ML20134H129

Summary of 850731 Meeting w/C-E Owners Group in Bethesda,Md Re Presentation of Draft Set 2 of Rev 3 to Generic Emergency Guidelines,Status of SER for Set 1 of Rev 3 & Review Process for Emergency Guidelines.W/Attendees List & Viewgraphs

ML20134H129
Person / Time
Issue date:	08/20/1985
From:	Thomas Greene, John Kramer Office of Nuclear Reactor Regulation
To:	Regan W, Ziemann D Office of Nuclear Reactor Regulation
References
NUDOCS 8508280283
Download: ML20134H129 (49)

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DMB NRC PDR PSRB R/F TAGreene AUG 201985 GRMazetis JJKramer MEMORANDUM FOR: Dennis L. Ziemann, Chief DTondi Procedures and Systems Review Branch HBClayton Division of Human Factors Safety William H. Regan, Acting Chief Human Factors Engineering Branch Division of Human Factors Safety FROM:

Thomas A. Greene, Nuclear Engineer Section B - Systems Procedures and Systems Review Branch Division of Human Factors Safety Joel J. Kramer, Sr. Engineering Psychologist Section A Human Factors Engineering Branch Division of Human Factors Safety

SUBJECT:

SUl: MARY OF IIEETING WITH COMBUSTION ENGINEERING OWNERS GROUP FOR EMERGENCY PROCEDURE GUIDELINES A meeting between representatives of Combustion Engineering Owners Group (CECG) for Emergency Procedure Guidelines and the NRC was held on July 31, 1985, in Bethesda. contains a list of attendees. The purpose of the meeting was to present draft Set 2 of Revision 3 to Generic Emergency Guidelines, to discuss the status of the SER for Set 1 of Revision 3 to Generic Emergency Guidelines, to discuss the review process of Generic Emergency Guidelines open issues, and to discuss task analysis supporting Emergency Operating Procedures and Detailed Control Room Design Reviews (DCRDR). A summary of the meeting highlights follows:

A.

The CEOG stated that draft Set 2 of Revision 3 to CEN-152 was not yet ready. The draft is now being reviewed by the CE0G prior to transnittal, and is expected to be available in September 1985. Since the CEOG internal review process is incomplete, this agenda item was deleted. The CE0G did state that the submittal would address six open items. These items were in the area of: Loss of Off-site Power, Natural Circulation, Station Blackout, liVA expansion, charging pumps, and P/T limits.

B.

The staff informed the CE0G that the SSER on Submittal 1 should be completed by the end of August. We noted that the issuance of an SSER was not possible until the staff received the CE0G formal submittal. The CE0G stated that the submittal was sent the early part of July. The CEOG proposed that they send the NRC three copies of their next submittal; one gny te ni_, mmm

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t l'ultiple Addressees AUG 2 01985 C.

It was suggested that some time be added to the schedule so that the staff could review the incorporation of their comments into the guidelines before writing the Safety Evaluation.

D.

The CE0G asked whether the reorganization would effect the review process. The staff stated that new personnel may be involved in the review, but it was not known at this time. The CE0G made it clear that they are interested in minimizing the impact of NRR reorganization on the development of guidelines.

E.

The CEOG asked about the status of their PRA work relating to the emergency procedure guidelines. The central issue is whether probabilistics can be utilized to resolve one or more of the identified open items. The staff indicated that we would try to obtain an NRC position, but suggested that CE0G not standby idle; in particular, we recommended that CE0G submit the PRA material which was being discussed with RRAB informally.

F.

The CE0G presented their methodology and sample results for their

" Generic Information and Control Characteristics Review Program" for discussion. Enclosure 2 contains a copy of their viewgraphs. Following a question and answer session, the staff concluded that the CE0G work was responsive to our concerns stated in an August 29, 1984 meeting with the CE0G relative to the DCRDR, Systems Function and Task Analysis requirement of Supplement 1 to NUREG-0737. The staff finds that this work satisfies this Supplement I requirement for the generic aspects; each CE plant would have to continue the analysis for plant-specific deviations and include appropriate justification for these deviations.

CEOG indicated that a formal submittal of their Generic Information and Control Characteristics Review Program would be made to tile NRC.

1 OrI2 nal signed by i

Original signed by Thomas A. Greene, Nuclear Engineer Joel J. Kramer, Sr. Engineering Section B - Systems Psychologist Procedures and Systems Review Branch Section A Division of Human Factors Safety Human Factors Engineering Branch Division of Human Factors Safety

Enclosures:

1.

List of Attendees 2.

