........... ... ................. 2.1 2.3 K5.06 Shielding..... ................. . . ................... 2.1 2.5 K6 Knowledge of the applicable performance and design attributes of the following SFPCS components:
K6.01 Pumps................................ ..................1.7 1.9 K6.02 Heat exchangers..... .......................... ........ 1.8 1. 9 K6.03 Valves................................. . . . . . . . . . . . . . 1. 7 1.7 K6.04 Motors... .......................... ........ ..... .... 1.7 1.7 K6.05 Pressure and pressure detectors.. .......... .. . ...... 1.7 1.7 K6.06 Temperature sensors............. ....................1.8 1.8 K6.07 Filters and demineralizers..................... .... ... 1.7 1.8 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SFPCS controls including:
A1.01 Spent fuel pool water level.... .......... ....... ..... 2.7 3.3 A1.02 Radiation monitoring systems............ ............ .. 2.8 3.3 A1.03 SFPCS controls and sensors..... ........... .. ........2.4 2.7 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the SFPCS; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Inadequate SDM...................... .......... ........ 3.0 3.5 A2.02 Loss of SFPCS.. ... .... . .. ............... .......... 2.7 3.0 A2.03 Abnormal spent fuel pool water level or loss of water level.. .......... . ..... ... ...... ............. .... 3.1 3.5 A3 Ability to monitor automatic operation of the SFPCS, including:
A3.01 Temperature control valves........ ...... .............. 2.5* 2.7*
A3.02 Spent fuel leak or rupture... ........... ......... .... 2.9 3.1 Ai Ability to manually operate and monitor in the control room:
A4.01 SFPCS pumps........ .... ............. .... . .. .. 2.4* 2.3*
A4.02 SFPCS valves. ........ .. . ... ... .. . .. . ..... 2.3* 2.1*
K/A catalog 3.11-6
3<-"x .
SYSTEM: 033 Spent Fuel Pool Cooling System (SFPCS) i I TASK MODE: 000 Generic
\_)'
-Tasks as.noted previously.
IMf0RTANCE K/A NO. ABILITY R0 SR0 A4.03 Support systems for fill and transfer of SFPCS water.... 2.3 2.4 AS- Ability to direct operations of the following:
A5.01 S F P C S p ump s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 4 2.9 A5.02 SFPCSva1ves............................................ 2. 4 2.8 AS.03 Support systems for fill and transfer of SFPCS water.... 2.4 2.9 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.8 3.1
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.3* 3.2
- 3. Knowledge of which events related to system operation / status should be reported. 2.3* 3.4
, ) 4. Knowledge of system purpose and/or function. 3.1 3.5 v
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8* 3.5*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.4 2.9
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.0 3.5
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.0 3.9
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.1 3.3
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.7 3.9
, 11. Ability to perform those actions, without reference to proce-r'~' dure, for all casualties which require immediate operation of
! system components or controls. 3.6 3.8 K/A catalog 3.11-7
SYSTEM: 033 Spent Fuel Pool Cooling System (SFPCS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE S_YSTEM GENERIC K/As R0 SR0
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change..................... ....... ..... 2.1* 2.2 Normal plant operations............ .... ... ............. . 2.1* 2.2 Plant heatup and startup.............................. ... .... 2.1* 2.2 Plant shutdown and cooldown........ .......... ... . .... ... 2.1* 2.2 O
O 1
K/A catalog 3.11-8 1
! I
'x_ /
SYSTEM: 034 Fuel Handling Equipment System (FHES)
TASK MODE: 000 Generic TASK: Operate the spent fuel handling machine / bridge / platform crane Operate the new fuel elevator Operate the refueling machine / main fuel handling bridge (fuel element change)
Operate the control rod change machine / fuel handling bridge / reactor building crane (control rod change)
Operate the fuel transfer system / fuel transfer carriages and upenders Operate the auxiliary fuel handling bridge manipulator crane Operate the auxiliary building overhead crane (general load handling)
What if a spent fuel assembly is dropped in containment?
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the FHES and the following systems:
Kl.01 RCS..................................................... 2.5 3.2 g'~'s Kl.02 RHRS.................................................... 2.5 3.2
- ) Kl.03 CVCS.................................................... 2.1 2.7*
N- # Kl.04 NIS..................................................... 2.6 3.5 Kl.05 Shutdown monitor........................................ 2.5* 3.4*
K1.06 SFPCS................................................... 2.4 3.0*
K2 Knowledge of bus power supplies to the following:
K2.01- All fuel handling equipment (e.g., cranes, fuel eleva-tors, handling bridge).................................. 1.5 2.0 K2.02 Airsupply.............................................. 1. 6 1.9 K2.03 Area monitors........................................... 1.9 2.2 K3 Knowledge of the effect that a loss of the FHES will have on the following:
K3.01 Containment ventilation................................. 2.4* 2.9*
K4 Knowledge of FHES design feature (s) and/or interlock (s) which provide for the following:
K4.01 Fuel protection from binding and dropping............... 2.6 3.4 K4.02 Fuel movement........................................... 2.5 3.3 K4.03 Overload protection..................................... 2.6 3.3 y'"'s K5 Knowledge of the following theoretical concepts as they
( ) apply to the FHES:
\m/
K5.01 General principles of mechanical lifting................ 1.7? 2.1?
K/A catalog 3.11-9
SYSTEM: 034 Fuel Handling Equipment System (FHES)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K5.02 Limiting of 1oad........................................ 2.0 2.6 K5.03 Res i dual heat removal ; decay. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2 2.7 K6 Knowledge of the applicable performance and design attributes of the following FHES components:
K6.01 Fuel handling equipment.......... ......................2.1 3.0 K6.02 Radiation monitoring systems............ ............... 2.6 3.3 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the FHES controls including:
A1.01 Load limits............................................. 2.4 3.2 A1.02 Water level in the refueling canal . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.7 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the FHES; and (b) based on those predictions, use procedures to correct, con-trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Dropped fuel element.................................... 3.6 4.4 A2.02 Dropped cask............................. ....... ..... 3.4 3.9 A2.03 Mispositioned fuel element.............................. 3.3 4.0 A3 Ability to monitor automatic operation of the FHES, including:
A3.01 Travel limits.... ............... ...................... 2.5* 3.1 A3.02 Load limits...................... ............. ....... 2.5* 3.1 A3.03 High flux at shutdown.. ........ ....... ... . ......... 2.9 3.3 A4 Ability to manually operate and/or monitor in tha con-trol rnnm:
A4.01 Radiation levels.. ......... ..... .. ........ ..... . . 3.3 3.7 A4.02 Neutron levels... .. .. ......... ........ ... .. ...... 3.5 3.9 SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.7 3.2 K/A catalog 3.11-10
4 f' ~'g SYSTEM: 034 Fuel Handling Equipment System (FHES) 000 Generic l.,v) TASK MODE:
Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.3* 3.0*
- 3. Knowledge of which events related to system operation / status should be reported. 2.3* 3.2*
- 4. Knowledge of system purpose and/or function. 3.1* 3.5*
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8* 3.7*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.7 3.3
- 7. Ability to locate, explain, and apply all limits and precau-tions. 2.9 3.7
- 8. Ability to recognize indications for system operating param-
[)N
(,,,
- eters, which are entry level conditions for Technical Specifications. 2.9 4.0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.1 3.5
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.7 4.1
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 2.0* 4.1
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change........ .......................... 2.0* 1.9*
Normal plant operations........................................ 2.0* 1.9*
Pl ant heatup and sta rtup . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 0* 1.9*
Plant shutdown and cooldown.............. ..................... 2.2* 2.1*
O
\s_ /
K/A catalog 3.11-11
-f m
\
\
v)
SYSTEM: 068 Liquid Radwaste System (LRS)
TASK MODE: 000 Generic TASK: Perform lineups of the reactor coolant waste (RCW) system (clean radwaste system)
Perform transfer operations from an RCW holdup / receiver tank Perform transfer operations from a reactor coolant monitor tank ,
Perform transfer operations from reactor coolant drain / pressurizer relief tank Monitor the RCW/ boron recovery system Start up the RCW/ boron evaporator Transfer waste / boron recovery evaporator concentrates Shut down the RCW/borcn recovery evaporator Recirculate distillate through the polishing demineralizer Perform transfer of distillate to primary water storage tank IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the LRS and the following systems:
/NI .,
(
s
'~'/ K1.01 RCS and CVCS.'................ .......................... 2.4 2.6 K1.02 Waste gas vent header................................... 2.5 2.6 K1.03 PRT..................................................... 2.2 2.3 K1.04 Reactor drain tank.......... ........................... 2.4* 2.5*
K1.05 CWS/CCWS................................................ 2.3 2.6 K1.06 Boron recovery equipment................................ 2.1* 2.3*
K1.07 Sources of liquid wastes for LRS. . . . . . . . . . . . . . . . . . . . . . . . 2.7 2.9 K1.08 A ux i l i a ry s t e am . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9
- 2.2*
K2 Knowledge of bus power supplies to the following:
K2.01 Transfer pump........................................... 1.7* 1.9 K2.02 Automatic isolation valves.............................. 1.9 2.1 K2.03 Radiation monitors...................................... 2.1 2.2 K3 Knowledge of the effect that a loss of the LRS will have on the following:
K3.01 CVCS.................................................... 2.2 2.4 K3.02 WGDS.................................................... 2.1 2.4 K4 Knowledge of LRS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Safety and environmental precautions for handling hot,
('~'T y _,/ acidic, and radioactive liquids......................... 3.4 4.1 K/A catalog 3.11-13
SYSTEM: 068 Liquid Radwaste System (LRS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K5 Knowledge of the following theoretical concepts as they apply to the LRS:
K5.01 Tharmal stress on equipment............................. 1.7 2.2*
K5.02 Relationships between temperature and pressure of a water-based fluid............................... ....... 1.5 1.9 K5.03 Units of radiation, dose, and dose rate................. 2.6 2.6 KS.04 Biological hazards of radiation and the resulting goal of ALARA........................................ ..... 3.2 3.5 K5.05 Relationship between evaporator reboiler steam pressure and the heatup rate............. ............... ..... 1.7 1. 9 K5.06 Evaporation-condensation cycle of distilling units.. ... 1.6* 1.8*
K6 Knowledge of the applicable performance and design attributes of the following LRS components:
K6.01 Filters......................... .. ..................1.7 1.9 K6.02 Demineralizers and ion exchangers. ..................... 1.9 2.0 K6.03 Boron recove ry evaporator. . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 1.9 K6.04 Valves........... ....... ....................... ...... 1.8 1.9 K6.05 Pumps............................................ . . . . 1. 7 1. 8 K6.06 Controllers and positioners...... .......... ........... 1.7 1.7 K6.07 Sensors and detectors................ ................1.9 1. 9 K6.08 Breakers, relays, and disconnects........... . . . . . . . . . . 1. 6 1.7 K6.09 Miscellaneous liquid radiation waste drain tanks and waste holdup tanks...... .... .... ..................... 1.9 2.1 K6.10 Radiation monitors........ ......... ...... ...... ... 2.5 2.9 K6.11 Waste . evaporators....... ... .... ....... ....... .. . . 1. 8 2.1 ABILITY Al Ability to predict and/or monitor changes in param-eters (to prevent exceeding design limits) associated with operating the LRS controls including:
A1.01 Waste coolant monitor tank....... .... ........ .. .... 2.2* 2.5*
A1.02 Evaporator pressure control...... . ... ... . ........ 2.2* 2.3*
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the LRS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 A boric-acid " freeze".. ..... . ...... . . .... ....... 2.3? 2.2?
