ML20236N448

Rev 3 to Emergency Operating Procedures, Training Course Syllabus

ML20236N448
Person / Time
Site:	Point Beach
Issue date:	01/21/1987
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20236N340	List: ML20236N337 ML20236N430 ML20236N441 ML20236N448 ML20236N466
References
TRCR-31.0, TRCR-31.0-R03, TRCR-31.0-R3, NUDOCS 8711160170
Download: ML20236N448 (26)

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ATTACHMENT 4 The Emergency Operating Procedure training course syllabus contained in'this attachment is a part of our Control ~0perator training program. Our operations

. training program received Institute of Nuclear Power Operations (INPO) accredi-tation in August 1986. This accreditation provides additional assurance that this training program and course are effective.

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EMERGENCY OPERATING PROCEDURES 1.0 GOALS _

To teach the operator the background information which supports the actions associated with the emergency procedures; to explain how the emergency procedures, emergency r:ontingency actions, and the critical safety procedures ar'e organized. To train operators in the use and understanding of these procedures.

2.0 DESCRIPTION

2.1 Prerequisite An employee enrolled in the Emergency Operating Procedures Course should be enrolled in the COT initial training program and have completed the following courses: Reactor Theory, Thermodynamics &

Heat Transfer, Fluid Mechanics, Primary Systems, Electrical Systems, Instrument Systems, Secondary Systems, Integrated Operations, Transient & Accident Analysis, and Technical Specifications.

2.2 Length of Course The Emergency Operating Procedures course is approximately 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> long.

2.3 Syllabus The Emergency Operating Procedures course includes the following instructional units: i IU-01 Organization & Format IU-02 Overviews IU-03 Application of E0P's .

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- 3.0 EVALUATION.

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A written; exam measuring-the objectives will beigiven at the completion of each instructional unit.' A grade of -80% will~ be . considered passing.

{ Failure of.the IU - written exam will result in:

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~ . 3 .~ 1 - The training coordinator: interviewing the trainee to determine-the.

problem.  ;

~I 3 '. 2 The trainee completing a self_ study period with access to an

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instruc Trainee, tor for questions / answers. passing a retake exam.(>80%) prior.to the

'3.3.

- 4' 0 TASK MATRIX ,

Task' matrix - attached as Appendix 1.

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TRCR 31.0 j IU-Ol' l ORGANIZATION & FORMAT .

-1.0 TERMINAL OBJECTIVES C7023 COT T Given a set of Emergency Operating Procedures and a listing of NUREG - 0737 requirements. Identify those requirements that directly effect the structure of the EOP's.

I C7025 COT T- Given a set of Emergency Operating Procedures analyze . the format and organization of the E0P's by idcotifying the various transition paths between procedures and the established priorities of various groups of procedures.

C7026 COT T Given'the specific events covered by the Emergency Operating '

Procedures evaluate additional analysis conducted by the ,

Westinghouse owners group to satisfy the NUREG requirements to determine what events beyond the FSAR are covered by  !

event specific E0P's.

C7024 COT T Given a set of Emergency Operating Procedures apply the procedural rules of usage to the E0P's by performing procedural steps in proper sequence making correct- .

i transitions to sequence through the E0P's to a termination point. .

'2.0 ' DESCRIPTION 2 .' 1 Prerequisites None 2.2 Lesson Plans NOTE: LESSON PLANS TO BE TAUGHT IN THIS ORDER.

LP0160 (183101LP1), " Westinghouse Owners Group & Rigulatory Requirements" LP0159 (183101LP2), " Procedure Organization & Network" LP0158 (183101LP3), " Procedure Format & Usage" 3.0 EVALUATION Enabling objectives are addretssed in the self assessments of r,ach lesson plan. There'are no quizzes associated with classroom lesson plans.

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TRCR 31.0 IU-02 J l-OVERVIEWS n

1.0 -TERMINAL OBJECTIVES 'l C7032 COT.T Given any of the Emergency Operating procedures, recognize the purpose and applicability of.that procedure by I

! identifying the major objective.and identifying the plant  ;

! conditions to which the. procedure applies. '!

C7033 COT.T Given any of the Emergency Operating Procedures, analyze the major action co egories.by classifying the procedural steps.

into major action categories.