Viewgraphs DW/ TAG 2/CE EP TG SUty cmc, >.DHFS:PSRB DNM$:HFEB DHFS:HFE

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-mg m3 ENCLOSURE 1 LIST CF ATTENDEES Jt'LY 31,1985 COMBUSTION ENGINEERING G. Max P. Hansen R. Pearce G. Bischoff P. Nelson COMBUSTION ENGINEERING CWNERS GROUP J. Tate, SCE W. Bromley, SCE D. Van Tasse11 FPL W. Klein, FPL P. Pieringer, BG&E J. Prichert, SCE C. Williams, SCE J. Becker, NU W. Windecker, FPL R. Fenech, CPC K. Holthaus, OPPD NRC T. Greene G. Mazetis J. Kramer W. Regan R. Ramirez F. Akstulewicz D. Houston L. Beltracchi R. Eckenrode OTHER R. Kirshner, ARD

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ENCLOSURE 2 C-E OWNERS GROUP l

GENERIC INFORMATION AND CONTROL CHARACTERISTICS REVIEW I

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BASED ON THE i

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COMBUSTION ENGINEERING EMERGENCY PROCEDURE GUIDELINES [CEN-152, REVISION 02)

JULY,1985 l

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THE EMERGENCY PROCEDURE GUIDELINE SYSTEM l

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OVERVIEW e

C-E EPGs 00 CONSTITUTE AN ADEQUATE SA515 FOR DETERMINING GENERIC AND PLANT SPECIFIC OPERATOR INFORMATION ANO CONTROL REQUIREMENTS.

e BA515 FOR THIS CONCLUSION 15 IN THE EPG OEVELOPMENT PROCESS AND DOCUMENTATION e

DEVELOPMENT

- INGRE0!ENTS

- SAFETY FUNCTIONS l

- PROCESS

- 3TRATEGY

- H CONSIDERATIONS o

DOCUMENTATION

- TECHNICAL ANALYSE 5

- TRAINING LESSONS

- BASES AND IMPLEMENTATION GU10ANCE e

IMPLEMENTATION SUCCESS 5

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EPG DEVELOPMENT PROCESS e

BEST ESTIMATE TECHNICAL ANALYSES e

PRELIMINARY STRATEGY DEVELOPED BY SYSTEMS DESIGNERS AND ANALYSTS REVIEWE0 AND REFINED BY OPERATIONS PERSONNEL, PROCEDURES e

WRITERS, INSTRUMENTATION AND CONTROL 5 OE5!GNERS.

ANALYTICAL SPECI ALISTS. TRAINING SPECI ALISTS o

EPGs REAUDITED TO ENSURE:

- C0VERAGE OF SAFETY FU NCTIONS

- CORRESPONDENCE TO STRATEGY CHARTS

- NAXIMUM AND APPROPRI ATE UTILIZATION OF SUCCESS PATN5 (CONTROL FUNCTIONS)

- CON 5!0ERATION OF ALTERNATIVE SCHEMES 0 40NITORING TRAN5IENTS o

NRC REVIEW i

o VALIDATION

- SIMPLE AND COMPLEX (MULTIPLE FAILURE) SCENARIOS 9

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SAFETY FUNCTION STRUCTURE OF EPGs t

e INNERENT TOP 00NN APPR0ACM ALL GUIDELINES BASED ON SAFETY FUNCTIONS e

EACM FUNCTION RELATED TO SUCCESS PATNS

- SUCCESS PATHS LINK FUNCTION TO PLANT NARDWARE

- SUCCESS PATHS REFER TO SPECIFIC PARANETERS ANO CONTROL 5

- ALTERNATIVE SUCCESS PATHS PROVIDE BACKUP MEANS OF A55ES$1NG AND FULFILLING EACM FUNCTION o

NUMERICAL CRITERI A USED THROUGHOUT EPGs

- 5AFETY FUNCTION ASSESSMENT

- DECISION CRITERI A (E.G., RCP TRIPPING.

1 TERMINATION) 1

- CRITERIA REFERENCE 0 TO SPECIFIC PARANC

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HIERARCHY OF SAFETY FUNCTIONS REACTIVITY CONTROL RCS

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STANDAR0 POST-TRIP ACTIONS

- IMMEDI ATE ACTIONS FOR ANY POST-TRIP 04 ESF ACTUATIONS e

OPTIMAL RECOVERY GUIDELINES

- TREAT SPECIFIC SYMPT 0M SETS o

FUNCTION AL RECOVERY GUIDELINES

- MAINTAIN PLANT IN SAFE, STABLE CON 0! TION

- IF UNABLE TO IDENTIFY SYMPT 0M SET

- IF SYMPTOM TREATMENT INADEQUATE o

STRATEGY CHARTS o

SAFETY FUNCTION STATUS CHECKS o

RECENT TECHNICAL ISSUES 9

EERGENCY PROCEDURE GUIDELINE SYSTEM NORMAL POWER OPERATION i

i f RT ACTUATED OR REQUIRED SAFETY FUNCTION STATUS CHECK AND STD. POST-TRIP ACTIONS l f i

DIAGNOSE EVENT YES SYMPTOMS NO MATCH EVENT I

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FUNCTIONAL OPTIMAL RECOVERY f MULTIPLE )