A2.02 Lack of tank recirculation prior to release.. .......... 2.7* 2.8*
K/A catalog 3.11-14
A SYSTEM: 068 Liquid Radwaste System (LRS)
TASK MODE: 000 Generic V) 5 Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A2.03 Insufficient sampling frequency of the boric acid in the e vapo ra to r bo t toms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5* 2.6*
A2.04 Failure of automatic isolation.......................... 3.3 3.3 A3 Ability to monitor automatic operation of the LRS, j including:
l A3.01 Evaporator pressure contro1............................. 2.5* 2.4*
A3.02 Automatic isolation..................................... 3.G 3.6 A4 Ability to manually operate and monitor in the control room:
A4.01 Control board for boron recovery........................ 2.7* 2.4*
A4.02 Remote radwaste release................................. 3.2* 3.1*
A4.03 Stoppage of release if limits exceeded.................. 3.9 3.8 A4.04 Automatic isolation..................................... 3.8 3.7 SYSTEM GENERIC K/As G 1. Knowledge of operator responsibilities during maintenance, J test, and surveillance activities. 2.7 3.1* 1 1
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.2 l
- 3. Fr.owledge of which events related to system operation / status should be reported. 2.6* 3.4
- 4. Knowledge of system purpose and/or function. 3.1 3.3
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 3.1* 3.9*
- 6. Ability to locate and operate components, using local controls ~
(outside the control room). 2.4 2.8
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.3 3.8
- 8. Ability'to recognize indications for system operating param-eters, which are entry level conditions for Technical O Specifications. 3.4 4.1 k)
K/A catalog 3.11-15
SYSTEM: 068 Liquid Radwaste System (LRS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.5
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.2
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 4.1
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change............... ................... 2.4 2.5 Normal plant operations........................................ 2.4 2. 5 Plant heatup and startup....................................... 2.5 2.6 Plant shutdown and cooldown......................... .......... 2.4 2.5 O
O K/A catalog 3.11-16
)
t
/
v SYSTEM: 071 Waste Gas Disposal System (WGDS)
TASK MODE: 000 Generic TASK: Perform lineups of the WGDS Start up the WGDS Shift WGOS compressors Shift waste gas decay tanks Return gas to the CVCS holdup tank Conduct authorized waste gas release Monitor WGDS operation Purge the waste gas surge tank and compressors Sample the waste gas decay tanks Recover from automatic termination of gas release due to PRMS system alarm Shut down the WGDS IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K1 Knowledge of the physical connections and/or cause-effect relationships between the WGDS and the following systems:
/m i
/
( ) K1.01 Nitrogen gas............................................ 2.1 2.1 Kl.02 Sealing water........................................... 2.2 2.2 K1.03 LRS..................................................... 2.1 2.1 K1.04 Station ventilation..................................... 2.7 2.8 K1.05 Meteorological tower.................................... 2.7 2. 8 K1.06 ARM and PRM systems.............................. ...... 3.1* 3.1 K1.07 RCS..................................................... 2.1 2.1 Kl.08 CVCS.................................................... 2.2 2. 2 K1.09 Plant sampling system................................... 2.1 2.2 K2 Knowledge of bus power supplies to the following:
K2.01 WGDS.................................................... 1.9 2.1 K2.02 Isolation valve........................................ 2.0* 2.0 K2.03 ARM and PRM systems..................................... 2.1* 2.3 K3 Knowledge of the effect that a loss of the WGDS wjl1 ~~
have on the followin,g:
K3.01 LRS..................................................... 2.0 2.3 K3.02 CVCS.................................................... 2.1 2.1 K3.03 RCS..................................................... 2.2 2.1 K3.04 Ventilation system...................................... 2.7 2.9 K3.05 ARM and PRM systems..................................... 3.2 3.2 f3
( ) K4 Knowledge of WGDS design feature (s) and/or interlock (s)
'- ' which provide for the following:
K/A catalog 3.11-17
SYSTEM: 071 Waste Gas Disposal System (WGDS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K4.01 Pressure capability of the waste gas decay tank......... 2.6 3.0 K4.02 Sealing water around the shaft of the gas compressor.... 2.5* 2.5*
K4.03 Ta n k l o op s e a l s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5* 2.6*
K4.04 Isolation of waste gas release tanks.................... 2.9 3.4 K4.05 Point of release......................... ....... ...... 2.7 3.0 K4.06 Sampling and monitoring of waste gas release tanks..... 2.7* 3.5*
K5 Know! edge of the following theoretical concepts as they apply to the WGDS:
K5.01 Relative pressure measurements....... .................. 1.7 2.1 K5.02 Relationships and measurements of gas temperature, pressure, and flow rate....... ................ ...... . 1.7 1.9 K5.03 Sources of hydrogen that could accumulate in the decay tank.................... .. .... . .... ... ......... .. 2.3 2.9 K5.04 Relationship of hydrogen / oxygen concentrations to flammability........ ......... ......................... 2.5 3.1 K5.05 Methods of measuring hydrogen gas concentration...... . 2.1 2.7 K5.06 Radioactive decay......... ........ ... .. ............. 2.3 2.4 K6 Knowledge of the applicable performance and design attributes of the following WGDS components:
K6.01 Valves...................... ..... ..................... 1.9 2.1 K6.02 Sensors and detectors........ .. ....... ............. . 1.9 1.9 K6.03 Controllers and positioners....... ..... ....... .. . . . 1. 8 1.9 K6.04 Pumps......................... ..... ................... 1.6 1.7 K6.05 Motors...................................... . . . . . . . . . . 1. 6 1.7 K6.06 Breakers, relays, and disconnects.... . . . . . . . . . . . . . . 1. 7 1.8 K6.07 Compressors....... ........... .. .. .. ..... .. ...... 1.9 2.1 K6.08 Rupture disks................... . ... . .. .. ....... 2.2 2.5 K6.09 Waste gas header.............. ....... ...... ......... 2.3 2.5 K6.10 Surge and decay tanks................................... 2.3 2.5 ABILITY Al Ability to predict and/or monitor changes in param-eters (to prevent exceedirg design limits) associated with operating the WGDS controls including:
A1.01 Time response of radiation levels to release of waste gas............................... .. .. .... ........ 2.2 2.9 A1.02 Nitrogen addition to the decay tank........ ........... 2.0 2.3 A1.03 Holdup tank pressure and level........... .... ........ 2.3 2.4 A1.04 Waste gas header pressure vs. compressor operation.. .. 2.3 2.5 A1.05 Decay tank pressure vs. liquid levels.......... . ... 2.0 2.1 K/A catalog 3.11-18
l fm SYSTEM: 071 Waste Gas Oisposal System (WGDS)
( -TASK MODE: 000 Generic Q) Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SR0 A1.06 Ventilation system...................................... 2.5 2.8 A1.07 Surge tank pressure and level........................... 2.0 2.2 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the WGDS; and (b) based on those predictions, use procedures to correct, con-
- trol, or mitigate the consequences of those malfunc-tions or operations:
A2.01 Use of WGOS to prevent entry of oxygen into holdup tanks during liquid transfers. . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 3? 2.8?
A2.02 Use of waste gas release monitors, radiation, gas flow rate, and totalizer..................................... 3.3 3.6 A2.03 Rupture disk failures................................... 2.7* 3.3*
A2.04. Loss of cover gas....................................... 2.3* 2.7*
A2.05 Power failure to the ARM and PRM Systems................ 2.5* 2.6 A2.06 Supply failure to the isolation valve................... 2.4 2.5 A2.07 Los s o f meteorol ogi cal tower. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5 2.9
[ A2.08 Meteorological changes.................................. 2.5 2.8*
iv ]/ A2.09 Stuck-open relief va1ve................................. 3.0* 3.5*
A3 Ability to monitor automatic operation of the WGDS, including:
A3.01 HRPS.................................................... 2.6* 2.7*
A3.02 Pressure-regulating system for waste gas vent header.... 2.8 2.8 A3.02 Radiation monitoring system alarm and actuating signals. 3.6 3.8 A4 Ability to manually operate and/or monitor in the con-trol room.
l i
l A4.01 Valve to put the holdup tank into service; indications ,
of valve positions and tank pressure.................. . 2.7* 2.2*
A4.02 Waste gas compressor, including control switch, un-loading valve, and drain valve.......................... 2.5* 2.3*
A4.03 Valves and indications for sealing water to the gas-compressor shaft........................................ 2.6* 2.2*
A4.04 Radwaste liquid transfer pumps.......................... 2.4 2.1*
A4.05 Gas decay tanks, including valves, indicators, and s amp l e l i ne . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 6
- 2.6*
A4.06 Meteorological charts and recorders, along with the stop-time and waste gas release number.................. 2.8 3.3 A4.07 Waste gas release fl owmeter. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 0* 3.0*
i ]j
[
s A4.08 A4.09 A4.10 Nitrogen gas addition...................................
Waste gas release rad monitors..........................
WGDS sampling...........................................