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2.0 DESCRIPTION

2.1 . Prerequisites TRCR 31.0,'IU-01 2.2 ' Lesson Plans' NOTE: LESSON PLANS TO BE TAUGHT IN THIS ORDER.

LP0390 (183102LP1), " Overview of E0P's"

'LP0391 (18~102LP2),

s " Overview of ECA's" l LP0392 (183102LP3),'" Overview of CSP's" f 1

. 3.0 EVALUATION Enabling objectives are addressed in the self assessments of each lesson plan. There are no quizzes associated with classroom lesson plans, j FOR INFDDIAT10RONLY 1 i

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-l 2 I APPLICATION'0F E0P's

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j jl'0 -TERMINAL OBJECTIVES; C7001 COT T From an operating condition with the reactor critical diagnose a reactor trip including ~the. identification of the

'cause using all'available~ control 1 room alarms and indications.

'C7002 COT T From an operating plant condition.at power, diagnose.a i safety injection actuation including the identification.of the cause using all available control room alarms and indications.

C7003COTLT From an' operating condition with the reactor critical, f

> assess the response of-the plant to a reactor trip by. I verifying the response of all automatic actions.- i

'C70'04 COT T Under operating plant conditions'at power, assess the response of thc. plant:to a lafety injection' actuation by; '

verifying the proper response of all automatic' actions. 1 1

C7005 COT.T Under'any plant condition, at power or shutdown, diagnose a loss. of all-'AC power by identifying the cause' and _ duration of the power. loss using all available indications on site q and communications.with. system operations. ')

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C7006 COT T .From'any plant condition in which all AC power has been ,

lost, recognize the immediate actions to respond to the loss of power by ' verifying that all' associated .i.unediate actions are ' accomplished in accordance with ECA-0.0, " Loss of ~ All AC

-Power."

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- q C7007 COT T From an operating plant conditions with the reactor at power i recognize an ATWS by identifying the cause and result of the

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ATWS using all available control room alarms and indications. I i

~C7008 COT T From an operating plant condition with the reactor in a critical condition, recognize.the immediate. actions to: -I respond to an ATWS event by verifying that all immediate I actions are accomplished in accordance with CSP-S.1, ;i

" Response To Nuclear Poder Generation /ATWS." l l

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- TRCR 31.0 IU-03 Page 2 C7009 COT T From 4.ny plant condition following a reactor trip or safety injection actuation recognize the critical safety functions -

by vetifying that all safety related parameters are  ;

satisfied in accordance with the critical safety function status trees.

C7010 COT T From operating plant conditions at power following a reactor  !

trip and safety injection recognize a loss of secondary )

coolant by verifying the. diagnostic conditions listed in j E0P-0. " Reactor Trip or Safety Injection."

C7011 COT T From operating plant conditions at power following a reactor trip and safety injection recognize a SGTR bysverifying the diagnostic conditions listed in EOP-0, " Reactor Trip or Safety Injection."

C7012 COT T From operating plant conditions at power following a reactor )

trip and safety injection recognize a LOCA by verifying the l diagnostic conditions listed in EOP-0, " Reactor Trip or {

Safety Injection."

C7015 COT T During emergency or accident conditions the operator must be  :

able to diagnose high RCS activity using available RMS indications and requesting sample analysis.

C7024 COT T Apply the procedural rules of usage to the PBNP E0Ps.

C7027 COT T During emergency conditions assess the automatic actions j required to verify the proper operation of the reactor  ;

protection and safeguards system in accordance with emergency operating procedures.  ;

C7028 COT T During an accident or emergency condition involving a team generator recognize multiple casualties so they may be identified and their priorities established according to E0P, Emergency Contingency Actions.

C7029 COT T During multiple accidents involving a steam generator tube rupture assess the applicability of either a subcooled or saturated recovery by considering availability of water inventory and the concern for preventing steam generater overfill.

C7030 COT T During an accident condition involving a steam generator tube rupture diagnose a failure of all pressurizer pressure control systems from inability to control pressurizer pressure as directed by the Emergency Operating Procedures.

FOR INFORMtJION ONLY

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- IU-03 Page.3-f C7031 COT T- 3

.During'an accident condition assess ~aLfailure of containment-sump recirculation capability in terms.of maintaining core ,

O -cooling. j l

I 1 C7032 COT T. tRecognize the purpose and applicability of each EOP.