RECOVERY 1

FAILURES, (EVENT-SPECIFIC) d DIAGNOSIS (UNDIAGNOSEDJ EVENT

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OVERVIEW OF THE EMERGENCY PROCEDURE GUIDELINE SYSTEM l

NORMAL OPERATION I

REACTOR TRIP ACTUATED OR REQUIRED STANDARD POI ~T TRIP ACTIONS TAKEN TO MAINTAIN CRITICAL SAFETY FUNCTIONS DIAGNOSTIC ACTION FUNCTIONAL RECOVERY REACTOR TRIP

'.C0VERY LOSS OF COOLA.ar ACCIDENT RECOVERY STEAM GENERATOR TUBE RUPTURE RECOVERY STEAM LINE BREAK RECOVERY LOSS OF FEEDWATER RECOVERY l

LOSS OF FORCED CIRCULATION RECOVERY

t OPTINAL RECOVERY GU!OELINE o

STRATEGIC APPROACM FOR SPECIFIC SYMPTOM SET

- EMPHA51ZE5 SPECIFIC SUCCESS PATHS o

SAFETY FUNCTION STATUS CHECK o

JOB PERFORMANCE AIDS o

SAFE SHUT 00WN o

PREVENT CORE DAMAGE. MINIMIZE RELEASES o

TASK SPECIFICATION 9

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FUNCTIONAL REC 0VERY GU!OELINE j

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MAINTAIN SAFE, STABLE CONDITION o

PREVENT CORE OAMAGE, NINIMIZE RELEASE 5

- INDEPENDENT OF SPECIFIC SYMPTOM SET o

PURELY FUNCTIONAL OR SYMPTONATIC APPROACH

- SUCCESS PATHS i

o SAFETY FUNCTION STATUS CHECK i

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SUPNARY e

NRC/CEOG/C-E MEETING OF AUGUST 29, 1984 BASIC PARAMETERS AND CONTROL FUNCTIONS NEEDED TO SATISFY SAFETY FUNCTIONS ARE IDENTIFIED IN CEN-152 TASK SPECIFICATION IN CEN-152 IS NOT SUFFICIENTLY DETAILED TO SUPPORT GENERIC OR PLANT SPECIFIC ICCR I

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INFORMATION AND CONTROL CHARACTERISTICS REVIEW (ICCR) e MULTIDISCIPLINARY TEAM i

e MODEL e PROCESS e EXAMPLE OF PROCESS e PLANT SPECIFIC CONVERSION e

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MULTIDISCIPLINARY TEAM

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e NUREC-0801 SPECIFIES QUALIFICATIONS AND STRUCTURE e REACTOR OPERATIONS e INSTRUMENTATION AND CONTROLS ENGINEERING e HUMAN FACTORS SPECIALIST e OTHER SUBJECT MATTER EXPERTS SYSTEMS ANALYST EXPERTS OPERATIONS EXPERTS

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L GENERIC ICCR ORGANIZATION CHART PROGRAM MANAGERS R.T. PEARCE (C-E) l P.J. HANSEN (C-E)

TECHNICAL ASSISTANT

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D.M. LONGO (C-E)

HUMAN FACTORS I&C SPECIALIST l

SPECIALIETS S.C. RYDER (C-E)

R.H. SHANNON, PhD (ARD)

J.8. WINTER (ARD)

OPERATIONS DESIGN AND ANALYSIS SPECIALISTS SPECIALISTS M.F. GRAMES (C-E)

P.B. KRAMARCHYK (C-E)

P. DELLARCO (C-E)

G. MAX (C-E) l j

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OVERVIEW OF PROCESS PROGRAM ESTABLISH MANAGEMENT E MULTIDISCIPLINARY TEAM sr ESTABLISH CEN-152 MODEL FOR THE REV. 02 ANALYSIS 1r DATA BASE

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MANAGEMENT SYSTEM REFERENCE PLANT DESIGN 9I TASK DEVELOPMENT ir DEFINE I&C REQUIREMENTS v

GENERATE CONSOLIDATED l

I&C LIST I

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e ICCR MODEL

4 ICCR MODEL i

i e GOAL OF ANALYSIS DEFINED EPGs AS STARTING POINT (FUNCTIONAL ANALYSIS) e e EXISTING FUNCTIONAL ALLOCATION ASSUMED e PROCESS DEFINED e REFERENCE PLANT HARDWARE BASIS e TASK CRITERIA e TASK ELEMENT CRITERIA I&C REQUIREMENT CHARACTERISTICS DEFINED e