2.3*
3.3 2.5*
2.0*
3.5 2.4*
K/A catalog 3.11-19
SYSTEM: 071 Waste Gas Disposal System (WGDS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. ABILITY R0 SRO A4.ll WGDS s tartup and s hutdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5* 2.3*
A4.12 Air purge of WGDS release radiation monitors. .......... 2.3* 2.4*
A4.13 Recovery from automatic termination of gas release due to PRM system alarm.................. .... . ...... ... 3.0 3.1 A4.14 WDGS status alarms................ ................. .. 2.8 3.0 A4.15 Procedure for putting the waste gas compressor in service and for removing it from service............ ... 2.4* 2.3*
A4.16 Waste gas decay tank shifts............... ........... . 2.5* 2.2*
A4.17 Stopping transfer of radioactive liquids to WGDS decay tank.................. ...... .......... ....... . .... 2.6* 2.5*
A4.18 Operation of radwaste liquid transfer pumps... .... . 2.2* 2.0*
A4.19 Bringing an empty WDGS decay tank on line and shutting down a full tank.... ........... .... ..... ... .. . .. 2.5* 2.2*
A4.20 Placing WGDS gas compressors in automatic operation.. .. 2.5* 2.2*
A4.21 Valve lineup for returning gas to the CVCS holdup tank from a waste gas decay tank................ ..... .. .. 2.4* 2.1*
A4.22 Use of recycle gas header..... ..... . .... .. . ... 2.3* 2.2*
A4.23 Procedure for regulating pressure in CVCS holdup tanks.. 2.3* 2.1*
A4.24 The double verification required before waste gas release.. ......... ............... ...... . ...... .. . 2.9* 3.4*
A4.25 Setting of process radiation monitor alarms, automatic functions, and adjustment of setpoints..... .. ... .... 3.2* 3.2 A4.26 Authorized waste gas release, conducted in compliance with radioactive gas discharge permit........ . .. . 3.1 3.9 A4.27 Opening and closing of the decay tank discharge control valve............................. ... .... ... . . . 3. 0
- 2.7*
A4.28 Nitrogen additions to the decay tank, and knowledge of limits............... .. .. ....... .......... ... . . 2.4* 2.4*
A4.29 Sampling oxygen, hydrogen and nitrogen concentrations in WDGS decay tank; knowledge of limits. .. ...... .. .. 3.0* 3.6*
A4.30 Water drainage from the WGDS decay tanks..... . 2.9* 2.6*
SYSTEM GENERIC K/As
- 1. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 2.6 2.9
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.1
- 3. Knowledge of which events related to system operation / status should be reported. 2.5* 3.4*
- 4. Knowledge of system purpose and/or function. 3.2 3.5 K/A catalog 3.11-20
[]\
3 SYSTEM:
TASK MODE:
071 000 Waste Gas Disposal System (WGDS)
Generic Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 3.1* 4.0
- 6. Ability to locate and operate components, using local controls (outside the contol room). 2.6 3.0
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.2 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.1 4.0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 3.4 s 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and
(/ abnormal operating procedures. 4.0 4.2
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.0 4.1
- 12. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.5* 2.5 Normal plant operations........................................ 2.5* 2.5 Plant heatup and startup....................................... 2.5* 2.5 Plant shutdown and cooldown.................................... 2.7* 2.5 nv K/A catalog 3.11-21
g
(
\~j
)
SYSTEM: 086 Fire Protection System (FPS)
TASK MODE: 000 Generic TASK: Perform lineup of the FPS Place the FPS in standby Shut down the FPS IMPORTANCE K/A NO. KNOWLEDGE R0 SRO K1 Knowledge of the physical connections and/or cause-effect relationships between the FPS and the following systems:
K1.01 High pressure service water............................. 3.0* 3.4*
K1.02 Raw service water....................................... 2.7* 3.2*
K1.03 A FW sy s t e m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4* 3.5*
K2 Knowledge of bus power supplies to the following:
K3 Knowledge of the effect that a loss of the FPS will have on the following:
im 1
( _,/ K3.01 Shutdown capability with redundant equipment............ 2.7 3.2 K4 Knowledge of FPS design feature (s) and/or interlock (s) which provide for the following:
K4.01 Adequate supply of water for FPS........................ 3.1 3.7 K4.02 Maintenance of fi re header pressure. . . . . . . . . . . . . . . . . . . . . 3.0 3.4 K4.03 Detection and location of fires......................... 3.1 3.7 K4.04 Personnel safety........................................ 3.1* 3.4 K4.05 Halon................................................... 3.0* 3.4*
K4.06 CO2 ..................................................... 3.0 3.3 K4.07 MT/G and T/G protection................................. 2.5 2.8 K5 Knowledge of the following theoretical concepts as they apply to the FPS:
K5.01 Effect of CO2 on fire...................... ............ 2.2 2.6 K5.02 Effect of halon on fire................................. 2.2 2. 6 K5.03 Effect of water spray on electrical components.......... 3.1 3.4 K5.04 Hazards to personnel as a result of fire type and methods of protcetion................................... 2.9 3.5*
K6 Knowledge of the applicable performance and design attributes of the following FPS components:
/a\ K6.01 2.1 2.3 1 / Pumps...................................................
# K6.02 Valves.................................................. 1.9 1.9 K/A catalog 3.11-23
SYSTEM: 086 Fire Protection System (FPS)
TASK MODE: 000 Generic Tasks as noted previously.
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 K6.03 Motors........................... ..... ................ 1.7 1. 9 K6.04 Fire, smoke, and heat detectors................... ..... 2.6 2.9 ABILITY Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the FPS controls including:
A1.01 Fire header pressure.... ......................... ..... 2.9 3.3 A1.02 Fi re water storage tank l evel . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 0* 3.2*
A1.03 Fire doors.............................................. 2.7 3.2*
A1.04 Fire dampers............................................ 2.7 3.3 A1.05 FPS lineurs..................................... ....... 2.9 3.1 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the FPS; and (b) based on those predictions, use procedures to correct, control, or mi;igate the consequences of those malfunctions or operauions:
A2.01 Manua i s h utdown o f the F PS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.1 A2.02 Low FPS header pressure.. .............................. 3.0 3.3 A2.03 Inadvertent actuation or the FPS due to circuit failure or wela:ng... ........................................2.7 2.9 A2.04 Failure to actuate the FPS when required, resulting in fire damage................... ................ ... .... 3.3 3.9 A3 Ability to monitor automatic operation of the FPS, including:
A3.01 Starting mechanisms of fire water pumps......... ....... 2.9 3.3 A3.02 Actuation of the FPS................... ........ ....... 2.9 3.3 A3.03 Actuation of fire detectors............... ............. 2.9 3.3 A4 Ability to manually operate and/or monitor in the con-trol room:
A4.01 Fire water pumps........................................ 3.3 3.3 A4.02 Fire detection panels................................... 3.5 3.5 A4.03 Fire alarm switch....... ........... ................... 3.5 3.4 A4.04 Fire water storage tank makeup pumps.................... 3.4* 3.3*
A4.05 Deluge valves.. ........................................ 3.0 3.5 A4.06 Halon system............................................ 3.2 3.2*
K/A catalog 3.11-24
__ A
/N SYSTEM: 086 Fire Protection System (FPS)
- ) TASK MODE
- 000 Generic v
Tasks as noted previously.
IMPORTANCE SYSTEM GENERIC K/As R0 SR0
- 9. Knowledge of operator responsibilities during maintenance, test, and surveillance activities. 3.0 3.5
- 21. Ability to locate and operate components, using local controls (outside the control room). 2.9 3.6
- 22. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.3
- 23. Knowledge of which events related to system operation / status should be reported. 2.5* 2.5
- 24. Ability to locate, explain, and apply all limits and precau-tions. 3.2 3.7
- 25. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical
,-_ Specifications. 3.1 4.0
/ i
.s_,) 26. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 3.5
- 27. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.0 4.2
- 28. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 4.1
- 29. Ability to perform specific system and integrated plant opera-tions during:
Controlled plant load change................................... 2.6 2.5 Normal plant operations........................................ 2.6 2.6 Plant heatup and startup....................................... 2.7 2.6 Plant shutdown and cooldown.................................... 2.6 2.5
- 35. Knowledge of system purpose and/or function. 3.4 3.7
- 36. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8* 3.7*
\O)
- j K/A catalog 3.11-25 u--._---_------.--
1 l
l
, -m SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 036 Fuel Handling Incident IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the fuel handling incident emergency task:
EK1.01 Radiation exposure hazards.............................. 3.5 4.1 EK1.02 SDM..................................................... 3.4 3.8 EK1.03 Indications of approaching criticality.................. 4.0 4.3 EK2 Knowledge of the-following components:
EK2.01 Fuel handling equipment................................. 2.9 3.5 EK2.02 Radiation monitoring equipment (portable and installed). 3.4 3.9 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Different inputs that will cause a reactor building evacuation.............................................. 3.1 3.7
(s) EK3.02 EK3.03 Interlocks associated with fuel handling equipment. . . . . .
Guidance contained in E0P for fuel handling incident....
2.9 3.7 3.6 4.1 i
v' ABILITY EA1 Ability to operate and monitor the following:
l EA1.01 Reactor building containment purge ventilation system... 3.3 3.8 EA1.02 ARM system.............................................. 3.1 3.5 EA1.03 Reactor building containment evacuation alarm enable switch.................................................. 3.5 3.9 EA1.04 Fuel handling equipment during an incident.............. 3.1 3.7 EA2 Ability to determine or interpret:
EA2.01 ARM system indications.................................. 3.2 3.9 EA2.02 Occurrence of a fuel handling incident.................. 3.4 4.1 EA2.03 Magnitude of potential radioactive release.............. 3.1* 4.2*
SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.6
- 3. . Knowledge of which events related to system operation / status
/'~'} should be reported. 2.6* 3.7 LI K/A catalog 3.11-27
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 036 Fuel Handling Incident IMPORTANCE SYSTEM GENERIC K/As R0 SRO
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.9* 3.9*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.8 3.4
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.3 3.9
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.2 4.3
- 9. Ability to veri., system alarm setpoints and operate controls identified in the alarm response manual. 3.4 3.9
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.0 4.5
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.1 4.3 O
K/A catalog 3.11-28
SYSTEM: 000 Emergency Plant Evolutions
[~ '\ EPE MODE: 059 Accidental Liquid Radioactive-Waste Release V IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the accidental liquid radioactive-waste release emergency task:
EKl.01 Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant................................................... 2.7 3.1 EKl.02 Biological effects on humans of various types of radia-tion, exposure levels that are acceptable for nuclear power plant personnel, and the units used for radiation-intensity measurements and for radiation-exposure levels......................................... 2.6 3.2*
EK1.03 Effects of placing a radioactive source near a radia-tion monitor; in particular, near a radioactive-liquid radiation monitor....................................... 2.3 2.9*
EK1.04 The relationship between background radiation intensity and the alarm setpoints on a radioactive liquid monitor. 2.3 2.9*
EKl.05 The calculation of offsite doses due to a release from the power plant......................................... 2.6' 3.6*
gsg EK2 Knowledge of the following components:
\ l
's '
EK2.01 Radioactive-liquid monitors............................. 2.7 2.9 EK2.02 Radioactive gas monitors................................ 2.7 2.7 EK2.03 Valves.................................................. 2.0 2.0 EK2.04 Sensors, detectors, and indicators...................... 1.9 1.9 EK3 Knowledge of the bases or reasons for the following: ,
EK3.01 Termination of a release of radioactive liquid.......... 3.5 3.9 EK3.02 Implementation of E plan........... .................... 3.2* 4.5 EK3.03 Declaration that a radioactive-liquid monitor is inoperable.............................................. 3.0 3.7 EK3.04 Actions contained in E0P for accidental liquid radioactive-waste release............................... 3.8 4.3 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Radioactive-liquid monitor.............................. 3.5 3.5 EA1.02 ARM system.............................................. 3.3 3.4 EA1.03 Flow rate controller.................................... 3.0* 2.9*
EA2 Ability to determine or interpret:
-1 j EA2.01 The failure-indication light arrangement for a radioactive-liquid monitor..............................