C7033 COT;T'

- Analyze the' major. action. categories of each EOP.

.P7001 COT.T During'an accident condition respond to a loss-of reactor t '

coolant by. performing the actions described =in thel Emergency

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-Operating Procedures (EOP-1, " Loss of' Reactor _or Secondary Coolant").. ,

=P7002 COT T lDuring emergency conditions' vent the RV head following an accident, in accordance.with CSP-I.3.

4 P7003 COT T. ~ During an accident condition respond to a' loss' of secondary M coolant by performing actions: described in the' emergency

. operating procedures-(EOP-2, " Faulted' Secondary Coolant").

' P7004 COT. T'. During an accident condition response to,a steam' generator tube: rupture by performing actions described in the

+: emergency operating procedures (EOP-3, " Steam Generator Tube g Rupture").

P7005 COT T' During emergency: conditions respond to a reactor coolant

-leak,~in accordance'with AOP-1A.

P7006 COT T' During'an emergency or: accident condition respond to a reactor; trip by performing the actions described in the

. emergency. operating procedures _(ECP-0, " Reactor Trip or Safety Injection'; EOP-0.1, "Reactar Trip Response")-

'P7007 COT T Following an. emergency plant' condition recover from an inadvertent SI.by- performing the actions listed in E0P-1 1, l "SI Termination."

'P7009 COT T During'an emergency or accident condition, respond to a loss of offsite power by performing actions directed by the Emergency Operation Procedures (Actions found in several specific Emergency Operath g Procedures).

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-P?O10 COT T- During an emergency'or accident condition respond to a station' blackout by performing the actions directed by  ;

'ECA-0.0, " Loss of All AC Power."

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,P7022 COT T: During'accidentjcondition respond to SGTR contingencies in-accordance with'the ECA-3 series of. procedures'.

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n P7023 COT T' -During a large LOCA when. transfer to containment sump

recirculation;isfrequired, respond to a loss of-containment' J sump. recirculation capability in accordance'with ECA-1.1,. l

" Loss of Containment Sump Recirculation' Capability.d j

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, P7024 COT T2 During.an' emergency condition requiring.a reactor trip when a reactor trip fails to occur, respond to an ATWS in accotdance'with steps identified in' CSP-S.1, " Response to nuclear Power Generation /ATWS."

P7025 COT T During an accident condition respond to inadequate core.

cooling by performing actions in accordance'.with critical

safety procedures'(CSP-C.1, " Response to Inadequate' Core Cooling"). l P70'27 COT T During an emergency condition respond'to a turbine generator; trip in accordance: w.i th guidelines established in E0P-0.1, ,

" Reactor Trip Response." l i

,P7028 COT;T During an' accident condition involving loss of all feedwater- 4 to both SG's, respond to a loss of all feedwater in  !

'accordance with steps identified in CSP-H.1,>"Rer,ponse?to-Loss of Heat Sink." .

CO206 COT T During accident conditions: analyze the effect 'of a loss 'of high head SI on the. RCS after:SI action in terms of the effect.on core cooling and guidance available for protective.

action.

l CO209 COT T Considering accident' conditions which include safeguards actuation, analyse the effect of a loss of the'PWST on the

- RCS in terms of how it' effects core safety and what direction is available to respond to'the loss of RWST.

I CO210 COT T Considering accident conditions which include safeguards actuation, analyze the effect of'a loss of the BAST on the RCS in terms of how it effects core safety and reactivity. ;1 C0212 COT T During emergency plant conditions involving a reactor trip analyze the effect of & loss of DG on the RCS with normal supply unavailable in terms of its effect on limiting the  ;

availability of required protection and safeguards equipment.  ;

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. TRCR 31.0 IU-03 Page 5 1

CO217 COT T During an accident condition the operator must be able to analyze the effect of a LOCA on RCP operation in terms of RCP operating criteria and the effect of continued RCP operation.

CO218 COT T 'During an accident condition the operator must analyze the i effect of inadequate core cooling on the reactor fuel in -

terms of fuel temperatures and the adverse results in '

excessive temperature.

C0219 COT T During emergency conditions, analyze the effect of a LOCA on A the containment. Satisfactory understanding should include  !

the containment design limits and sump capacity.