CAPTURED IN DBMS CODING SCHEME S

6 GOAL OF ANALYSIS TO IDENTIFY THE FUNCTIONAL CHARACTERISTICS OF THE OPERATOR INFORMATION AND CONTROL REQUIREMENTS NEEDED TO SUPPORT EMERGENCY OPERATIONS (AVAILABILITY AND SUITABILITY) e RELIABLY e

VALIDLY IN A MANNER WHICH SUPPORTS PLANT e

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1 REFERENCE PLANT DEFINITION e SUPPORTS THE DEFINITION OF TASK ELEMENTS e SOURCE - DESIGN INFORMATION FOR C-E 2700 MW(t) PLANT e SYSTEM DESCRIPTION FOR EACH SYSTEM e SIMPLIFIED SYSTEM DIAGRAM FOR EACH SYSTEM e COMPONENT LISTINGS L

SYSTEMS OF GENERIC ICCR SYSTEM ABBREVIATION MISCELLANE0US MISC REACTOR COOLANT SYSTEM RCS REACTOR COOLANT PUMPS RCP STEAM GENERATOR S/G MAIN STL41 SYSTEM MSS SAFETY INJECTION SYSTEM SIS CONTAINMENT ATMOSPHERE CONTROL SYSTEM CACS CONTAINMENT ISOLATION SYSTEM CIS FEEDWATER SYSTEMS FWS CHEMICAL AND VOLUME CONTROL SYSTEM CVCS PRESSURIZER SYSTEM PZR PRESSURIZER AND REACTOR VESCEL GAS VENT SYSTEM RGVS REACTIVITY CONTROL (CEA'S, CEDM'S, RPS)

RXCS ELECTRICAL DISTRIBUTION SYSTEM EDS COMPONENT COOLING WATER SYSTEM CCWS l

COMPRESSED AIR SYSTEM CAS I

INTAKE COOLING WATER SYSTEM ICWS STEAM GENERATOR BLOWDOWN SYSTEM DGBS SHUTDOWN COOLING SYSTEM SCS RCS AND STEAM GENERATOR SAMPLING SYSTEM SS NONE NONE i

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SAMPLE COMPONENT LISTING FOR SAFETY INJECTION (SIS -05) 1.

REFUELING WATER TANK 2.

RWT ISOLATION TANK (4) 3.

BLANK 4.

LPSI PUMP (2) 5.

HPSI PUMP (2) 6.

HPSI AND LPSI MINIFLOW ISOLATION VLAVE (4) 7.

SCS HEAT EXCHANGER (2) 6.

SCS HEAT EXCHANGER BYPASS FLOW CONTROL VALVE (2) 9.

SCS HEAT EXCHANGER OUTLET VALVE (2)

10. SCS HEAT EXCHANGER INLET FLOW CONTROL VALVE (2)

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CRITERIA FOR DEVELOPING TASK STATEMENTS 1.

TASKS ARE A SMALL, CONVENIENTLY ANALYZABLE UNIT OF WORK CONDUCTED IN THE CONTROL RCOM WITH RESPECT TO SYSTEMS IDENTIFIED IN THE REFERENCE PLANT DESCRIPTION.

2.

A TASK IS A UNIT OF CONTROL ROOM WORK WHICH IS INDEPENDENT OF THE PRECEDING OR FOLLOWING TASK. THAT IS, ITS CONTENTS AND SEQUENCE OF i

ACTIVITIES WILL REMAIN THE SAME REGARDLESS OF THE OPERATIONAL TRANSIENT IN WHICH THE TASK APPEARS.

3.

A TASK STATEMENT IS BEGUN WITH ONE OF THE TASK VERBS IDENTIFIED IN THE VERB LIST FOLLOWED BY THE OBJECT OF THE VERS. THE OBJECT OF THE VERB MAY BE A PARAMETER (E.G., " DETERMINE PRESSURIZER LEVEL") OR A COMPONENT, SYSTEM OR SUBSYSTEM (E.G., " ALIGN THE SIS FOR COLD LEG INJECTION" OR " ENSURE PROPER HPSI PUMP OPERATION").

4.

TASKS ARE COMPOSED OF 15 OR FEWER UNITS OF HUMAN ACTIONS (TASK i

5.

TASKS SHOULD BE IDENTIFIABLE WITH NO MORE THAN ONE PLANT SYSTEM OR SUBSYSTEM.

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I 6.