3.2 3.5 '
l K/A catalog 3.11-29 l l
J
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 059 Accidental Liquid Radioactive-Waste Release IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.02 The permit for liquid radioactive-waste release......... 2.9 3.9 EA2.03 Failure modes, their symptoms, and the causes of misleading indications on a radioactive-liquid monitor.. 3.1 3.6 EA2.04 The valve lineup for a release of radioactive liquid.... 3.2* 3.5*
EA2.05 The occurrence of automatic safety actions as a result of a high PRM system signal.................. ..... . . 3.6 3.9 CA2.06 That the flow rate of the liquid being released is less than or equal to that specified on the release permit... 3.5* 3.8 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.5
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.7
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.9* 3.8*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9 3.1
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.3 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.1 4.1
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.5 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.0 4.3
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.1 4.2 O
K/A catalog 3.11-30
SYSTEM: 000 Emergency Plant Evolutions (v j EPE MODE: 060 Accidental Gaseous-Waste Release IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they apply to the accidental gaseous-waste release emergency task:
EK1.01 Types of radiation, their units of intensity and the location of sources of radiation in a nuclear reactor p owe r p l a nt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5 3.1*
EK1.02 Biological effects on humans of the various types of radiation, exposure levels that are acceptable for per-sonnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure levels......................................... 2.5 3.1**
EK1.03 Theory of radiation detection and intensity measurement by the use of ionization chambers and scintillation-typa radiation detectors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.5*
EKl.04 Calculation of offsite doses due to a release from the p owe r p l a n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5* 3.7*
EK2 Knowledge of the following components:
O y'j EK2.01 ARM system, including the normal radiation-level indications and the operability status.................. 2.6 2.9*
EK2.02 Auxiliary building ventilation system. . . . . . . . . . . . . . . . . . . 2. 7 3.1-EK2.03 Va1ves.................................................2.1 2.1 EK2.04 Sensors , detectors , and indicators. . . . . . . . . . . . . . . . . . . . . . 1. 9 1.9 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Implementation of E plan................................ 2.9 4.2 EK3.02 Isolation of the auxiliary building ventilation......... 3.3* 3.5*
EK3.03 Actions contained in E0P for accidental gaseous-waste release................................................. 3.8 4.2 EK3.04 Startup of the gas treatment system..................... 2.2* 2.7*
ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Area radiation monitors................................. 2.8 3.0 EA1.02 Ventilation system...................................... 2.9 3.1 l I
l EA2 Ability to determine or interpret:
EA2.01 A radiation-level alarm, as to whether the cause was j due to a gradual (in time) signal increase or due to a j O sudden increase (a " spike"), including the use of strip-chart recorders, meter and alarm observations. . . . . 3.1 3.7 i
V K/A catalog 3.11-31 l
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 060 Accidental Gaseous-Waste Release IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.02 The possible location of a radioactive gas leak, with the assistance of PEO, health physics and chemistry personnel............................................... 3 .1 4.0 EA2.03 The steps necessary to isolate a given radioactive gas l e a k , u s i n g P&I D s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2 3.9 EA2.04 The effects on the power plant of isolating a given radioactive gas leak.................................... 2.6 3.4*
EA2.05 That the automatic safety actions have occurred as a resul t of a high ARM system signal . . . . . . . . . . . . . . . . . . . . . . 3. 7 4.2 EA2.06 Valve lineup for release of radioactive gases........... 3.6* 3.8 SYSTEM GENENIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.5
- 3. Knowledge of which events related to system operation / status should be reported. 2.7* 3.7
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.9* 3.9*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9 3.1
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.3 3.8
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.2 4.3
- 9. Ability to verify system alarm setpoints and operate controls I
identified in the alarm response manual. 3.5 3.7
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 4.1 4.4
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 4.0 4.1 O
K/A catalog 3.11-32
f- s' SYSTEM: 000 Emergency Plant Evolutions
, I EPE MODE: 067 Plant Fire On Site
(
IMPORTANCE K/A NO. KNOWLEDGE R0 SRO EK1 Knowledge of the following theoretical concepts as they apply to the plant fire on site emergency task:
EK1.01 Fire classifications, by type..... ..................... 2.9 3.9 EK1.02 Fire fighting........................................... 3.1 3.9 EK2 Knowledge of the following components:
EK2.01 Sensors, detectors and valves........................... 2.3 2.5*
EK2.02 Controllers and positioners............................. 2.0 2.3 EK2.03 Motors.................................................. 1.9 2.1 EK2.04 Breakers, relays, and disconnects....................... 1.9 2.1 EK3 Knowledge of the bases or reasons for the following:
EK3.01 Installation of fire detectors.......................... 2.3 2.8 EK3.02 Steps called out in the site fire protection plan, FPS manual, and fire zone manual............................ 2.5 3.3 EK3.03 Fire detector surveillance test......................... 2.0* 2.5*
EK3.04 Actions contained in E0P for plant fire on site......... 3.3 4.1
(-
t ABILITY G
EA1 Ability to operate and monitor the following:
EA1.01 Respirator air pack..................................... 3.6 3.6 EA1.02 Re-installation of a fire detector...................... 2.4* 2.5*
EA1.03 Bypass of a fire zone detector.......................... 2.5* 2.8*
EA1.04 Bypass of a heat detector............................... 2.5* 2.7*
EA1.05 Plant and control room ventilation systems.............. 3.0 3.1 EA1.06 F i re a l a rm . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5 3.7 EA1.07 Fire alarm reset panel.................................. 2.9 3.0 EA1.08 Fire fighting equipment used on each class of fire...... 3.4 3.7
- EA1.09 Plant fire zone panel (including detector location).. . . . 3.0 3.3 EA2 Ability to determine or interpret:
EA2.01 Auxiliary building gas treatment system................. 2.5* 2.8* l EA2.02 Damper position......................................... 2.5 2.9 )
EA2.03 Fire alarm.............................................. 3.3 3.5 l EA2.04 The fire's extent of potential operational damage to l plant equipment......................................... 3.1 4.3 EA2.05 Ventilation alignment necessary to secure affected area. 3.2 3.6 1 EA2.06 Need for pressurizing control room (recirculation mode). 3.3 3.6 EA2.07 Whether malfunction is due to common-mode electrical l
(N) failures................................................ 2. 6 3.1*
t EA2.08 Limi ts of af fected area. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 9 3.6
\/ EA2.09 That a failed fire alarm detector exists................ 2.4 2.7 i K/A catalog 3.11-33
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 067 Plant Fire On Site IMPORTANCE K/A NO. ABILITY R0 SR0 EA2.10 Time limit of long-term-breathing air system for control room............................................ 2.9* 3.6*
EA2.11 Time limit for use of respirators....................... 3.3* 3.5 EA2.12 Location of vital equipment within fire zone............ 2.9 3.9 EA2.13 Need for emergency plant shutdown. . . . . . . . . . . . . . . . . . . . . . . 3. 3 4.4 EA2.14 Equipment that will be affected by fire suppression acti vi ti es i n each zo ne. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2 4.3 EA2.15 Requirements for establishing a fire watch. . . . . . . . . . . . . . 2. 9 3.9 EA2.16 Vital equipment and control systems to be maintained and operated during a fire.............................. 3.3 4.0 EA2.17 Systems that may be affected by the fire................ 3.5 4.3 SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.7* 3.7
- 3. Knowledge of which events related to system operation / status should be reported. 2.6* 3.8
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.8* 3.7*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.9 3.7
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.1 3.7
- 8. Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.3 4.2
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 3.6
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.9 4.3
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.9 4.1 O
K/A catalog 3.11-34
/'~'s SYSTEM: 000 Emergency Plant Evolutions
( ) EPE MODE: 076 High Reactor Coolant Activity v
IMPORTANCE K/A NO. KNOWLEDGE R0 SR0 EK1 Knowledge of the following theoretical concepts as they apply to the plantwide emergency / abnormal conditions emergency task:
EK1.01 Radioactivity units..................................... 2.1 2.5 EK1.02 Radiation source term and transport pathway............. 2.0 2.5 EK1.03 Channel i ng i n a demi nerali zer. . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.0 EK1.04 Effects of excessive temperature on a demineralizer resin................................................... 2.1 2.3 EK1.05 Definition and use of the following terms: F, log scale, CPM, multipoint, setpoint, gpm, pH, D/F, conductivity... 1.9 2.3 EK1.06 Chemical shock and crud burst........................... 2.1 2.6 EK1.07 Thermal shock........................................... 2.2 2.4 EKl.08 Hydraulic shock......................................... 2.1 2.3 EK1.09 Relationship between letdown flow rate and letdown temperature............................................. 2.2 2.3 EK2 Knowledge of the following components:
EK2.01 Process radiation monitors.............................. 2.6 3.0 tO EK2.02 CCW pump and heat exchangers............................ 2.1 2.3
(,_,/ EK2.03 Sensors and detectors................................... 1.9 1. 9 EK2.04 Valves.................................................. 1.8 1.9 EK2.05 Controllers and positioners............................. 1.9 1.9 EK2.06 Demineralizers and ion exchangers....................... 2.0 2.1 EK3 Knowledge of the bases or reasons for the following:
EK3.01 RCS differentiating activity due to fission products and due to corrosion products, from chemistry report.... 2.4 3.1 EK3.02 Increased CCW flow...................................... 2.4 2.6 EK3.03 Orifice controls for minimum letdown flow rates......... 2.1* 2.1 EK3.04 Setpoint controls for maximum demineralizer flow rates.. 2.3 2.5 EK3.05 Corrective actions as a result of high fission product radioactivity level in the RCS.......................... 2.9 3.6 EK3.06 Actions contained in E0P for high reactor coolant activity................................................ 3.2 3.8 ABILITY EA1 Ability to operate and monitor the following:
EA1.01 Interlocks associated with orifice isolation valve...... 2.4 2.2 EA1.02 CCWS standby pump and outlet va1ves..................... 2.1 2.0 EA1.03 CVCS letdown flow rate and temperature.................. 2.3* 2.1
[}
V' EA1.04 Failed fuel-monitoring equipment........................ 3.2 3.4 EA2 Ability to determine or interpret:
K/A catalog 3.11-35
SYSTEM: 000 Emergency Plant Evolutions EPE MODE: 076 High Reactor Coolant Activity IMPORTANCE K/A N0. ABILITY R0 SRO EA2.01 Location or process point that is causing an alarm...... 2.7 3.2 EA2.02 Corrective actions required for high fission product activity in RCS................. ....................... 2.8 3.4 EA2.03 RCS radioactivity level meter........................... 2.5 3.0 EA2.04 Process effluent radiation chart recorder.......... .... 2.6 3.0 EA2.05 CVCS l etdown flow rate i ndication. . . . . . . . . . . . . . . . . . . . . . . 2. 2 2.5 EA2.06 Response of PZR LCS to changes in the letdown flow rate. 2.2 2.5 EA2.07 When demineralizer resin needs to be replaced........... 2.4* 2.7*
SYSTEM GENERIC K/As
- 2. Knowledge of system status criteria which require the notifi-cation of plant supervisors or off plant personnel. 2.5* 3.5
- 3. Knowledge of which events related to system operation / status should be reported. 2.5* 3.7
- 5. Knowledge of the Technical Specification bases and defini-tions related to limiting conditions for operations and safety limits. 2.7* 3.6*
- 6. Ability to locate and operate components, using local controls (outside the control room). 2.3 2.5
- 7. Ability to locate, explain, and apply all limits and precau-tions. 3.0 3.4 8 Ability to recognize indications for system operating param-eters, which are entry level conditions for Technical Specifications. 3.1 4.0
- 9. Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.1 3.3
- 10. Ability to recognize abnormal indications for system operating parameters, which are entry-level conditions for emergency and abnormal operating procedures. 3.7 4.0
- 11. Ability to perform those actions, without reference to proce-dure, for all casualties which require immediate operation of system components or controls. 3.6 3.9 O
K/A catalog 3.11-36
O j
l 1
APPENDIX A J O co Po~eur x~ow'eDoes .