CO225 COT T During an emergency involving a reactor trip from power .

operation recognize the need to maintain subcooling margin {

on natural circulation in terms of its effect on core j cooling and in terms of procedure applicability.

CO226 COT T Considering all availchle control board indications, recognize-the need to monitor incore TC's and wide range RTD;s while on natural circulation considering the conditions that make TC's and RTD's more accurate than other related indications.

CO227 COT T Following an emergency condition recognize the need to

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maintain cooldown rates while en natural circulation in terms of adverse effects to the RCS of excessive cooldown.

CO228 COT T During accident conditions involving-safeguards actuation 3 diagnose inadequate core cooling by using available safety

.nonitoring equipment.

CO229 COT T Considering accident conditions in which primary inventory is lost, assess various means of core cooling as addressed j in CSP-C.1, " Response to Inadequate Core Cooling" in terms l of their effectiveness and potential hazards, i l

CO234 COT T During accident conditions of either a secondary fault or a l LOCA, the operator must be able to discriminate between over- l cooling and LOCA indications to effective diagnose and j implement the appropriate E0P.

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CO235 COT T. 'Following an emergency-or accident condition when SI is.no longer needed the operator should recognize when operation of the reactor coolant gas vent system is desirable by  :

identifying conditions in the reactor vessel using available.  !

indications and considering the potential problems of- j venting the RCS.  !

CO237 COT T During an emergency condition recognize the importance of obtaining representative samples of baron during natural circulation'to verify adequate shutdown margin and anticipate the effects.of active vs. inactive regions of the j core. ,

i C0502 COT T 'During an accident condition with SI in service the operator mustLassess the loss of RHR on.the SI system with respect to

. low head injection cooling and recirculation capabiAlty.

l C0508 COT T During an accident condition the operator should assess the ,

response of the.RHR system to a safeguards actuation signal to determine expected RHR flow rate in relation to system  !

pressure.

- C0514 COT T During an accident condition the operators must be able to diagnose inadequate suction for the RHR pumps from the RCS '!

hot leg, RWST or containment recirculation sump. d C0602 COT T. During.an emergency or accident condition the operator must be able to recognize the need for SI actuation in accordance with the criteria established per the Emergency Operating i Procedures.

C0604 COT T During emergency or accident conditions, the operator must be able to diagnose malfunctions of the SI system that inhibit any function of the SI system.

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C0608 COT T During a small or large break LOCA assess SI system response by verifying all automatic safeguards components actuate as required and that system parameters such as flow, temperature and pressure follow expected system characteristics.

C0609 COT T During a major steam line break either inside or outside containment assess SI system response by. verifying all automatic safeguards components actuate as required and that

,. system parameters such as flow, temperature and pressure l' follow expected system characteristics.

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!- , l l . TRCR 31.0 l IU-03 i Page 7 C0610 COT T- .During a major steam generator tube rupture (resulting in SI actuation) assess SI system response by verifying all  !

automatic safeguards components actuate as required and that i system parameters such as flow, temperature and pressure follow expected system characteristics. -i C0612 COT T During an emergency or. accident condition the operator must be able to recognize conditions for blocking automatic SI actuation as identified in the Emergency Operating Procedure.a.

C0613 COT T During an accident condition involving SI actuation analyze the relationships among RCS pressure, SI flow and break flow i using available indications to verify equilibrium or transient conditions and to determine adequate core cooling conditions.

C0615 COT T During emergency or ac ident conditions the operator must be able to recognize conditions for terminating or resetting SI as identified in the Emergency Operating Procedures.

C0616 COT T During an emergency or accident condition use safety related temperature and pressure indications (i.e., ASIP Subcooling Meter) to diagnose a loss of subcooling to less then the minimum required subcooling margin.

C0617 COT T Using Control board indication and the ASIP panel assess the 8 response of pressurizer level, pressure and subcooling margin after SI actuation. These parameters should be maintained within the lirr.its identified on the foldout page.

C0701 COT T During an emergency or accident condition diagnose a stuck open PORV or safety based on the response of the PRT and associated instrumentation. ,

C0705 COT T During an emergency or accident condition discriminate between a leaking PORV and pressurizer safety by analyzing tailpipe temperature indications and acoustic monitor response.