THE PURPOSE OF THE TASK (USUALLY IMPLICIT) IS TO MAINTAIN OR RESTORE l

ONE OR MORE RELATED SAFETY FUNCTIONS.

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CRITERIA FOR DEVELOPMENT OF TASK ELEMENTS 1.

TASK ELEMENTS FOLLOW THE SAME VERB - OBJECT FORMAT AS TASK STATEMENTS. THE VERBS ARE CHOSEN FROM THE TASK ELEMENT VERBS ON THE VERB LIST.

2.

TASK ELEMENTS ARE ELEMENTARY HUMAN ACTIONS NEEDED TO ACCOMPLISH A PARTICULAR TASK.

3.

TASK ELEMENTS ARE WRITTEN ONLY FOR HUMAN ACTIONS IN THE CONTROL

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ROOM WHICH REQUIRE THE USE OF A CONTROL ROOM INFORMATION OR CON FUNCTIONS.

4.

A TASK STATEMENT MAY BE USED AS A TASK ELEMENT INSIDE ANOTHER TASK OF GREATER COMPLEXITY.

5.

TASK ELEMENT VERBS MAY BE DIVIDED INTO SENSORY - COGNITIVE OR BEHAVIORAL. THESE CATEGORIES ARE RELATED, RESPECTIVELY, TO INFORMATION AND CONTROL REQUIREMENTS.

6.

EACH TASK ELEMENT REFERS TO ONE AND ONLY ONE INFORMATION OR CONTROL REQUIREMENT.

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A SCOPE OF TASK ELEMENT SPECIFICATION e COMPONENT LEVEL e LIMITED TO CONTROL ROOM INSTRUMENTS AND CONTROLS e BASED ON INFORMATION FROM PRIMARY SOURCE DOCUMENTS SUCH AS:

BEST ESTIMATE TRANSIENT ANALYSES FSAR ANALYSIS BASIC DESIGN DOCUMENTATION e ALL PRACTICAL ALTERNATIVES ARE SPECIFIED

SAMPLE VERB LIST FOR ICCR TASK /

TASK ELEMENT VERB DEFINITION T.

ALIGN

- TO ARRANGE OR CONFIGURE COMPONENTS S0 AS TO LET FLOW OR CURRENT PASS.

T.

BLOCK

- MANIPULATION OF INSTRUMENTATION OR CONTROLS WHICH EITHER RESULTS IN BLOCKING OF THE AUTOMATIC INITIATION OF SYSTEM OR COMPONENT OPERATION.

T.

BYPASS

- ESTABLISHES A PIPING PATH THAT AVOIDS OR IS AUXILIARY TO THE MAIN PATH.

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CALCULATE

- TO MAKE A COMPUTATION. SUGGESTS THE USE OF SIMPLE MATHEMATICS AND RESULTS IN A DETERMINABLE RESULT; E.G., CALCULATE THE RCS BORON CONCENTRATION.

T.

COMPARE

- TO EXAMINE IN ORDER TO NOTE SIMILARITIES EVALUATE OR DIFERENCES te.

CLOSE

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CONTROL

- THE ACT OF REGULATING A PLANT PARAMETER.

CONTROL IS USUALLY PERFORMED BY WAY OF AN INSTRUMENT OR APPARATUS WHICH IS AVAILABLE IN THE CONTROL ROOM, WHICH IN TURN REGULATES A MECHANISM.

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I&C CHARACTERISTICS DEFINITION e TASK ELEMENT POINTS TO THE REQUIREMENT AVAILABILITY e CHARACTERISTICS DEFINE SUITABILITY FUNCTIONAL CHARACTERISTICS e INFORMATION CHARACTERISTICS TYPE OF DISPLAY RANGE

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UNITS ACCURACY AVAILABILITY

. RESPONSE TIME INTERVALS DIVISIONS e CONTROL CHARACTERISTICS TYPE OF CONTROL

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MODE OF CONTROL RANGE UNITS AVAILABILITY RESPONSE TIME e DBMS CODING SCHEME FORCED CHOICE FORMAT

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O DATABASE MANAGEMENT SYSTEM (DBMS) a SUPPORTS ENTIRE ICCR PROCESS e IBM PC, DISKETTE AND HARD DISK e FLEXIBILITY e INPUT: CODED TASK DATA TASK PURPOSE CUE (S)

AFFECTED SAFETY FUNCTION (S)

TASK ELEMENTS AFFECTED COMPONENT AFFECTED SYSTEM ISC CHARACTERISTICS BASES e

OUTPUT / SORTING CAPABILITIES TASK BREAKDOWN TASK ELEMENT INF0/ CONTROL TASK LISTING ISC COMPONENT LISTING CONSOLIDATION e USER FRIENDLY (MENU DRIVEN)