E D
l O i
l i
4 i
O APPENDIX A t
COMPONENTS l
4 4
Y 4
1 i
4 1
4 1
i i
i k
!,9 I
i i
I l
I i
1 i
O t
,i j K/A catalog 1
i-1 1
J
+
- CONTENTS i
!, Page Va1ves................................................................... A-1 i .
! Sen s o r s /De tec to rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-4 1
Controllers and Positioners.............................................. A-7 a
P ump s - Ce nt r i f uga l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A- 9
- R o t a ry Va n e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A- 11
- Positive Displacement............................................ A-12 4
Venturi.......................................................... A-13
- Motors................................................................... A-14 Heat Exchangers and Condensers........................................... A-16 i
- Demineralizers and Ion Exchangers........................................ A-20
- f. Breakers, Relays and Disconnects......................................... A-23 1
1
.i 1
e
.i, 6
.i k
,4 i
4 f
i
[
t 1
4 it 1
1 i,
K/A catalog A-iii i
1
- +.-e,-w,---ww.. _
~~.-----ww-----w-+-,,--n----. _mmm=~
l f
i
- f. COMPONENT: Valves
( IMPORTANCE
\ KNOWLEDGE OF: R0 SR0
. T h e o ry o f : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2* 2.5*
safety va1ves.................................................. 2.3* 2.5*
re l i e f v a l v e , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 3
- 2. 5*
l gate va1ves_................................................... 1.9 2.1 l globe va1ves................................................... 1.9 2.1 rupture drives................................................. 2.0 2.2*
Ope ra t i o n o f : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2
- 3.5*
safety va1ves.................................................. 3.0* 3.2 l relief va1ves.................................................. 2.9* 3.1
- gate valves.................................................... 2.4 2.6 globe va1ves.................................................. 2.4 2.7 rupture drives................................................. 2.5* 2.5 F u nc ti o n s o f : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 2* 3.5*
l
[ safety va1ves.................................................. 3.1 3.2 l' relief valves.................................................. 2.9 3.1 gate valves.................................................... 2.1 2.2 globe valves................................................... 2.1 2.2 rupture drives................................................. 2.3* 2.6*
~'
C ha rac te ri s ti c s o f: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 0* 3.2*
safety va1ves.................................................. 2.6 2.7 relief va1ves.................................................. 2.6 2.7 l gate valves.................................................... 2.0 2.1
( globe valves................................................... 2.0 1.9 rupture drives................................................. 2.1* 2.2*
- Constructionof:.................................................... 2. 0 2.0 l
l safety valves.................................................. 1.6 1.8 l relief valves.................................................. 1.6 1.8 i gate va1ves.................................................... 1.6 1.7 l globe va1ves................................................... 1.5 1.7 rupture drives................................................. 1.5 1. 7 Definition of wire drawing (valve seat erosion)..................... 1.9 2.1
, Relationship of valve position to flow rate and controlled pressure level.............. . ............................................ 2.2 2.4 Characteristics of c i' srent types of controls for valves: . . . . . . . . . . 2.7 2.9
/'~'g Pneumatic (diaphragm or piston)..................................... 2.2 2.4
'( ) Motor (electric pneumatic-hydraulic). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2 2.4 Manual (wheels-knobs-cranks-chain-level)............................ 2.2 2.3 K/A catalog A-1
_ ~ ~ , , , - ,- - --_,,,, -..,._,-_ , ., , . , , . _ - . . , , , - - - - , - - , , , , - - - - - , , _ y, , , ,.
COMPONENT: Valves IMPORTANCE KNOWLEDGE OF: R0 SR0 Valve design for a given failed-valve position (open, closed, and as-is positions; spring-loaded valves; hydraulic, pneumatically con-trolled valves; electric motor-driven valves)....................... 2.9 3.1 Significance of stem position (valve status) for gate valves........ 2.7 2.9 Applications of gate, globe, flapper, needle, diaphragm, ball, check, relief and float va1ves...................................... 2.0 2.2 Safety concerns in the use of gate valves (protect valve seals, open slowly)............................... ............................. 2.1 2.2 Pneumatic controllers for valves checked for air leaks.............. 1.6 1.8 Use of a variator................................................... 2.7? 2.7?
Use of a manual stop to hold a valve open........................... 2.l* 2.3 Cautions for placing a controller in manual mode isolation, not for throttling... ...................................................... 2.7* 2.5 Emergency operation of MOV with motor inoperable. . . . . . . . . . . . . . . . . . . . 3. 0 3.4 Theory of operation of float valves................................. 1.6 1.6 Construction and operation of float valves....... .................. 1.5 1. 6 Measurement of the time for the inlet valve to reach the indicated full-open position.................................................. 2.4* 2.4 Operation of butterfly valves....................................... 1.9 1.9 The stroke test for a valve, including the use of a stopwatch....... 2.6* 2.4 Principles of operation and purpose of check valves. ............... 2.2* 2.3*
Reason why a valve is timed for a closed-to-open or for an open-closed stroke........ .............................................. 2.1 2.5 Operation of manual valves and verification of position with indi-cator lights........................................................ 2.8* 2.9 Reason for using globe valves for throttling........................ 2.0* 2.2 Difference between spring pressure and system pressure relief valves.............................................................. 2.1* 2.2 O
K/A catalog A-2
[
COMPONENT: Valves IMPORTANCE KNOWLEDGE OF: R0 SRO. <
Construction and use of globe va1ves................................ 1.7 1.9 Difference between safety-related and.non-safety-related valves:
~
safety valves positioned and power supply defused................... 2.9 3.2 i Constant enthalpy expansion through a valve......................... 2.0 2.2 Thermodynamics and flow characteristics of open or leaking valves... 2.0 2. 3 Design philosophy of knocker valves................................. 1.7 1.7 l
l l
K/A catalog A-3 l
l
COMPONENT: Sensors / Detectors IMPORTANCE KNOWLEDGE OF: R0 SR0 Flow Theory of operation of venturis, orifice, annubar (pitot), ball f l oat , a nd ro tame te rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2 2. 5 Temperature compensation requirements............................... 2.4 2.7 Effects of steam on flow rate indicator (steam causes higher-than-actual readings).................................................... 2.2 2.5 Effects of gas or steam on liquid flow rate indications (erroneous reading)........ ................................................ .. 2.2 2.5 Modes of failure........................................... .. ..... 3.0 3.0 Operation of a flow detector........................................ 2.3 2.6 Theory of operation of a D/P cell type flow detector................ 2.1 2.4 Theory of operation of tachometers.................................. 1.4 1.6 Theory of operation of flow detectors................ .............. 1.9 2.0 Level Techniques, theory of operation, and applications of sight glass dip stick; AP across bellows (diaphragms) and bourdon tubes....... . 2.2* 2.3 Temperature / pressure compensation requirements...................... 2.4* 2. 6 Theory of operation of bourdon tube level detectors................. 2.1 2.1 Operation of a bellows type level detector.......................... 2.2 2.3 Operation of a differential pressure level detector................. 2.4 2.5 Calculation of tank capacity in gallons from level reading in feet.. 2.5* 2.4 Effects of operating environment (pressure, temperature, and radiation)...... . ................................................. 2.6 3.0*
Pressure Measurement of pressure relative to a reference pressure to under-stand negative pressure readings.................................... 2.0 2.1 Theory of operation of bourdon tubes, diaphragms, bellows, pistons, and Piezoelectric................................. ................ 2.1 2. 2 K/A catalog A-4
COMPONENT: Sensors / Detectors
{q IMPORTANCE U'1 KNOWLEDGE OF: R0 SR0 Effects of operating environment (pressure, temperature, radiation). 2.5 2.7 Operation of a D/P cell............................................. 2.4 2.6 Theory of operation of pressure detectors........................... 2.1 2.1 1
Theory of operation of a bourdon tube............................... 1.9 2.1 Theory and characteristics of differential measurement systems...... 2.1 2.2 Temperattr_e Theory of operation of T/C, RTD, thermostats, thermometers (expand-ing fluid).......................................................... 2.5 2.6 Indications of fail ure modes of T/C, RTD, thermometers. . . . . . . . . . . . . . 3.0 3.1 R e s p o n s e t i me s . . . . . . . . . . . . . . . . . . . . . . . . . : . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.4 Application of thermo-wells......................................... 1.9 2.1 Application of averaging techniques................................. 1.7 1.8 s
Operation of a potentiometer........................................ 1.9 2.0 Position Detectors Failure modes of reed switches, LVDT, limit switches, and ,
potentiometers...................................................... 2.3 2.4 l Principles and applications for reed switches, magnets, LVDT, poten-l tiometers, and limit switches....................................... 2.2 2.2 Speed Sensors Failure modes of tachometers........................................ 1.9 2.0 Application of tachometers.......................................... 1.7 1. 7 Electrical Applications of voltmeters, ammeters, frequency, and ground detectors........................................................... 2.1* 2.2*
Nuclear Instrumentation Theory of operation of fission chambers, ion chambers (UIC/CIC BF3/810) GM......................................................... 2.7 3.0 Q Units of measure for power range indications........................ 2.9 3.0 K/A catalog A-5
I COMPONENT: Sensors / Detectors IMPORTANCE KNOWLEDGE OF: R0 SR0 Effect of voltage changes on neutron detector performance........... 2.9 2.9 Failure modes of fission chambers, ion chambers, and proportional counters............................................................ 3.1 3.1 Miscellaneous Principles of operation of fire, seismic, vibration, humidity, acoustic, photo-electric, and optical (fuel handling)............... 2.2 2.4 Operation of vibration meter and strobe tachometer.................. 1.7 1. 9 Theory of operation of the gross failed-fuel detector, including the radioactive elements that are measured and the transit time from the reactor core to the detector.......... ......................... 2.4 2.7 O
O K/A catalog A-6
n COMPONENT: Controllers and Positioners
( IMPORTANCE
( - KNOWLEDGE OF: R0 SR0 Effects of changing the control and alarm setpoints on major compo-n e n t s a n d sy s t e m s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2 3.2 Effects on major components and systems of changes in the control and alarm setpoints................................................. 3.1 3.0 Effects of isolation or failure of controllers and positioners on major components and systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 3. 2 Function and characteristics of flow controller in manual and auto-matic modes......................................................... 2.5 2.7 Function and characteristics of a speed controller.................. 2.3 2.3 Function and characteristics of a loadlimit controller.............. 2.1 2.1 Characteristics of controller indicators. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 2* 2.4*