C1013 COT T During an accident or emergency condition, recognize and diagnose the formation of a steam bubble in the reactor vessel head using available indications such as the reactor vessel level indicating system pressure level and RCS subcooling meter. a msm a n , e E M 8dl m kp. n Q n WwpeMI hSf M B V ybbd!I h diW i ]bO !sl Nli!20 M E %h D

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TRCR 31.0 IU-03 Page 8 C1401 COT T During emergency or accident conditions analyze indications to determine reactor coolant co litions using available control room indications.

C1403 COT T During an emergency or accident condition assess the response of the incore thermocouple to a LOCA by using the thermocouple indications to determine the effect of safeguards systems or providing core cooling.

C1404 COT T During an accident conditions use the thermocouple indications to relate changes in core exit temperatures to ,

I changes in core conditions by detecting subcooled, ' saturated or a core uncovery condition.

C1405 COT T During emergency plant operations which require monitoring of subcooling indication, the operator should recognize the effect of a loss of the incore thermocouple on the subcooling monitor.

C1406 COT T 'During emergency plant operations the operators muet apply TS and procedural requirements associated with the incore thermocouple, concerning their minimum availability and maximum indicated temperatures.

C1805 COT T During normal and emergency conditions identify malfunctions of containment ventilation systems, in accordance with OP-9C .

and E0Ps. ,

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C1904 COT T After initiation of containment spray due to a LOCA or steam break assess the trends of containment temperature and press to determine the effectiveness of the containment spray system.

C1905 COT T During an emergency or accident condition, determine the need for initiation of containment spray by assessing the conditions of containment pressure against availability of the containment spray system and its suction source.

C1912 COT T During an accident condition assess the response of the containment spray system to an actuation signal by verifying proper actuation of system components and verifying proper flow characteristics of spray and caustic additive.

I C2408 COT T During an accident or emergency condition recognize the significance of a loss of a steam generator on the heat removal capability and the importance of the remaining steam generator to removing decay heat.

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. TRCR 31.0 IU-03 Page 9 C2409 COT T During an accident condition involving a loss of main feedwater the operator must predict the effect on the steam generator in relation to steam generator-level, pressure and j heat removal capability. l C2410 COT T During an ernrgency or accident condition assess the effect of a loss of' auxiliary FW.on the steam' generator in terms of its effect on maintaining decay heat removal capability.

C2411 COT T During an emergency or accident condition assess the effect-of a main steam line break on the steam generator in terms of expected pressure and level response in the steam generator and its availability for removing decay heat.

C2412 COT T During an emergency or accident condition assess the effect of a main feed line break on the steam generator in terms of expected pressure and level response and its availability for removing decay heat.

P4010 COT T During an emergency or accident condition respond to a loss of feedwater, in accordance with E0Ps.

C2413 COT T During emergency operation the operator must recognize the effect on the steam generator caused by a turbine trip as a means to verify proper response following the trip.

C2414 COT T During emergency operation the operator must recognize the effect on the steam generator due to a reactor trip as a means to verify proper response following the trip.

C2416 COT T During emergency operation the operator must analyze the effect of the MSIV closure on the steam generator in relation to steam generators level, pressure and heat removal capability, C2417 COT T During an emergency or accident condition analyze the effect of a stuck open MS safety or SG PORV on the steam-generator in terms of SG pressure and temperature and its availability as a heat sink to remove decay heat.

C2711 COT T During an accident condition involving a steam line break, the operator must be able to discriminate whetner a steam line break is inside or outside containment by using available containment pressure and temperature indications.

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f. C2712 COT T During an accident condition involving a faulted steam generator the operator must be able to assess the i significance of an MSIV failing to close when required, in l terms of the potential effect to the RCS temperature and pressure.

l' C2713 COT T During an accident condition involving a faulted steam generator the operator must be able to analyze the effect of admitting feedwater to a dry steam generator in terms of the potential effect on the SG components.

C3308 COT T During an emergency or accident condition assess the response of the main lube oil system to a turbine generator ,

trip by verifying necessary responses to prevent turbine damage.

C4209 COT T During a steam generator tube rupture accident analyze the impact of operating the steam driven AFW pumps in relation to the effect it will have on the ruptured SG pressure.