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ICCR PROCESS D

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ICCR PROCESS e WELL DEFINED IN THE MODEL e PROCESS EMBODIED IN DATA BASE SYSTEM e WEEKLY TEAM TECHNICAL REVIEW MEETINGS e PROCESS BOUNDED BY PRE-ESTABLISHED CRITERIA, CODING AND FORMATS O

GENERIC ICCR PROCESS CEN -152 WE LY EMERGENCY PROCEDURE TECHNICAL GUIDELINES REVIEW DEFINE MEETINGS REFERENCE PLANT 9r DEVELOP TASK LISTS d

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TASK IDENTIFICATION 1r TASK INVENTORY i

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TASK ELEMENT IDENTIFICATION II l

CHARACTERISTICS OF BASES l

INFORMATION DOCUMENTED AND CONTROLS U

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GENERIC ICCR PROCESS I&C TASK COMMONALITY TASK CHARACTERISTICS DEVELOPMENT ANALYSIS BREAKDOWN DEVELOPMENT CONSOLIDATION LOCA TASK TASK TASK CONSOLIDATED LISTINGS STATEMENT ELEMENT REQUIREMENTS BY TASK CHARACTER.

SYSTEM SYSTEM 1/EPG COMPONENT TASK ELEMENTS AND 5

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REF. PLANT REF. PLANT ENCOMPASSING TEAM INPUT TEAM INPUT TEAM INPUT CHARACTERISTICS SCENARIOS SCENARIOS ANALYSES

COMBUSTION ENGINEERING TITLE Loss of Coolant EMERGENCY PROCEDURE GUIDELINES page 9 of 24 g, vision 02

• 34. [ Monitor containment radiation levels in order to evaluate environmental releases.

It may be desirable to reduce airborne radiation levels in the containment to minimize environmental releases.]

s

35. E the CSAS has been actuated and containment pressure subsequently falls below [7 psig], Then containment spray should be terminated. Upon termination, the CSS must be realigned and reset for automatic actuation.

The CSS may be manually restarted to control iodine levels in the con-tainment.

36. H plant conditions permit, Then bypass automatic initiation of [MSIS by lowering the setpoint as the cooldown and depressurization proceed.]

37. At [2-4 hours] after the start of the loss of coolant event, th lig I

ment of the [ SIS] for simultaneous hot and cold leg injection should be made, unless the criteria of step 38 can be met before the [4 hour] time limit.

In that case, go to step 38. Verify SIS flow per Figure 5-3.

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• 38. Determine if the conditions for entering shutdown cooling system opera-tion can be established by the following criteria:

a)

Pressurizer level is greater than [100"] and constant or increasing b)

The RCS is at least [20*F] subcooled c)

RCS activity level within [ plant specific limits]

d)

Condensate inventory adequate per Figures 5-4 and 5-5.

e)

[0ther plant specific information insert here, (e.g., compnent cooling water, instrument air, valve control power).]

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• Step performed continuously.

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LOCA 5-9 CEN-152 Rev. 02

SAMPLE FROM LOCA TASK LISTING

33. Control RCS inventory 156. Determine HPSI pump flow to RCS 157. Stop charging pumps 158. Stop HPSI pumps 159. Determine if SIS termination criteria are met

34. Maintain containment isolation 160. Determine containment area radiation status 161. Start containnent spray system operation 162. Stop containment spray' system operation

35. Control containment temprature and pressure 163. Determine containment pressure 164. Stop containment spray system operation 165. Determine containment airborne radiation level 166. Start containment spray system

36. Bypass undesired automatic initiation of plant protection signals 167. Determine if plant conditions permit bypassing MSIS 168. Block MSIS

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37. Control RCS and core heat removal l>

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ijn S}S for simuItaneou[ hot and cold leg n[ectic l

T71. Determine HPSI pu5 flow tolCT -

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38. Control RCS and core heat removal l

172. Determine pressurizer level 173. Determine RCS subcooling 174. Determine RCS fluid radioactivity level 175. Determine condensate inventory 176. [ Plant specific]

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e PORTION OF TASK STATEMENT TABLE CODE TASK STATEMENT 0507 DETERMINE HPSI PUMP FLOW TO RCS 0508 ENSURE PROPER SIS VALVE ALIGNMENT AL'IGN SIS FOR SIMULTANEOUS HOT & COLD LEG INJECT 0510 LIG S FOR COLD LEG INJECTI 0'511 ENSURE SIAS 0512 BLOCK SIAS 0513 DETERMINE CONTAINMENT SUMP LEVEL 0514 STOP HPSI PUMPS 0515 ENSURE RAS 0516 ISOLATE SITS 0517 VENT SITS 0518 DRAIN SITS 0519 DETERMINE IF SIAS IS PRESENT 0520 ENSURE PROPER LPSI OPERATION 0521 DETERMINE LPSI PUMP FLOW TO RCS t