Operation of a valve controller, including seal-in features......... 2.3* 2.2 Location of controllers and of controller indications............... 3.0* 3.0*
Function of pressure regulator bypass valves........................ 2.3 2.3
\
) Function and characteristics of pressure and temperature controll-ers, including pressure and temperature control valves.............. 2.3 2.4 Function and characteristics of air-operated valves, including fail-ure modes........................................................... 2.8 3.1*
Function and characteristics of valve positioners. . . . . . . . . . . . . . . . . . . 2.2 2.2 Indicator units..................................................... 2.2* 2.2 Characteristics and surveillance of time-to-close or time-to-open for certain valves.................................................. 2.2 2.6*
Function and characteristics of governors and other mechanical contro11ers......................................................... 2.3 2.6 Safety precautions with respect to the operation of controllers and positioners......................................................... 2.5 2.7 Theory of operation of bistable components.......................... 2.2 2.4 i
Veri fication of power supply to valve motors. . . . . . . . . . . . . . . . . . . . . . . . 2. 7 2.9 Theory of operation of potentiometers............................... 1.6 1.7 v
K/A catalog A-7
COMPONENT: Controllers and Positioners IMPORTANCE KNOWLEDGE OF: R0 SR0 Theory of operation of controllers; including the different types (electronic, electrical, pneumatic, governors, and mechanical)...... 1.9 2.1 Theory of operation of controllers, including the different con-trolled variables (speed, flow, temperature, pressure).............. 1.9 2.1 Theory of operation of indicators, including failure modes. . . . . . . . . . 2.4* 2. 6 Principles of modes of operation of controllers, including propor-tional, proportional and reset, proportional and integral........... 2.2 2.4 O
O K/A catalog A-8
n)
(V COMPONENT:
KNOWLEDGE OF:
Pumps - Centrifugal IMPORTANCE R0 SR0 Identification, symptoms, and consequences of cavitation............ 3.4 3.6 Reasons for venting a centrifugal pump.............................. 3.2 3.2 Consequences of air binding......................................... 3.1 3.3 Consequences of operating a pump dead headed or for extended recir-culation times...................................................... 3.1 3.3 Identification of improper system operation on pump characteristic pressures and flows................................................. 2.9 3.2 Indication of runout conditions..................................... 3.1 3.1 Pump performance curve interpretation............................... 2.7* 2.8*
Relative relationships between flow and each of the following: head pressure, power, speed.............................................. 2.6 2.6 Quantitative relationships between flow capacity and speed, pump haad and speed, pump power and speed................................ 2.1 2.2 O Need for net positive suction head (NPSH); effects of loss of (w suction.............................................................3.4 3.6 Starting current and operating current interpretation............... 3.0 3. 2 Purpose of starting a pump with discharge valve closed.............. 3.0 3.0 Pressure and flow relationship of pumps in parallel................. 2.4 2.4 Pressure and flow relationship of pumps in series. . . . . . . . . . . . . . . . . . . 2.3 2.5 Consequences of operating at runout conditions...................... 2.5 2.9 Definition of pump shutoff head..................................... 2.2 2.2 Head curves for centrifugal pumps and how they are experimentally obtained............................................................ 1.9 1. 9 Definition of runout................................................ 2.2 2.2 Definition of pump differential pressure............................ 2.1 2.3 Definition, identification, and need for leak-off of pump packing... 1.9 2.2 Identification of adequate lubrication / cooling...................... 2.5 2.7
! ) Establi shad s ec.i rculating setpoints. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1* 2.1*
%./
K/A catalog A-9
COMPONENT: Pumps - Centrifugal IMPORTANCE KNOWLEDGE OF: R0 SR0 Pressure flow-rate relationships for series and parallel ficw path operations... .....................................................2.1 2.3 Head curves for centrifugal pumps and how they are experimentally obtained............................................................ 1.8 2.0
" Runout" of a centrifugal pump (definition, causes, effects, and corrective measures).......................... ..................... 2.5 2.6 Venting centrifugal pumps while filling system...................... 2.7 2.7 Thecry of operation and behavior of centrifugal pumps in systems servicing multiple components....................................... 2.3 2.3 Principles of operation of a centrifugal pump....................... 2.5* 2.7 Consequences of loss of suction on a centrifugal pump.. . .. ....... 3.0 3.1 Definition and application of Bernoulli's general energy equation... 1.4 1.5 Units and characteristics of fluid flow............................. 1.7 2.0 Relationship between flow from a pump and suction and discharge heads............................................................... 1.9* 2.1 Principles of a centrifugal pump, including effect of loss of flow through pump..... .................................................. 2.5 2.7 i
O l
K/A catalog A-10 l
l
,ex COMPONENT: Pumps - Rotary Vane
( ) IMPORTANCE
'x_ /
KNOWLEDGE OF: R0 SR0 Safety precautions associated with rotary vane pumps............... 2.0* 2.1*
Consequences of water intake (reduces vacuum capability)............ 2.1 2.1 Function and characteristics of rotary vane pumps....... ........... 1.9* 1.9 Construction of a rotary vane pump.................................. 1.5 1.6 Relationship between flow and amperage for rotary vane pumps. . . . . . . . 1.7 1. 6 Theory of operation of rotary vane pumps. . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7 1.8 Theory of operation of vacuum pumps................................. 1.6 1. 7 i r\
i \
\ /
~
l ,
I
\ /
)
'mJ K/A catalog A-11
COMPONENT: Pumps - Positive Displacement IMPORTANCE KNOWLEDGE OF: R0 SR0 Relationship of head, flow, speed, and power requirements for a positive displacement pump.................. ... ................... 2.3 2.3 Net positive suction head (NSPH) requirements for a positive dis-placement pump................................. .................... 2.7* 2.7*
Pump performance curve interpretation............................... 1.9 2. 2 Consequences of operating a positive displacement pump against a closed flow path....................................... .. ... ..... 3.4* 3.3 Indication of runout conditions..................................... 2.6 2.6 Functions and characteristics of positive displacement pumps........ 2.3 2.6 Operation of a pump against a shutoff head.......................... 3.3* 3.5 Reason for starting a positive displacement pump with the discharge valve open ; need to cl ear the flow path. . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1* 3.1*
Safety procedures and precautions associated with positive displace-ment pumps.......................................................... 3.1* 3.3*
Basic operation of positive displacement pumps...................... 2.4 2.4 Theory of operation of positive displacement pumps.................. 2.5* 2.4 O
K/A catalog A-12
rN COMPONENT: Pumps - Venturi IMPORTANCE
(\~ ') KNOWLEDGE OF: R0 SRO Consequences of loss of motive fluid to a venturi pump, steam jet a i r ej e c to r , e t c . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5
- 2.5 Areas of high pressure and low pressure in a venturi pump and re-sultant var.uum or pump motive power (suction)....................... 1.9 2.0 Function and characteristics of jet pumps and steam jet air ejectors (venturi pumps)..................................................... 1.9 2.0 Need for jet pumps free from cracks or breaks (jet pump integrity).. 1.6 1.6 Cons tructi on o f ventu ri pumps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 6 1.8 Safety precautions associated wi th venturi pumps. . . . . . . . . . . . . . . . . . . . 2.1 2.2*
Theory of operation of venturi pumps................................ 1.9 2.1 Application of Bernoulli's theorem to the high-velocity / low pressure phenomenon in a venturi pump........................................ 1.6 1.8 O
V b)
( s-I I
K/A catalog A-13 1
f COMPONENT: Motors IMPORTANCE KNOWLEDGE OF: R0 SR0 Locked motor rotor, recognition from motor parameters............... 2.7 2.8 Use of motor / pump performance curves to determine flow from amperage. 2.1 2.1 Potential consequences of overheating motor insulation or motor bearings................ ........................................... 2.6 2.7 DC and AC motor control circuits........... ........................ 1.9 2.1 Causes of excessive current in motors, such as low voltage, overload-ing, and mechanical binding......................................... 2.3 2.5 Relationship between pump motor current (ammeter reading) and the following: pump fluid flow, head, pressure, speed, and stator tem-perature............................................................ 2.2 2.4 Definition of electromotive force and counter EMF as it applies to motors.............................................................. 1.5 1. 5 Use of equations relating applied voltage to motor current and counter EMF......................................................... 1.4 1.7 Starting current and operating (running) current in a motor......... 2.9* 2.9 Reason for limiting the number of motor starts in a given time period.............................................................. 3.1* 3.3 Location and interpretation of the following:....................... 2.7* 2.7*
Motor stator temperature indicator and alarm...... ............ 2.6* 2. 7 Motor amperage meter........................................... 2.9 3.0 Motor bearing temperature indicator and alarm.................. 2.7* 2. 8 Motor controllers, breakers, alarms, and switches.............. 2.5 2.6 Motor over-current trips (phase and ground).......... ......... 2.5 2.6 Motor running lights........................................... 3.0* 3.0 Line diagrams for power to major motors............................. 2.7* 2.8 Definition of voltage, current, impedance........................... 2.0 1. 9 Theory of operation of de motors, ac single phase-motors, 3 phase motors, induction motors, and synchronous motor..................... 1.7 1.9 Basic electrical symbols and circuits............................... 2.2 2.6*
Theory of an ac induction motor..................................... 1.7 1. 9 Load sharing among generators on a system........................... 2.1* 2.2*
K/A catalog A-14
COMPONENT: Motors
- /'~'N IMPORTANCE KNOWLEDGE OF: R0 SR0 Relationship between secondary thermal power and generator true power............................................................... 1.9 2.0
- Definition of synchronous speed..................................... 1.7 1.9 Definition of generator power factor................................ 1.7 1.8 Electrical units; volts, amps, ac, dc, and hertz.................... 2.2 2.3 Theory of operation for M/G sets.................................... 2.0 2. 3 T h e o ry o f a c ge ne ra to r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.2 Definition of frequency-synchronous frequency....................... 1.9 1.9 Definition of reactive current reactive power. . . . . . . . . . . . . . . . . . . . . . . 1.8 2.0 Definition of power factor / reactive power. . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.1 Theory of operation of rod drive motors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.2 DefinitionofVARs.................................................. 1. 7 1. 9 I\
\s_ /
Series and parallel dc circuits..................................... 1.6 1.6 Electrical theory of pump amperage (normal and startup) and locked-motor amperage...................................................... 2.2* 2.2 De f i ni ti on of open ci rcui t. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.1 Principles of operation of rod drive motor (magnetic jack or roller nut)................................................................ 2.1 2.3 Consequences of overexcited /underexcited............................ 2.2 2.7 I