C4304 COT T During an emergency or accident condition assess the response of the diesel generators to an undervoltage ,

condition on a safeguards bus in that the DG must function to provide electrical power to its associated safeguards loads. 4 C4305 COT T- During an emergency or accident condition, diagnose a loss of an AC bus from available control room indications. f C4306 COT T During an emergency or accident condition assess the effect of electrical system malfunctioning on as a result of a loss of power to various electrical components.

C5003 COT T During an emergency or accident condition diagnose causes of changing radiation levels in the plant as a means of identifying causes or locations of specific accidents or emergency conditions.

C7302 COT T From any plant condition operating or shutdown, diagnose conditions requiring safeguards actuation from parameters of pressurizer level, pressurizer pressure, and RCS subcooling. l l

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l TRCR 31.0 IU-03 Page 11 P4315 COT T During an accident condition perform a loss of all AC electrical power with safety injection required, in accordance with the actions identified in ECA-0.2, " Loss of All AC Power Recovery With SI Required "

P4318 COT T During emergency conditions if the DG 2es not start automatically diagnose the condition s..a correct the malfunction.

P0204 COT T During a shutdown condition following an emergency condition establish natural circulation in accordance with the guidelines established in the Emergency Operating Procedures (Steps contained in several specific E0P's).

C7314 COT T During all modes of operation, prioritize problems without error.

2.0 DESCRIPTION

2.1 Prerequisites TRCR 31.0; IU-01, IU-02 2.2 Lesson Plans NOTE: LESSON PLANS TO BE TAUGHT IN THIS ORDER.

LP0405 (183103LP1), " Reactor Trip Response" LPO407 (183103LP2), " Natural Circulation Cooldown" LP1074 (183103LP10),." Diagnostic Principles" LPO435 (183103LP3), " Loss of Coolant Accidents" LPO441 (183103LP4), " Steam Generator Fault & Ruptured Steam Generator" LPO462 (183103LP5), " Loss of All AC Power" LP0079 (183103LP6), "LOCA & Faulted SG, Contingencies" LPO473 (183103LPT), " Steam Generator Tube Rupture Contingencies" LPO488 (183103LP8), " Critical Safety Procedures S, C & I" LP0491 (183103LP9), " Critical Safety Functions HPZ" (183103LP11), "EOP Control Board Hockup Walkthrough" 3.0 EVALUATION Enabling objectives are addressed in the self assessments of each lesson l plan. There are no quizzes associated with classroom lesson plans. l l

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C7024 X --

C7023 X -1 i

C7025 X C7026 X C7009 X ij

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C7002 _

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X C7012 X X CO226  %

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C1912 X l C7003 X C7004 X .

C5003 X j C0701 X C3308 X C7312 X C7314 X C7315 X  ;

C7316 X P7106 X- ,

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C7024  : X C7032 X X

C7033 CO210 X l

CO219 X C7302 X C0705 X CO217 X C0234 X ._

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-TRCR 31.0' p TRCG 31.0 1

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1 Name EMERGENCY OPERATING PROCEDURES

1.0, ORGANIZATION & FORMAT (IU-01)

.[

Lesson Plans-  !

LP0160 (183101LP1), " Westinghouse owners Group'& Regulatory Requirements" ,

.LP0159 (183101LP2), " Procedure Organization & Network"

-LP0158-(183101LP3), " Procedure Format & Usage".

i Performance Measures l

None 2.0' OVERVIEW (IU-02)

, Lesson Plans-LP0390-(183102LP1), " Overview of E0P's" LP0391 (183102LP2), " Overview of ECA's" LP0392-(183102LP3), " Overview of CSP's" Performance' Measures None 3.0 -APPLICATION OF E0P's (10-03) )

Lesson Plans  ;

j LPO405 (183103LP1), " Reactor Trip Response" LPO407 (183103LP2), " Natural Circulation Cooldown" LPO435 (183103LP3), " Loss of Coolant Accidents"  !

LPO441 (183103LP4), " Steam Generator Fault & Ruptured Steam Generator" LPO462 (183103LP5), " Loss of All AC Power" LP0079 (183103LP6), "LOCA & Faulted SG, Contingencies" LPO473 (183103LP7), " Steam Generator Tube Rupture Contingencies" LP0488 (183103LP8), " Critical Safety Procedures S, C & I" '

LPO491 (183103LP9), " Critical Safety Functions HPZ" LP1074 (183103LP10), " Diagnostic Principles" (183103LP11), "EOP Control Board Mockup Walkthrough" l s

P ',(  %.