7 j

0522 ALIGN CHARGING PUMPS TO INJECT THROUGH SIS 0601 ENSURE PROPER OPERATION OF CNTMT AIR COOLERS 0602 ENSURE PROPER CNTMT SPRAY OPERATION 0603 DETERMINE CNTMT SPRAY FLOW 0604 START CNTMT SPRAY SYSTEM OPERATION 0605 STOP CNTMT SPRAY SYSTEM OPERATION 9

e e

O G

e 1

1 PORTION OF TASK flWENTORY TABLE l

TA9C CCtt TABLE i

SYSTEM TASK EPS EPS E?S NLTBER CC:E TITLE SF;"Furr r;r tr.m NUMBER 4U?!ER v;M6 R 05 0507 03 17:

0037 05 0507 04 077 Orio?

05 0507 04 03s 0 c; 05 0507 05 C22 06n2 05 0507 05 0:3 2002 05 0507 06 0'5 0>0:

05

?507 06 0:4 0002 05 0507 15 07 0007 05 0507 15 0:5 4t0!

05 0507 18

26 0007 05 0507 18 0:6 AC01 05 0507 24 072 0015

'05 0507 24 058 4C01 05 0507 25 0:4 0007 05 0507 25 0:1 AC01 05 0507 2

011 0003 05 0507 32 085 0004 05 0507 32 09:

0004 05 0507 32 134 0005 05 O!07 lit 0005 05 0508 03 062 0010 05 2508 04 Ci!

00:0 25 0:03 05 07 *-

20;3 O!

050E 009 003 05 0508 20 231 0007

_ 23

5co

s

.ss

'r'c )

" ~ '

( 3[ ' O J0i T Z_ '03_ ' _ 1 D,_

v5 -

'059~ ' ' '?J-W.

05 05 9 32 0:4 120'

):

!Ce

• s t, c.r.n.

05

'5 07

2 NJa 05

'! 0

):

'A'8 05 05:0 0*

'"9 i:4i 05

!!;0 06

'P'

^t'i 05 0510 32 12 3

'01 05 05

0 2

01:

C30:

05 0510 12 059

00 05 0510

?!?

'.00:

05 0510 32 089 0}04 05 0:10

!2 10!

0004 05 0510 22 l02 v20:

05 0511 01

It 0005 05 0511 11 0;;

100:

05 00:

5:01 05 05:1 18

!03

.0)!

05 0!!;

2; 0:5 0000 05 05:1 24 00:

M0;

.nsnr 7n

R e

a 9

e TASK BREAKDOWN REPORT e

E[}_IIILE E[g,$ECI!gy

$((ECIEQ_!6[EILFUNCIlQN!_

LOCA 0037 INVENTORY CONTROL RCS HEAT REMOVAL REACTIVITY CONTROL I6gK_SI6IEUENI 16}K_CQQE }EQ_NUM@EB CUE IN[Q,CQQE

[UBEQ}E ALIGN SIS FOR SIMULTANEQUS HOT & COLD LEG INJECT 0509 170 2

0000740501 TO PREVENT THE CONCENTRATION AND PRECIPITATION OF BORIC ACID IN THE REACTOR VESSEL I6!K_ ELE @ENI!

6((ECIEQ,HSIEU l

CLOSE THE HOT LEG INJECTION ORIf!CE BYPASS VALVE SIS OPEN HPSI HOT LEG INJECTION FLOW CONTROL VALVE SIS ENSURE PROPER SIS VALVE ALIGNMENT (TASK CODE 0508)

NONE DETERMINE HPSI FLOW TO RCS (TASK CODE 0507)

NONE l

l I

c-

9 TASK ELEMENT INF0/ CONTROL CHARACTERISTICS

_TA_S_K_S_T_A_TE_M_EN_T T_A_SK_C_O_D_ E ALIGN SIS FOR SIMULTANEOUS HOT & COLD LEG INJECT 0509 i

AFFECTED COMP INF0/ CONTROL CHARACT.