v K/A catalog A-15
COMPONENT: Heat Exchangers and Ccodensers IMPORTANCE KNOWLEDGE OF: R0 SR0 Startup/ shutdown of a heat exchanger.................. ....... ..... 2.7* 2. 7 Verification of main condenser backpressure... . ... .. . ... .. 2.7 2. 7 Proper filling of a shell-and-tube heat exchanger. . ......... ..... 2.5 2.6 Location and operation of the following components:. ...... ... . 3.0* 3.2*
All heat exchangers in the plant............. .. ........ . . 2.4* 2.6 Valves and valve switches which control flow through the heat exchangers.......................................... ........ 2.S* 2.7*
Cool-leg and hot-leg temperature sensors and their normal oper-ating temperature range..... ... ..... ....... ........... . 3.2* 3.3 Basic heat transfer in a heat exchanger....... ...... ..... ... .. 2.4 2.7 Effects of heat exchanger flow rates that are too high or too low.. 2.4 2.6 Flow paths for the heat exchanger (counterflow and U-type). .. .. .. 2.0 2.2 Construction of the heat exchanger (shells, tubes, plates, etc.). 1. 7 1. 9 Heat exchanger temperature limits; control of heat exchanger temperatures.... .......................... ........... . ... . 2.6 2.7 Design basis for heat exchanger system operating temperature limits. 2.2 2.5 Relationship between inlet and outlet flow rates and temperatures. 2.2 2.6 Working properties of water (entropy, enthalpy, pressure, etc. ). . . . 2.0 2.1 Definition and appl'eation of Bernoulli's general energy equation. . 1.6 1. 7 Definition of thermal r. hock....................... ..... .. ..... . 2.4 2.7*
Units and characteristics of fluid flow................ .. .. ... . . 2.0 2.1 Principle of operation of a barometric condenser....... ..... . . . 1. 8 1. 9 Heat exchanger formula:
q=VA (T-out - T-in).......................... . ... . .. 2.0 2. 2 Relationship of various temperature scales (Fahrenheit, Celsius, Rankine, Kelvin).......................................... ......... 2.2 2.4 Principles of heat transfer.................... ...... . ... .. . 2.3 2.4 O
K/A catalog A-16
--. -- = -_ - . - - - -. -
p COMPONENT: Heat Exchangers and Condensers
- i IMPORTANCE V KNOWLEDGE OF: R0 SR0 Pressurized water reactor heat transfer formula (RCS to S/G)........ 2.1 2.4 Relationships of pressure, volume, temperature in a mixture of l i q u i d a n d wa te r v a p o r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.3 Basic heat conduction and convection. .............................. 2.3 2.5 Definition of latent heats of vaporization and condensation. . . . . . . . . 2.2 2.7 Principle of operation of condensers................................ 2.4* 2.4 Relationship between condenser vacuum and backpressure.............. 2.3 2.6 Heat transfer in heat exchangers.................................... 2.4 2.2 Relationships of pressure, volume, temperature in a mixture of liquid and water vapor..... ........................................ 2.1 2.4 understanding of basic heat conduction and convection............... 2.4 2.5 Definition of latent heats of evaporation and condensation.......... 2.5* 2.8 O Thermodynamics of forming a steam bubble in PZR steam tables........ 2.6* 2.7
!kj 2.1 Characteristics of convection heat transfer. . . . . . . . . . . . . . . . . . . . . . . . . 2. 3 Properties of noncondensable gases in contact with water............ 2.1 2.2 Characteristics of conduction heat transfer......................... 2.2 2.4 Properties of condensable gases in contact with water............... 1.9 2.2 Definition of saturation temperature................................ 3.0* 3.1 Expansion of liquids as temperature increases....................... 2.5 2.5 l Theory of thermal stress............................................ 2.6* 2.6 Basic heat transfer equation........................................ 2.2 2.4 Working properties of water (enthalpy, entropy, pressure, tempera-ture, specific volume, and electrical energy)....................... 2.0 2. 3 Pressure, temperature, and volume relationships of liquid associated with nitrogen gas................................................... 1.9 2.2
.ressure-temperature relationship for water at saturation and sub-2 O cooled margin....................................................... 3.0* 3.4
(
i \
K/A catalog A-17
COMP 0NENT: Heat Exchangers and Condensers ~
IMPORTANCE KNOWLEDGE OF: R0 SR0 Causes of natural circulation.......... .... ........... .......... 3.7 3.9 Definition of subcooling; use of steam tables to determine.......... 3.7 3.7 Reactor heat transfer under forced and natural circulation.... ..... 3.7 4.0 Principle of cooling by natural convection. . . . . . . . . . . . . . . . . . . . . . . . 3. 2 3.5 Principles of steam quenching............................ . ..... . 2.5 2.7 Relationships among pressure, volume, and temperature of a mixture of liquid water and water vapor............................... ..... 2.4 2. 5 0NB................................................... ............. 3.2 3.5 Theory of steam tables with respect to conditions which cause water to flash to steam.......... ........... . . ....... .. .... ....... 3.1* 3.2 Ideal gas 1aws............................... ........... . . . . . . . 1. 7 1. 9 Boyles' Law and Charles' Law............................. .......... 1.7 1.7 Relationship between condenser vacuum and backpressure.............. 2.4* 2.5 Definitions of subcooled and saturated liquids....... ... .......... 3.1* 3.2*
Steam tables, including subcooled, saturated, and superheated regions.................................. ............. .. ......... 3.1* 3.2 Use of steam tables in determining condition of fluid in PZR........ 3.2* 3.4 Working properties of water (entropy, enthalpy, pressure, etc.)..... 2.2 2.5 Relationship between accumulator volume and pressure................ 2.5 2.6 Principle of cooling by evaporation................................. 1.9 2.3 Difference in pressure-temperature relationship between the water /
steam system and the water / nitrogen system.......................... 1.8 2.1 Theory of heat transfer within a heat exchanger (AT, flow rate)..... 2.2 2.4 Steam tables, including subcooled, saturated, and superheated regions............................................................. 3.1* 3.4 Definition of a saturated liquid.................................... 3.3 3.5 Characteristics of conduction and convection processes.............. 2.7 2.9 Use of steam tables to determine saturation pressure for a given temperature and vice versa........................ ...... .......... 3.1 3.4 K/A catalog A-18
COMPONENT: Heat Exchangers and Condensers
) IMPORTANCE 6
V KNOWLEDGE OF:
R0 SR0 Principle of vacuum drag............................................ 1.8 2.1*
Determination of degrees of subcooling using temperature and press-ure indications for a primary coolant............................... 3.6* 3.7 Application of steam tables to determine saturation conditions (in specific reference to subcooling determination)..................... 3.2* 3.6 Heat transfer formulas for primary and secondary coolant............ 2.1 2.4 Hot channel factors................................................. 2.4 2.9 Thermodynamics of water and steam, including the subcooled margin, superheat and saturation............................................ 2.9* 3.0*
Pressure-temperature relationship in a saturated system............. 3.3 3.5 Water hammer and methods of prevention.............................. 3.1* 3.2 Definition of hydraulic shock....................................... 2.2 2.4*
Definition and effects of departure from nucleate boiling (DNB)..... 3.4* 3.7 Meaning of enthalpy, saturated and superheated...................... 3.1* 3.2
(
Ef fects of pressure on a solid system. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6 3.8 l
l l
1 i
i l
i I
l l
l l
l l
l
\
l K/A catalog A-19 I
l L
COMPONENT: Demineralizers and Ion Exchangers IMPORTANCE KNOWLE0GE OF:
R0 SR0 Effect of excessive differential performance...................... pressure on demineralizer
................................... 2.2 2.5 Effect of exces'sive temperature on resin............................ 2.6 2.7 Definition of channeling in a demineralizer......................... 2.1 2.3 Reason for filling and venting demineralizer after resin change..... 1.9 2. 4 Reason for performing volumetric verification of i demineralizer.....................................solated ..................1.7 1. 9 Factors which can cause an increase in corrosion product activity... 1.9 2. 3 De f i ni ti on o f c rud bu rst. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 0 2. 3 Demineralizer characteristics that can cause a change in boron concentration....................................................... 2.9 3. 3 Reason for bypassing demineralizer in abnormal dilution situation... 2.9* 3.1 Reason for using mixed-bed demineralizers to process primary water.. 2.0 2. 2 Reasons why using a mixed-bed demineralizer may cause a reactivity transient........................................................... 2.9 3.1 Reactivity effects of boron......................................... 3.6 3.6 Purpose of the high-tem demineralizer..........perature divert valve associated with cation
............................................. 2.5* 2. 7 Reason for notifying chemist of demineralizer status change. . . . . . . . . 2.1 2.5 Need for uniform resin distribution....................... ......... 1.8 2. 0 Possible release of waste water to the environment during r2 genera-tion cyc1c.......................................................... 1.9 2.4 Plant evolutions which can cause crud bursts........................ 2.2 2.7 Effects of flow rate on the removal rate of corrosion activity in a mixed-bed demineralizer.................procuct .............. 1.8 2.3 Function of domineralizer resin..................................... 1.9 2. 2 Ca tion deminera li zer flow l imi ts. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 8 2.0 Operation of cation demineralizer bypass valve...................... 1.9 2.1 Fact that demineralizer used in primary system can be a source of radiation because of radioactive filtration. . . . . . . . . . . . . . . . . . . . . . . . . 2.6 2.8 K/A catalog A-20
ex I COMPONENT: Demineralizers and Ion Exchangers
- d KNOWLEDGE OF
IMPORTANCE R0 SR0 Characteristics of the following items: . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 5 3.0*
Mixed-bed demineralizer........................................ 1.7 2.1 Deep-bed demineralizers........................................ 1.8* 2. l*
Septum demineralizers............... .......................... 1.7* 2.0*
Diatomateous earth demineralizers.............................. 1.7 1. 9 Interpretation of local mixed-bed demineralizer valve position indicator........................................................... 1.9 2.1 Reason for flushing a demineralizer................................. 1.9 2.1 Purpose of a demineralizer.......................................... 2.4 2.7 Reason for sampling inlet and outlet of demineralizer............... 2.2 2.6 Purpose of demineralizer D/P gauge.................................. 2.1 2.4 Reason for mixed-bed demineralizer temperature and flow limits...... 2.2 2.4 Safety precautions associated with diatomateous earth demineralizers. 2.1 2. 2
()
( /
Safety precautions associated with deep bed demineralizers. . . . . . . . . . 2.2 2.2 Safety precautions associated with septum domineralizers............ 2.2* 2.2 Maximum specified purification flow rates through demineralizer..... 2.2 2.4 Procedures regarding the shifting of mixed-bed demineralizers....... 2.2 2.2 Principles of demineralizer operation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 7 1. 9 liigh-flow alarm setpoint for a mixed-bed demineralizer. . . . . . . . . . . . . . 2.0 2.2 Operation of throttle valve on domineralizer output. . . . . . . . . . . . . . . . . 1.6 1.9 Definition of " boron saturated" as it relates to a domineralizer.... 2.5 2.7 Domineralizer D/P to determine condition of demineralizer resin bed., 2.1 2.3 De f ini tion o f demineral i zer D/P. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 2.0 Differences between L10ll and 110l1 demineralizers..................... 1.6 1.9 Chemical processes in mixed-bed demineralizer....................... 1.5 1.8 Function of lon exchange by resin type.............................. 1.5 1.9 O
Definition of ion exchange and appilcation to corrosion.............