M9rgi NORMAT!0N DNLY  !

_ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ . _ _ _ _ _ _ _ _ ______________________._____o

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'" < TRCR 31'0 TRCG 31.0 o

'Page 2 i',

-Performance Measures Administrator 'Date Action ,

.P7001 COT T During an accident condition respond

.to a loss.of reactor coolant by performing the actions described in the Emergency Operating Procedures .,j (EOP-1, " Loss of Reactor or Secondary 'i Coolant").

P7002 COT T '

.I "I During emergency conditions vent'the RV head following an accident,-in

'accordance with CSP-I.3.  ;

L

.P7003 COT T l

During an accident condition respond .j to a loss'of secondary coolant by i performing' actions described in the emergency operating procedures .j (EOP-2, " Faulted Secondary Coolant").  !

P7004 COT T

,During an accident condition response to a steam generator tube rupture.by performing actions described in the ';

emergency operating procedures (EOP-3,

" Steam Generator Tube Rupture").

'P7005 COT T' ,

i During emergency conditions respond to a reactor-coolant leak, in  !

accordance with AOP-la.

P7006 COT T During an emergency or accident condition respond to a reactor trip .;

i by performing the actions described $

.in the emergency operating procedures (EOP-0, " Reactor Trip or Safety )

l

. Injection; E0P-0.1, " Reactor Trip }

I Response") 1

?GA!INF0Nif TION ONLY l

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Page'3 jh-

'PerformanceiMeasures Administrator- Date -Action .,

m- 'P7009 COT-T-

'During an~ emergency or: accident

. condition ^,' respond.to a loss

of,offsite power:by performing

>  ; actions directed by-the Emergency.

. Operation Procedures'(Actions found '

=in'several' specific Emergency

~ '

1 Operating Procedures). j u

1 P7010 COT T ' >

i During'an' emergency or" accident condition respond to'a station blackout by performing the actions directed by ECA-0.0, -" Loss of All' 1AC Power."- Ll-4 LP7022 COT T-During accident condition-respond to ' '

SGTR contingencies in accordance with the ECA-3 series'of procedures.- l

'l P7023 COT T

,During'a large LcCA when transfer to 6 . containment' sump recirculation is -1

. required, r.espond to a loss of

'1 containment sump recirculation  !

'y capability in accordance.with ECA-1.1,

" Loss of Containment Sump Recirculation- '

Capability."

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b5 5 / TRCR 31.0 TRCG 31.0 J Page 4 .

. N

-q Performance Measures ' Ackninistrator Date Action' , j

-I 1

- P7024 COT T' During an emergency condition requiring a reactor trip when-a reactor trip' fails to occur, .;

respond to'an ATWS'in accordance with' steps identified-in CSP-S.1,

" Response.to-nuclear Power Genera-tion /ATWS."

l

' P7025 COT T-During an accident condition respond to inadequate core cooling by performing actions'in accordance with critical t

- safety procedures (CSP-C.1, " Response [

to Inadequate Core Cooling"). {

l P7027 COT T f

During an emergency condition respond tola turbine generator trip in

' accordance with guidelines established in E0P-0.1, " Reactor. Trip Response."

P7028 COT T During~an accident' condition involving

. loss of.all feedwater to both SG's, respond to'a loss of all feedwater in accordance with steps identified in CSP-H.1, " Response to Loss of Heat-Sidk." j J

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TRCG 31.0' a Page'.5

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1 Performance Measures' Administrator Date  : Action q

.l P4315 COT.T- ]

'l

'During an' accident condition perform '

T a loss of:all AC electrical power with safety' injection required, in accor-

-dance with the. actions: identified in-'

ECA-0.2, " Loss: of All AC Power Recovery  ;

With SI Required" P4318 COT T j 1

During emergency conditions if the

'DG does not start automatically diagnose the condition and correct the malfunction.

i P0204 COT T

~

During a shutdown condition following-an emergency. condition establish ',

natural circulation in'accordance with the' guidelines established in'the Emergency Operating Procedures-(Steps

. contained in several specific E0P's).

P4010 COT T

.During an emergency or accident' condi-tion, respond to'a loss of feedwater, in accordance with EOPs.

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