REMARK}

Io!K_ELEMENJ}JEM M]Mg JJM y3M OPEN HPSI HOT LEG INJECTION FROM CONTROL VALVE SIS 12 CONTROL T.D.C. DISCRETE MODE MANUAL RANGE HIN: SHUT l MAX: OPEN R.T. 1-5 SEC i AVAIL. LOOP l

INF0/ CONTROL CHARACTERISTICS BASES I6S3,SI61EUEgl 16}3,C99E ALIGN SIS FOR SIMULTANEOUS HOT & COLD LEG INJECT 0509 TASK ELEMENT ELEMENT AFFACTED COMPONENT E90EEE. ElEIEU_. hyd@EB,,, ~~~~~~~~~~~~ OPEN HPSI HOT LEG INJECTION FLOW CONTROL VALVE 02 SIS 12 INF0/ CONTROL CHARACT. RA}{S,FQR,[ACH,BEgulREMjNT

IIEd, y3 lye, CONTROL THIS VALVE POSI. ION CONTROL IS A DISCRETE FUNCTION, T

T.0.C. DISCRETE EITHER OPEN OR SHUT. MODE MANUAL THIS VALVE REQUIRES ONLY MANUAL OPERATION IN THIS SEQUENCE RANGE O - 100 PERCENT IS EQUIVALENT TO FULLY SHUT TO FULLY OPEN MIN: SHUT MAX: OPEN R.T. 1 - 5 SEC VALVE IS A 3 INCH GLOBE VALVE, CONTROL TIME OF 1 - 5 SEC SHOULD ADEQUATELY CONTROL HPSI FLOW AVAIL. LOOP REQUIRED FOLLOWING A LOSS OF MAIN GRID POWER, CONTROLLER IS LOCATED OUTSIDE OF CONTAINMENT AND THEREFORE DOES NOT NEED TO WITHSTAND A HARSH ENVIRONMENT 4

r I CONSOLIDATED REPORT of[EgIEp_SISIEU 6((EgIEg,ggyPgNENI SIS HPSI HOT LEG INJECTION CONTROL VALVE !!E_BEgu]BEMENIS 99NJ89L HPSI HOT LEG INJ FLOW VALVE CONTROL TYPE OF CONTROL: CONTINUOUS MODES: MANUAL RANGE: MIN: 0 MAX: 100 UNITS AVAILABILITY: LOOP REACTION TIME: 1-5 SEC INE9BooI19N HPSI HOT LEG INJ FLOW VALVE POS IND TYPE OF DISPLAY: VALUE RANGE: MIN: 0 MAX: 100 UNITS: ACCURACY: 0 - 15% INTERVALS: 20 DIVISIONS: 3 AVAILABILITY: LOOP REACTION TIME: 1-5 SEC -, = -,.

i ,s PRODUCTS e ICCR REPORT WHICH INCLUDES PURPOSE BACKGROUND ICCR METHODOLOGY RESULTS (CONSOLIDATED LIST) METHOD FOR CONVERSION TO PLANT SPECIFIC ICCR SUPPORTING DOCUMENTATION REFERENCE PLANT DESCRIPTION DBMS DESCRIPTION e DISKETTE COPY OF DATA BASE o HARD COPY OF DATA BASE TASK STATEMENT LIST - EPG TASK LISTINGS TASK INVENTORY TASK BREAKDOWN REPORTS I&C CHARACTERISTICS O g -w r -, ,e .---,r

e O 8 O PLANT SPECIFy CogyERSIOg e 4

~ GENERIC TO PLANT SPECIFIC ICCR; RECOMMENDED CONVERSION PROCESS _ DEFINE PLANT DEFINE ANALYSIS REVISE DATA BASE MODEL MANAGEMENT SYSTEM SPECIFIC SCOPE PM.H.ENG PM,H,IC PM.ENG,H i f I I If I f REVISE TASK STATEMENTS, TASK LISTINGS, TASK INVENTORY 4 PM,H,RO,ENG I f DATA ENTRY T ~ i f DEVELOP NEW TASK ELEMENTS AND I&C CHAPACTERISTICS PM,H,RO,IC,ENG I f DATA ENTRY l f SORT NEW I&C REQUIREMENTS BY COMPONENT l T DEVELOP NEW CONSOLIDATED l LIST OF I&C REQUIREMENTS DM.H,R0 LEGEND OF TEAM PARTICIPANTS i f PM - PROGRAM MANAGEMENT DATA ENTRY H - HUMAN FACTORS SPECIALIST T RO - REACTOR OPERATOR 3 g IC - I&C SPECIALIST ENG - DESIGN SPECIALIST 1f T - TECHNICIAN PLANT SPECIFIC I&C REQUIREMENTS l "--------v-

..s

SUMMARY

e C-E EPGs PROVIDE FUNCTIONAL ANALYSIS e GENERIC ICCR IDENTIFIES GENERIC I&C REQUIREMENTS PROVIDES MODEL PROVIDES METHOD AND FORMAT ~ PROVIDES DBMS s PLANT SPECIFIC CONVERSION DEVELOPS INFORMATION AND CONTROL REQUIREMENTS FOR EMERGENCY OPERATIONS SUPPORTS DCRDR AND E0P EFFORTS --n-- - - -, - - - - -.}}