(v) 1.4 1. 7 De f i n i t i o n o f f i l t ra t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 5 1. 6 K/A catalog A-21
COMPONENT: Demineralizers and Ion Exchangers IMPORTANCE KNOWLEDGE OF: R0 SR0 Theory of operation of a mixed-bed demineralizer..............'...... 1.7 1.9 Theory of operation of a deborating demineralizer................... 2.0 2.2 Construction and function of a cation demineralizer................. 1.6 1.9 Function of a deep-bed demineralizer................................ 1.7* 1. 7
- Theory of operation of a deep-bed demineralizer..................... 1.6* 1. 6*
Construction of a deep-bed demineralizer............................ 1.4* 1. 5*
Construction, function, and theory of operation of a diatomateous earth demineralizer................................................. 1.5* 1.8*
Construction, function, and theory of operation of a septum demineralizer....................................................... 1.6* 1. 9
- ABILITY T0:
Verify which ion exchanger is in service and which is to be placed into service........................................................ 2.4 2.3 Convert spent resin storage tank level in inches to gallons using a graph............................................................... 1.9* 1.9*
Use the soluble poison control OP to calculate the required total flow through the deborating demineralizer........................... 2.0 2. 2 Apply ion exchange to corrosion protection.......................... 1.7 2. 0 Purify: involves filtration as well as ion removal.................. 1./ 1. 7 Measure water conductivity.......................................... 2.0* 2.1*
O K/A catalog A-22
rm COMPONENT: Breakers, Relays and Disconnects (V') KNOWLEDGE OF:
IMPORTANCE R0 SR0 Theory of operation of pneumatically operated circuit breakers. . . . . . 1.6 1. 8 Functions, characteristics and construction of electrical breakers, including differences between MCC bus breakers, high, medium, and low voltage breakers (equipment isolation, overload protection, interlocks to prevent closure while racked out) and two position and three position breakers......................................... 1.7 1.8 Basic functional theory of circuit breakers. . . . . . . . . . . . . . . . . . . . . . . . . 1.7 1.9 Basic construction of MCC load breakers............................. 1.5 1.7 Constructi on o f brea ke rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 4 1.4 Purpose and procedure for racking out breakers (de energize com-ponent and associated control and indication circuits).............. 2.6 2.9 Control room indication of a breaker being racked out............... 2.7 2.8 Local indication that breaker is open, short or tripped free........ 2.9* 2.9 g Meaning of power supply circuit breaker indicator lights (green ,
t open, red-closed) and capability to remotely open and close......... 3.1 3.1 O} Operation of various push buttons, switches and handles and the resulting action (trip, close, open, reset) on power su circuit breakers...............................................pply ............. 2.8* 3.1 Function and phration of thermal overload protection device........ 2.2 2.6 Physicalmet/odofoperationofbreakerstorackout(ratchetin, ratchet out)'and of control switches (two position and three-position)........................................................... 2.6 2.6 Location of cir uit breaker racking tools, breaker wrench. . . . . . . . . . . 2.0 2.1 Source of indicating power for circuit breakers..................... 1.8 1. 9 l
One-line diagram of breaker control circuitry....................... 1.6 1.7 Safety procedures and precautions associated with breakers, includ-ing MCC bus breakers, high, medium and low voltage breakers, relays and disconnects..................................................... 2.7* 2.6 Theory of operation of relays....................................... 1.5 1.6 One-line diagrams of breaker control circuitry...................... 1.5 1. 9 Function of flags on front panel of breaker... ..................... 1.9 2.3
- K/A catalog A-23 i
COMPONENT: Breakers, Relays and Disconnects IMPORTANCE KNOWLEDGE OF: R0 SR0 Correct position of switches (e.g., pull-to-lock) during fuse replacement......................................................... 2.3* 2.3 Loca ti o n o f l o c k-o u t re l ays . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1* 2.3 Effects of closing breakers with current out of phase, different frequencies, high voltage differential, low current, or too much 1oad................................................................. ?.9* 3.1 Effect of racking out breakers on control and indicating circuits (may lose valve position indication) and removal of control power on breaker operation (disaH es remote operation of breaker)......... 2.7* 2. 9 Functions, characteristics and construction of disconnects... .. ... 1.6 1.5 Controls and precautions associated with disconnects................ 2.2* 1. 9 Purpose and operation of "rackout" and "tagout" of circuit breakers. 2.9* 2.7 Procedure for racking in high voltage circuit breakers.............. 2.6* 2.6*
Operation of power supply ci rcuit breakers. . . . . . . . . . . . . . . . . . . . . . . . . . 2. 0 1. 9 Basic functional theory of circuit breaker.......................... 1.7 1. 8 Function, control, and precautions associated with disconnects...... 2.2* 2.1 Theory of operation of pneumatically operated circuit breakers...... 1.7 1. 8 Theory of operation of MCC (bus) breakers, power supply circuit breakera, high, medium and low voltage circuit breakers............. 1.6 1. 7 Operation o f motor-operated disconnects. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 9 1. 7 O
K/A catalog A-24
i u s Ni cL EmE tuts.Tomy commission i nE-oat NuMsER e.tu.sR., e, noC. a v., =. . .,,,,,,
cFoRMsas E',"3$'- BIBLIOGRAPHIC DATA SHEET NUREG-1122 q sE. .NiiRuct,04:O~v EREvERs, 2 TITLE AND Sv8 TITLE 3 LE AVE 8 LANK
'l Knowledges and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors e DATE REPORT COMPLETED MONTH vtAR
. Auf ORisi luly 1985 6 DATE REPORT ISSutD MONTM YEAR July 1985 F, PERFORMING ORGANIZATION NAME AND MAILING ADORESS (f=4earle C dr1 8 PROJECTsT ASK1NORE UNIT NUMBER Division of Human Factors Safety Office of Nuclear Reactor Regulation ' ' ' ' " ' " ' ' ' " " ' ' "
U.S. Nuclear Regulatory Connission Washington, DC 20555
- 10. SPONSORING ORGANi2AflON NAME AND MAILING ADDRE$$ (tw4 dele C.ses 11a YVPE OF REPORY Same as #7 D PERIOD COVERED lisectensnee deeps, 12 SUPPLEMENT AR v NOTES
- 13. ASSTR ACT f100 e.sas .r 'esst This document catalogs roughly 5300 knowledges and abilities of reactor operators and
,A, senior reactor operators. It results from a reanalysis of a much larger job-task
(" ) analysis data base compiled by the Institute of Nuclear Power Operations (INP0). Know-ledges and abilities are cataloged for 45 major power plant systems and 38 emergency evolutions, grouped according to 11 fundamental safety functions (e.g., reactivity control and reactor coolant system inventory control). With appropriate sampling from this catalog, operator licensing examinations having content validity can be developed.
A structured sampling procedure for this catalog is under development by the Nuclear Regulatory Commission (NRC) and will be published as a companion document, " Examiners' Handbook for Developing Operator Licensing Examinations" (NUREG-ll21). The examina-tions developed by using the catalog and handbook will cover those topics listed under Title 10, Code of Federal Regulations, Part 55.
14 DOCUMLNT ANAk v54 - . stE vvv0RDS DESCRiPTORS is Avail AstLa T V Examinations, Power Plant Operators, PWR, Training Unlimited 16 S Cumity CLa5SiFICaf SON i n .s , ,,,
. ,oiNei 1 Ri>OPEN ENo.D vERMs Unclassified a r-e ,,
() Unclassified
, , wM.E R O. , Aas ie PRa($
)